From 5b661195f8312aa89212f0e4745531f568e2ff53 Mon Sep 17 00:00:00 2001 From: "github-actions[bot]" <41898282+github-actions[bot]@users.noreply.github.com> Date: Mon, 13 Jan 2025 13:08:30 +0000 Subject: [PATCH] 2025-01-10 --- exforall/411/41102.x4 | 740 +++++++++++++++++++++++------------------- exforall/411/41106.x4 | 203 ++++++------ exforall/411/41125.x4 | 42 ++- exforall/411/41137.x4 | 60 ++-- exforall/411/41145.x4 | 718 ++++++++++++++++++++-------------------- exforall/411/41147.x4 | 354 ++------------------ exforall/411/41149.x4 | 159 ++++----- exforall/411/41150.x4 | 158 +++++---- exforall/411/41151.x4 | 107 +++--- exforall/411/41157.x4 | 429 +++++++++++++++++------- exforall/411/41159.x4 | 73 +++-- exforall/411/41181.x4 | 47 +-- exforall/411/41193.x4 | 92 +++--- exforall/411/41199.x4 | 342 +++++++++---------- exforall/417/41776.x4 | 606 ++++++++++++++++++++++++++++++++++ 15 files changed, 2430 insertions(+), 1700 deletions(-) create mode 100644 exforall/417/41776.x4 diff --git a/exforall/411/41102.x4 b/exforall/411/41102.x4 index 15505ba10..a9263fb7a 100644 --- a/exforall/411/41102.x4 +++ b/exforall/411/41102.x4 @@ -1,48 +1,55 @@ -ENTRY 41102 20061120 20070521 20060816 4139 -SUBENT 41102001 20061120 20070521 20060816 4139 -BIB 11 24 +ENTRY 41102 20240916 20250110 20250110 4220 +SUBENT 41102001 20240916 20250110 20250110 4220 +BIB 11 29 +TITLE Neutron production cross sections for Fe, Au, and Bi + nuclei at an energy E0=20.6 MeV +AUTHOR (G.A.Prokopets) +REFERENCE (J,SNP,32,19,1980) English translation of YF,32,37 + (J,YF,32,37,1980) Issue 1. + Main reference, cross-sections are given + ((C,80KIEV,2,54,1980)=(R,INDC(CCP)-169,(2),54,1980)) + Level density parameter, nuclear temperatures and some + sigmas are given. INSTITUTE (4UKRKGU) -REFERENCE (J,YF,32,(1),37,198007) Main Reference, Cross-sections - Are Given - (J,SNP,32,19,198007) English Translation Of YF,32,37 - (C,80KIEV,2,54,198009) .Level Density Param, Nuclear - Temperatures And Some Sigmas Are Given -AUTHOR (G.A.PROKOPETS) -TITLE Neutron Yield Cross-sections For The Fe, Au, Bi - Nuclei At The Energy 20.6 MeV -FACILITY (VDG,2SWDSWR) Pulse Van De Graaff Accelerator +FACILITY (VDG,2SWDSWR) Pulse Van de Graaff accelerator INC-SOURCE (D-T) -METHOD (TOF) Flight Base Is 300 cm -DETECTOR (SCIN) Liquid Scintilation Counter +INC-SPECT (EN-RSL-HW) Energy spread due to the geometrical factor + and slowing down in the gas. +METHOD (TOF) Flight base is 300 cm +DETECTOR (SCIN) Liquid scintilation counter MONITOR (1-H-1(N,EL)1-H-1,,SIG) -ERR-ANALYS Error, If Given, Is Total -HISTORY (19920831C) + + COMPILED AT THE CENTRE - CJD + + - (19931021A) Subents 41102011 - 41102016 Deleted Due To - The Fact That Data Given There Are Not Fit - For Exfor Compilation (MEMO 4C-3/369) - Changed Coding In SAN 017 - 021 - (19981111U) .Bib-information Corrected, - Cross-references Added - (20061113A) Correction In According To Memo CP-C/386. +HISTORY (19920831C) + + Compiled at the centre - CJD + + + (19931021A) Subents 41102011 - 41102016 deleted due to + the fact that data given there are not fit + for Exfor compilation (MEMO 4C-3/369). + Changed coding in SAN 017 - 021 + (19981111U) .Bib-information corrected, + cross-references added + (20061113A) Correction according to Memo CP-C/386. M.M. -ENDBIB 24 + (20240916U) Upper -> lower case correction. + Ref. R,INDC(CCP),(2),54,1980 was added. + STATUS information was updated. +ENDBIB 29 NOCOMMON 0 0 -ENDSUBENT 27 -SUBENT 41102002 20061113 20070521 20060816 4139 -BIB 4 5 +ENDSUBENT 32 +SUBENT 41102002 20240916 20250110 20250110 4220 +BIB 5 7 REACTION (26-FE-0(N,X)0-NN-1,,DA/DE) -SAMPLE Hollow Cylinder Of Chemically Pure Iron -STATUS Data Are Taken From 1st Reference,Table 1 -HISTORY (19931021U) New Reference Added - (19981111U) .Reference Deleted -ENDBIB 5 +SAMPLE Hollow cylinder of chemically pure iron +ERR-ANALYS (DATA-ERR) Total uncertainty +STATUS (TABLE,,G.A.Prokopets,J,SNP,32,19,1980) Table 1. +HISTORY (19931021U) New reference added + (19981111U) .Reference deleted + (20240916A) ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 7 COMMON 3 3 -EN EN-RSL ANG +EN EN-RSL-HW ANG MEV KEV ADEG 20.6 93. 90. ENDCOMMON 3 DATA 4 31 -E-MAX E-MIN DATA ERR-T +E-MAX E-MIN DATA DATA-ERR MEV MEV MB/SR/MEV MB/SR/MEV 20.2 17.7 0.24 0.05 17.7 15.6 0.73 0.08 @@ -76,22 +83,24 @@ MEV MEV MB/SR/MEV MB/SR/MEV 0.85 0.6 51. 14. 0.6 0.35 36. 11. ENDDATA 33 -ENDSUBENT 47 -SUBENT 41102003 20061113 20070521 20060816 4139 -BIB 4 5 +ENDSUBENT 49 +SUBENT 41102003 20240916 20250110 20250110 4220 +BIB 5 7 REACTION (79-AU-197(N,X)0-NN-1,,DA/DE) -SAMPLE Hollow Cylinder Of Chemically Pure Gold -STATUS Data Are Taken From 1st Reference, Table 1 -HISTORY (19931021U) New Reference Added - (19981111U) .Reference Deleted -ENDBIB 5 +SAMPLE Hollow cylinder of chemically pure gold +ERR-ANALYS (DATA-ERR) Total uncertainty +STATUS (TABLE,,G.A.Prokopets,J,SNP,32,19,1980) Table 1. +HISTORY (19931021U) New reference added + (19981111U) .Reference deleted + (20240916A) ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 7 COMMON 3 3 -EN EN-RSL ANG +EN EN-RSL-HW ANG MEV KEV ADEG 20.6 93. 90. ENDCOMMON 3 DATA 4 31 -E-MAX E-MIN DATA ERR-T +E-MAX E-MIN DATA DATA-ERR MEV MEV MB/SR/MEV MB/SR/MEV 20.2 17.7 0.70 0.09 17.7 15.6 1.62 0.17 @@ -125,31 +134,38 @@ MEV MEV MB/SR/MEV MB/SR/MEV 0.85 0.6 266. 74. 0.6 0.35 232. 69. ENDDATA 33 -ENDSUBENT 47 -SUBENT 41102004 20070321 20070521 20060816 4139 -BIB 5 11 +ENDSUBENT 49 +SUBENT 41102004 20240916 20250110 20250110 4220 +BIB 5 21 REACTION (83-BI-209(N,X)0-NN-1,,DA/DE) -SAMPLE Hollow Cylinder Of Chemically Pure Bismuth -ERR-ANALYS (ERR-S) Error Due To Statistics Of The Counts - (ERR-2) Error Due To Absorption And Multiple - Scattering - (ERR-3) Error Due To Neutrons Energy Error - (ERR-4) Error Due To Analysis -STATUS Data Are Taken From 1st Reference, Table 1 -HISTORY (19931021U) New Reference Added - (19981111U) .Reference Deleted +SAMPLE Hollow cylinder of chemically pure bismuth +ERR-ANALYS Sources of uncertainties at neutron energy ~ 1.7 MeV: + Statistics of the counts for Bi 1.5 + Correction for energy spread of neutron source 18. + Correction for absorption and multiple + scattering for Bi 5. + Method of analysis 7. + Statistics for np-scattering peak 1. + Correction for absorption and multiple + scattering for np-scattering 3. + np scattering vross section 1. + Relative efficiency of detector 4. + Total uncertainty 21. + (DATA-ERR) Total uncertainty +STATUS (TABLE,,G.A.Prokopets,J,SNP,32,19,1980) Table 1. +HISTORY (19931021U) New reference added + (19981111U) .Reference deleted (20070321U) ERR-1 was chanhed into ERR-S -ENDBIB 11 -COMMON 7 6 -EN EN-RSL ANG ERR-S ERR-2 ERR-3 -ERR-4 -MEV KEV ADEG PER-CENT PER-CENT PER-CENT -PER-CENT - 20.6 93. 90. 1.5 5. 18. - 7. -ENDCOMMON 6 + (20240916A) ERR-ANALYS was corrected. + ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 21 +COMMON 3 3 +EN EN-RSL-HW ANG +MEV KEV ADEG + 20.6 93. 90. +ENDCOMMON 3 DATA 4 31 -E-MAX E-MIN DATA ERR-T +E-MAX E-MIN DATA DATA-ERR MEV MEV MB/SR/MEV MB/SR/MEV 20.2 17.7 0.68 0.16 17.7 15.6 2.20 0.27 @@ -183,458 +199,526 @@ MEV MEV MB/SR/MEV MB/SR/MEV 0.85 0.6 231. 64. 0.6 0.35 103. 31. ENDDATA 33 -ENDSUBENT 56 -SUBENT 41102005 20061113 20070521 20060816 4139 -BIB 5 6 +ENDSUBENT 63 +SUBENT 41102005 20240916 20250110 20250110 4220 +BIB 6 9 REACTION (26-FE-0(N,X)0-NN-1,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Iron +SAMPLE Hollow cylinder of chemically pure iron ANALYSIS (4PI1A) -STATUS Data From Table of 3rd Reference - C,80KIEV,2,54 -HISTORY (19981111U) .Reference Moved To San 001 - (19981111T) .Data Are The Same As In 88019002 -ENDBIB 6 +ERR-ANALYS (DATA-ERR) Total uncertainty +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to San 001 + (19981111T) .Data are the same as in 88019002 + (20240916A) ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 9 NOCOMMON 0 0 DATA 4 1 -EN EN-RSL DATA ERR-T +EN EN-RSL-HW DATA DATA-ERR MEV KEV B PER-CENT 20.6 93. 1.77 20. ENDDATA 3 -ENDSUBENT 14 -SUBENT 41102006 20061113 20070521 20060816 4139 -BIB 5 6 +ENDSUBENT 17 +SUBENT 41102006 20240916 20250110 20250110 4220 +BIB 6 9 REACTION (27-CO-59(N,X)0-NN-1,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Cobalt +SAMPLE Hollow cylinder of chemically pure cobalt ANALYSIS (4PI1A) -STATUS Data From Table of 3rd Reference - C,80KIEV,2,54 -HISTORY (19981111U) .Reference Moved To San 001 - (19981111T) .Data Are The Same As In 88019003 -ENDBIB 6 +ERR-ANALYS (DATA-ERR) Total uncertainty +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to San 001 + (19981111T) .Data are the same as in 88019003 + (20240916A) ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 9 NOCOMMON 0 0 DATA 4 1 -EN EN-RSL DATA ERR-T +EN EN-RSL-HW DATA DATA-ERR MEV KEV B PER-CENT 20.6 93. 1.94 20. ENDDATA 3 -ENDSUBENT 14 -SUBENT 41102007 20061113 20070521 20060816 4139 -BIB 5 6 +ENDSUBENT 17 +SUBENT 41102007 20240916 20250110 20250110 4220 +BIB 6 9 REACTION (41-NB-93(N,X)0-NN-1,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Niobium +SAMPLE Hollow cylinder of chemically pure niobium ANALYSIS (4PI1A) -STATUS Data From Table of 3rd Reference - C,80KIEV,2,54 -HISTORY (19981111U) .Reference Moved To San 001 - (19981111T) .Data Are The Same As In 88019004 -ENDBIB 6 +ERR-ANALYS (DATA-ERR) Total uncertainty +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to San 001 + (19981111T) .Data are the same as in 88019004 + (20240916A) ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 9 NOCOMMON 0 0 DATA 4 1 -EN EN-RSL DATA ERR-T +EN EN-RSL-HW DATA DATA-ERR MEV KEV B PER-CENT 20.6 93. 3.21 20. ENDDATA 3 -ENDSUBENT 14 -SUBENT 41102008 20061113 20070521 20060816 4139 -BIB 5 6 +ENDSUBENT 17 +SUBENT 41102008 20240916 20250110 20250110 4220 +BIB 6 9 REACTION (49-IN-115(N,X)0-NN-1,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Indium +SAMPLE Hollow cylinder of chemically pure indium ANALYSIS (4PI1A) -STATUS Data From Table of 3rd Reference - C,80KIEV,2,54 -HISTORY (19981111U) .Reference Moved To San 001 - (19981111T) .Data Are The Same As In 88019005 -ENDBIB 6 +ERR-ANALYS (DATA-ERR) Total uncertainty +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to San 001 + (19981111T) .Data are the same as in 88019005 + (20240916A) ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 9 NOCOMMON 0 0 DATA 4 1 -EN EN-RSL DATA ERR-T +EN EN-RSL-HW DATA DATA-ERR MEV KEV B PER-CENT 20.6 93. 3.31 20. ENDDATA 3 -ENDSUBENT 14 -SUBENT 41102009 20061120 20070521 20060816 4139 -BIB 5 8 +ENDSUBENT 17 +SUBENT 41102009 20240916 20250110 20250110 4220 +BIB 6 11 REACTION (79-AU-197(N,X)0-NN-1,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Gold +SAMPLE Hollow cylinder of chemically pure gold ANALYSIS (4PI1A) -STATUS Data From Table of 3rd Reference - C,80KIEV,2,54 -HISTORY (19981111U) .Reference Moved To San 001 - (19981111T) .Data Are The Same As In 88019006 - (20061120A) Misprint in Data was corrected in according +ERR-ANALYS (DATA-ERR) Total uncertainty +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to San 001 + (19981111T) .Data are the same as in 88019006 + (20061120A) Misprint in DATA was corrected according to Memo CP-C/378. M.M. -ENDBIB 8 + (20240916A) ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 11 NOCOMMON 0 0 DATA 4 1 -EN EN-RSL DATA ERR-T +EN EN-RSL-HW DATA DATA-ERR MEV KEV B PER-CENT 20.6 93. 5.70 20. ENDDATA 3 -ENDSUBENT 16 -SUBENT 41102010 20061113 20070521 20060816 4139 -BIB 5 5 +ENDSUBENT 19 +SUBENT 41102010 20240916 20250110 20250110 4220 +BIB 6 8 REACTION (83-BI-209(N,X)0-NN-1,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Bismuth +SAMPLE Hollow cylinder of chemically pure bismuth ANALYSIS (4PI1A) -STATUS Data From Table of 3rd Reference - C,80KIEV,2,54 -HISTORY (19981111U) .Reference Moved To SAN 001 -ENDBIB 5 +ERR-ANALYS (DATA-ERR) Total uncertainty +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to SAN 001 + (20240916A) ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 8 NOCOMMON 0 0 DATA 4 1 -EN EN-RSL DATA ERR-T +EN EN-RSL-HW DATA DATA-ERR MEV KEV B PER-CENT 20.6 93. 5.45 20. ENDDATA 3 -ENDSUBENT 13 -NOSUBENT 41102011 19931021 20050926 0000 -NOSUBENT 41102012 19931021 20050926 0000 -NOSUBENT 41102013 19931021 20050926 0000 -NOSUBENT 41102014 19931021 20050926 0000 -NOSUBENT 41102015 19931021 20050926 0000 -NOSUBENT 41102016 19931021 20050926 0000 -SUBENT 41102017 20061113 20070521 20060816 4139 -BIB 5 8 +ENDSUBENT 16 +SUBENT 41102011 20240916 20250110 20250110 4220 +SUBENT 41102012 20240916 20250110 20250110 4220 +SUBENT 41102013 20240916 20250110 20250110 4220 +SUBENT 41102014 20240916 20250110 20250110 4220 +SUBENT 41102015 20240916 20250110 20250110 4220 +SUBENT 41102016 20240916 20250110 20250110 4220 +SUBENT 41102017 20240916 20250110 20250110 4220 +BIB 6 10 REACTION (26-FE-0(N,INL)26-FE-0,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Iron +SAMPLE Hollow cylinder of chemically pure iron ANALYSIS (4PI1A) -STATUS Data Are Taken From The Reference One, Table 3 -HISTORY (19931021A) Changed Coding Of Reaction: Sum Deleted - New Reference Added - (19981111U) .Reference Moved To SAN 001 - (19981111T) .Data Coincides With Those Of 88009002 -ENDBIB 8 +ERR-ANALYS (DATA-ERR) Total uncertainty +STATUS (TABLE,,G.A.Prokopets,J,SNP,32,19,1980) Table 3. +HISTORY (19931021A) Changed coding of reaction: sum deleted. + New reference added + (19981111U) .Reference moved to SAN 001 + (19981111T) .Data coincides with those of 88009002 + (20240916A) ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 10 NOCOMMON 0 0 DATA 4 1 -EN EN-RSL DATA ERR-T +EN EN-RSL-HW DATA DATA-ERR MEV KEV MB MB 20.6 93. 290. 130. ENDDATA 3 -ENDSUBENT 16 -SUBENT 41102018 20061113 20070521 20060816 4139 -BIB 5 6 +ENDSUBENT 18 +SUBENT 41102018 20240916 20250110 20250110 4220 +BIB 5 8 REACTION (27-CO-59(N,INL)27-CO-59,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Cobalt +SAMPLE Hollow cylinder of chemically pure cobalt ANALYSIS (4PI1A) -STATUS Data From Table of 3rd Reference - C,80KIEV,2,54 -HISTORY (19931021A) Changed Coding Of Reaction: Sum Deleted - (19981111U) .Reference Moved To SAN 001 -ENDBIB 6 +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19931021A) Changed coding of reaction: sum deleted. + (19981111U) .Reference moved to SAN 001 + (20240916A) EN-RSL -> EN-RSL-HW +ENDBIB 8 NOCOMMON 0 0 DATA 3 1 -EN EN-RSL DATA +EN EN-RSL-HW DATA MEV KEV MB 20.6 93. 230. ENDDATA 3 -ENDSUBENT 14 -SUBENT 41102019 20061113 20070521 20060816 4139 -BIB 5 7 +ENDSUBENT 16 +SUBENT 41102019 20240916 20250110 20250110 4220 +BIB 5 9 REACTION (41-NB-93(N,INL)41-NB-93,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Niobium +SAMPLE Hollow cylinder of chemically pure niobium ANALYSIS (4PI1A) -STATUS Data From Table of 3rd Reference - C,80KIEV,2,54 -HISTORY (19931021A) Changed Coding Of Reaction: Sum Deleted - (19981111U) .Reference Moved To SAN 001 - (19981111T) .Data Are The Same As In 88019009 -ENDBIB 7 +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19931021A) Changed coding of reaction: sum deleted + (19981111U) .Reference moved to SAN 001 + (19981111T) .Data are the same as in 88019009 + (20240916A) EN-RSL -> EN-RSL-HW +ENDBIB 9 NOCOMMON 0 0 DATA 3 1 -EN EN-RSL DATA +EN EN-RSL-HW DATA MEV KEV MB 20.6 93. 270. ENDDATA 3 -ENDSUBENT 15 -SUBENT 41102020 20061113 20070521 20060816 4139 -BIB 5 8 +ENDSUBENT 17 +SUBENT 41102020 20240916 20250110 20250110 4220 +BIB 6 10 REACTION (79-AU-197(N,INL)79-AU-197,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Gold +SAMPLE Hollow cylinder of chemically pure gold ANALYSIS (4PI1A) -STATUS Data Are Taken From The Reference One, Table 3 -HISTORY (19931021A) Changed Coding Of Reaction: Sum Deleted - New Reference Added - (19981111U) .Reference Moved To SAN 001 - (19981111T) .Data Are The Same As Those In 88009005 -ENDBIB 8 +STATUS (TABLE,,G.A.Prokopets,J,SNP,32,19,1980) Table 3. +ERR-ANALYS (DATA-ERR) Total uncertainty +HISTORY (19931021A) Changed coding of reaction: sum deleted. + New reference added + (19981111U) .Reference moved to SAN 001 + (19981111T) .Data are the same as those in 88009005 + (20240916A) ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 10 NOCOMMON 0 0 DATA 4 1 -EN EN-RSL DATA ERR-T +EN EN-RSL-HW DATA DATA-ERR MEV KEV MB MB 20.6 93. 250. 170. ENDDATA 3 -ENDSUBENT 16 -SUBENT 41102021 20061113 20070521 20060816 4139 -BIB 5 8 +ENDSUBENT 18 +SUBENT 41102021 20240916 20250110 20250110 4220 +BIB 6 10 REACTION (83-BI-209(N,INL)83-BI-209,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Bismuth +SAMPLE Hollow Cylinder of chemically pure bismuth ANALYSIS (4PI1A) -STATUS Data Are Taken From The Reference One, Table 3 -HISTORY (19931021A) Changed Coding Of Reaction: Sum Deleted - New Reference Added - (19981111U) .Reference Moved To SAN 001 - (19981111T) .Data Are The Same As In 88009006 -ENDBIB 8 +ERR-ANALYS (DATA-ERR) Total uncertainty +STATUS (TABLE,,G.A.Prokopets,J,SNP,32,19,1980) Table 3. +HISTORY (19931021A) Changed coding of reaction: sum deleted. + New reference added + (19981111U) .Reference moved to SAN 001 + (19981111T) .Data are the same as in 88009006 + (20240916A) ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 10 NOCOMMON 0 0 DATA 4 1 -EN EN-RSL DATA ERR-T +EN EN-RSL-HW DATA DATA-ERR MEV KEV MB MB 20.6 93. 350. 170. ENDDATA 3 -ENDSUBENT 16 -SUBENT 41102022 20061113 20070521 20060816 4139 -BIB 5 7 +ENDSUBENT 18 +SUBENT 41102022 20240916 20250110 20250110 4220 +BIB 6 9 REACTION (26-FE-0(N,2N),,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Iron +SAMPLE Hollow cylinder of chemically pure iron ANALYSIS (4PI1A) -STATUS Data Are Taken From The Reference One, Table 3 -HISTORY (19931021U) New Reference Added - (19981111U) .Reference Moved To San 001 - (19981111T) .Data Coincides With Those Of 88009003 -ENDBIB 7 +ERR-ANALYS (DATA-ERR) Total uncertainty +STATUS (TABLE,,G.A.Prokopets,J,SNP,32,19,1980) Table 3. +HISTORY (19931021U) New reference added + (19981111U) .Reference moved to San 001 + (19981111T) .Data coincides with those of 88009003 + (20240916A) ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 9 NOCOMMON 0 0 DATA 4 1 -EN EN-RSL DATA ERR-T +EN EN-RSL-HW DATA DATA-ERR MEV KEV MB MB 20.6 93. 740. 80. ENDDATA 3 -ENDSUBENT 15 -SUBENT 41102023 20061113 20070521 20060816 4139 -BIB 5 6 +ENDSUBENT 17 +SUBENT 41102023 20240916 20250110 20250110 4220 +BIB 5 8 REACTION (27-CO-59(N,2N)27-CO-58,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Cobalt +SAMPLE Hollow cylinder of chemically pure cobalt ANALYSIS (4PI1A) -STATUS Data From Table of 3rd Reference - C,80KIEV,2,54 -HISTORY (19981111U) .Reference Moved To SAN 001 - (19981111T) .Data Are The Same As In 88019010 -ENDBIB 6 +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to SAN 001 + (19981111T) .Data are the same as in 88019010 + (20240916A) EN-RSL -> EN-RSL-HW +ENDBIB 8 NOCOMMON 0 0 DATA 3 1 -EN EN-RSL DATA +EN EN-RSL-HW DATA MEV KEV MB 20.6 93. 840. ENDDATA 3 -ENDSUBENT 14 -SUBENT 41102024 20061113 20070521 20060816 4139 -BIB 5 6 +ENDSUBENT 16 +SUBENT 41102024 20240916 20250110 20250110 4220 +BIB 5 8 REACTION (41-NB-93(N,2N)41-NB-92,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Niobium +SAMPLE Hollow cylinder of chemically pure niobium ANALYSIS (4PI1A) -STATUS Data From Table of 3rd Reference - C,80KIEV,2,54 -HISTORY (19981111U) .Reference Moved To SAN 001 - (19981111T) .Data Are The Same As In 88019011 -ENDBIB 6 +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to SAN 001 + (19981111T) .Data are the same as in 88019011 + (20240916A) EN-RSL -> EN-RSL-HW +ENDBIB 8 NOCOMMON 0 0 DATA 3 1 -EN EN-RSL DATA +EN EN-RSL-HW DATA MEV KEV MB 20.6 93. 1050. ENDDATA 3 -ENDSUBENT 14 -SUBENT 41102025 20061113 20070521 20060816 4139 -BIB 5 7 +ENDSUBENT 16 +SUBENT 41102025 20240916 20250110 20250110 4220 +BIB 6 9 REACTION (79-AU-197(N,3N)79-AU-195,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Gold +SAMPLE Hollow cylinder of chemically pure gold ANALYSIS (4PI1A) -STATUS Data Are Taken From The Reference One, Table 3 -HISTORY (19931021U) New Reference Added - (19981111U) .Reference Moved To SAN 001 - (19981111T) .Data Are The Same As In 88009005 -ENDBIB 7 +ERR-ANALYS (DATA-ERR) Total uncertainty +STATUS (TABLE,,G.A.Prokopets,J,SNP,32,19,1980) Table 3. +HISTORY (19931021U) New reference added + (19981111U) .Reference moved to SAN 001 + (19981111T) .Data are the same as in 88009005 + (20240916A) ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 9 NOCOMMON 0 0 DATA 4 1 -EN EN-RSL DATA ERR-T +EN EN-RSL-HW DATA DATA-ERR MEV KEV MB MB 20.6 93. 1250. 280. ENDDATA 3 -ENDSUBENT 15 -SUBENT 41102026 20061113 20070521 20060816 4139 -BIB 5 7 +ENDSUBENT 17 +SUBENT 41102026 20240916 20250110 20250110 4220 +BIB 6 9 REACTION (83-BI-209(N,3N)83-BI-207,,SIG) -SAMPLE Hollow Cylinder Of Chemically Pure Bismuth +SAMPLE Hollow cylinder of chemically pure bismuth ANALYSIS (4PI1A) -STATUS Data Are Taken From The Reference One, Table 3 -HISTORY (19931021U) New Reference Added - (19981111U) .Reference Moved To San 001 - (19981111T) .Data Are The Same As In 88009007 -ENDBIB 7 +ERR-ANALYS (DATA-ERR) Total uncertainty +STATUS (TABLE,,G.A.Prokopets,J,SNP,32,19,1980) Table 3. +HISTORY (19931021U) New reference added + (19981111U) .Reference moved to San 001 + (19981111T) .Data are the same as in 88009007 + (20240916A) ERR-T -> DATA-ERR, EN-RSL -> EN-RSL-HW +ENDBIB 9 NOCOMMON 0 0 DATA 4 1 -EN EN-RSL DATA ERR-T +EN EN-RSL-HW DATA DATA-ERR MEV KEV MB MB 20.6 93. 1100. 280. ENDDATA 3 -ENDSUBENT 15 -SUBENT 41102027 20061113 20070521 20060816 4139 -BIB 5 6 +ENDSUBENT 17 +SUBENT 41102027 20240916 20250110 20250110 4220 +BIB 6 10 REACTION (26-FE-0(0,0),,TEM) -SAMPLE Hollow Cylinder Of Chemically Pure Iron -ANALYSIS .Nuclear Temperature Determination By LECOUTEUR - Method -STATUS Data Are Taken From The Table of 3rd Reference -HISTORY (19981111U) .Reference Moved To SAN 001 -ENDBIB 6 +SAMPLE Hollow cylinder of chemically pure iron +ANALYSIS .Nuclear temperature determination by Lecouteur + method +ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the + article. +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to SAN 001 + (20240916A) ERR-T -> DATA-ERR +ENDBIB 10 NOCOMMON 0 0 DATA 2 1 -DATA ERR-T +DATA DATA-ERR MEV MEV 1.63 0.15 ENDDATA 3 -ENDSUBENT 14 -SUBENT 41102028 20061113 20070521 20060816 4139 -BIB 5 6 +ENDSUBENT 18 +SUBENT 41102028 20240916 20250110 20250110 4220 +BIB 6 10 REACTION (27-CO-59(0,0),,TEM) -SAMPLE Hollow Cylinder Of Chemically Pure Cobalt -ANALYSIS .Nuclear Temperature Determination By Lecouteur - Method -STATUS Data Are Taken From The Table Of 3rd Reference +SAMPLE Hollow cylinder of chemically pure cobalt +ANALYSIS .Nuclear temperature determination by Lecouteur + method +ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the + article. +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. HISTORY (19981111U) .Reference Moved To SAN 001 -ENDBIB 6 + (20240916A) ERR-T -> DATA-ERR +ENDBIB 10 NOCOMMON 0 0 DATA 2 1 -DATA ERR-T +DATA DATA-ERR MEV MEV 1.57 0.24 ENDDATA 3 -ENDSUBENT 14 -SUBENT 41102029 20061113 20070521 20060816 4139 -BIB 5 6 +ENDSUBENT 18 +SUBENT 41102029 20240916 20250110 20250110 4220 +BIB 6 10 REACTION (41-NB-93(0,0),,TEM) -SAMPLE Hollow Cylinder Of Chemically Pure Niobium -ANALYSIS .Nuclear Temperature Determination By Lecouteur - Method -STATUS Data Are Taken From The Table Of 3rd Reference -HISTORY (19981111U) .REFERENCE MOVED TO SAN 001 -ENDBIB 6 +SAMPLE Hollow cylinder of chemically pure niobium +ANALYSIS .Nuclear temperature determination by Lecouteur + method +ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the + article. +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to SAN 001 + (20240916A) ERR-T -> DATA-ERR +ENDBIB 10 NOCOMMON 0 0 DATA 2 1 -DATA ERR-T +DATA DATA-ERR MEV MEV 1.18 0.12 ENDDATA 3 -ENDSUBENT 14 -SUBENT 41102030 20061113 20070521 20060816 4139 -BIB 5 6 +ENDSUBENT 18 +SUBENT 41102030 20240916 20250110 20250110 4220 +BIB 6 10 REACTION (49-IN-115(0,0),,TEM) -SAMPLE Hollow Cylinder Of Chemically Pure Indium -ANALYSIS .Nuclear Temperature Determination By Lecouteur - Method -STATUS Data Are Taken From The Table Of 3rd Reference -HISTORY (19981111U) .Reference Moved To SAN 001 -ENDBIB 6 +SAMPLE Hollow cylinder of chemically pure indium +ANALYSIS .Nuclear temperature determination by Lecouteur + method +ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the + article. +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to SAN 001 + (20240916A) ERR-T -> DATA-ERR +ENDBIB 10 NOCOMMON 0 0 DATA 2 1 -DATA ERR-T +DATA DATA-ERR MEV MEV 1.21 0.15 ENDDATA 3 -ENDSUBENT 14 -SUBENT 41102031 20061113 20070521 20060816 4139 -BIB 5 6 +ENDSUBENT 18 +SUBENT 41102031 20240916 20250110 20250110 4220 +BIB 6 10 REACTION (79-AU-197(0,0),,TEM) -SAMPLE Hollow Cylinder Of Chemically Pure Gold -ANALYSIS .Nuclear Temperature Determination By Lecouteur - Method -STATUS Data Are Taken From The Table Of 3rd Reference -HISTORY (19981111U) .Reference Moved To SAN 001 -ENDBIB 6 +SAMPLE Hollow cylinder of chemically pure gold +ANALYSIS .Nuclear temperature determination by Lecouteur + method +ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the + article. +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to SAN 001 + (20240916A) ERR-T -> DATA-ERR +ENDBIB 10 NOCOMMON 0 0 DATA 2 1 -DATA ERR-T +DATA DATA-ERR MEV MEV 1.05 0.05 ENDDATA 3 -ENDSUBENT 14 -SUBENT 41102032 20061113 20070521 20060816 4139 -BIB 5 6 +ENDSUBENT 18 +SUBENT 41102032 20240916 20250110 20250110 4220 +BIB 6 10 REACTION (83-BI-209(0,0),,TEM) -SAMPLE Hollow Cylinder Of Chemically Pure Bismuth -ANALYSIS .Nuclear Temperature Determination By Lecouteur - Method -STATUS Data Are Taken From The Table Of 3rd Reference -HISTORY (19981111U) .Reference Moved To SAN 001 -ENDBIB 6 +SAMPLE Hollow cylinder of chemically pure bismuth +ANALYSIS .Nuclear temperature determination by Lecouteur + method +ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in the + article. +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to SAN 001 + (20240916A) ERR-T -> DATA-ERR +ENDBIB 10 NOCOMMON 0 0 DATA 2 1 -DATA ERR-T +DATA DATA-ERR MEV MEV 1.14 0.05 ENDDATA 3 -ENDSUBENT 14 -SUBENT 41102033 20061113 20070521 20060816 4139 -BIB 4 4 +ENDSUBENT 18 +SUBENT 41102033 20240916 20250110 20250110 4220 +BIB 4 5 REACTION (26-FE-0(0,0),,LDP) -SAMPLE Hollow Cylinder Of Chemically Pure Iron -STATUS Data Are Taken From The Table Of 3rd Reference -HISTORY (19981111U) .Reference Moved To SAN 001 -ENDBIB 4 +SAMPLE Hollow cylinder of chemically pure iron +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to SAN 001 +ENDBIB 5 NOCOMMON 0 0 DATA 1 1 DATA 1/MEV 5.8 ENDDATA 3 -ENDSUBENT 12 -SUBENT 41102034 20061113 20070521 20060816 4139 -BIB 4 4 +ENDSUBENT 13 +SUBENT 41102034 20240916 20250110 20250110 4220 +BIB 4 5 REACTION (27-CO-59(0,0),,LDP) -SAMPLE Hollow Cylinder Of Chemically Pure Cobalt -STATUS Data Are Taken From The Table of 3rd Reference -HISTORY (19981111U) .REFERENCE MOVED TO SAN 001 -ENDBIB 4 +SAMPLE Hollow cylinder of chemically pure cobalt +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to SAN 001 +ENDBIB 5 NOCOMMON 0 0 DATA 1 1 DATA 1/MEV 6.9 ENDDATA 3 -ENDSUBENT 12 -SUBENT 41102035 20061113 20070521 20060816 4139 -BIB 4 4 +ENDSUBENT 13 +SUBENT 41102035 20240916 20250110 20250110 4220 +BIB 4 5 REACTION (41-NB-93(0,0),,LDP) -SAMPLE Hollow Cylinder Of Chemically Pure Niobium -STATUS Data Are Taken From The Table of 3rd Reference -HISTORY (19981111U) .Reference Moved To SAN 001 -ENDBIB 4 +SAMPLE Hollow cylinder of chemically pure niobium +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to SAN 001 +ENDBIB 5 NOCOMMON 0 0 DATA 1 1 DATA 1/MEV 12.9 ENDDATA 3 -ENDSUBENT 12 -SUBENT 41102036 20061113 20070521 20060816 4139 -BIB 4 4 +ENDSUBENT 13 +SUBENT 41102036 20240916 20250110 20250110 4220 +BIB 4 5 REACTION (49-IN-115(0,0),,LDP) -SAMPLE Hollow Cylinder Of Chemically Pure Indium -STATUS Data Are Taken From The Table of 3rd Reference -HISTORY (19981111U) .Reference Moved To SAN 001 -ENDBIB 4 +SAMPLE Hollow cylinder of chemically pure indium +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to SAN 001 +ENDBIB 5 NOCOMMON 0 0 DATA 1 1 DATA 1/MEV 11.9 ENDDATA 3 -ENDSUBENT 12 -SUBENT 41102037 20061113 20070521 20060816 4139 -BIB 4 4 +ENDSUBENT 13 +SUBENT 41102037 20240916 20250110 20250110 4220 +BIB 4 5 REACTION (79-AU-197(0,0),,LDP) -SAMPLE Hollow Cylinder Of Chemically Pure Gold -STATUS Data Are Taken From The Table Of 3rd Reference -HISTORY (19981111U) .Reference Moved To SAN 001 -ENDBIB 4 +SAMPLE Hollow cylinder of chemically pure gold +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to SAN 001 +ENDBIB 5 NOCOMMON 0 0 DATA 1 1 DATA 1/MEV 16.1 ENDDATA 3 -ENDSUBENT 12 -SUBENT 41102038 20061113 20070521 20060816 4139 -BIB 4 4 +ENDSUBENT 13 +SUBENT 41102038 20240916 20250110 20250110 4220 +BIB 4 5 REACTION (83-BI-209(0,0),,LDP) -SAMPLE Hollow Cylinder Of Chemically Pure Bismuth -STATUS Data Are Taken From The Table Of 3rd Reference -HISTORY (19981111U) .Reference Moved To SAN 001 -ENDBIB 4 +SAMPLE Hollow cylinder of chemically pure bismuth +STATUS (TABLE,,G.A.Prokopets,R,INDC(CCP)-169,(2),54,1980) + Table on page 57. +HISTORY (19981111U) .Reference moved to SAN 001 +ENDBIB 5 NOCOMMON 0 0 DATA 1 1 DATA 1/MEV 14.0 ENDDATA 3 -ENDSUBENT 12 +ENDSUBENT 13 ENDENTRY 38 diff --git a/exforall/411/41106.x4 b/exforall/411/41106.x4 index f63549d48..356d9f65a 100644 --- a/exforall/411/41106.x4 +++ b/exforall/411/41106.x4 @@ -1,107 +1,114 @@ -ENTRY 41106 19931024 20050926 0000 -SUBENT 41106001 19931024 20050926 0000 -BIB 12 16 -TITLE NEW DATA ABOUT EXCITATION LEVELS SCHEME - OF THE NUCLUS GE-73 -AUTHOR (YU.G.KOSYAK,D.K.KAIPOV.L.V.CHEKUSHINA) +ENTRY 41106 20240916 20250110 20250110 4220 +SUBENT 41106001 20240916 20250110 20250110 4220 +BIB 10 17 +TITLE New data on excited states of 73Ge +AUTHOR (Yu.G.Kosyak,D.K.Kaipov.L.V.Chekushina) +REFERENCE (J,BAS,54,(11),80,1990) English of IZV,54,2166 + (J,IZV,54,2166,1990) Issue 11. INSTITUTE (4KASKAZ) -REFERENCE (J,IZV,54,(11),2166,9011) - (J,BAS,54,(11),80,9011) ENGLISH OF IZV,54,2166 FACILITY (REAC) -INC-SPECT .FAST NEUTRON SPECTRUM OF THE THERMAL REACTOR -DETECTOR (GELI,NAICR) -MONITOR CO-56 CALIBRATION GAMMA-SOURCE -SAMPLE .METALLIC GERMANIUM, WEIGHT 30 GRAM, - GE-73 CONTENT 74.3 PERCENT -STATUS .DATA ARE TAKEN FROM THE REFERENCE -ERR-ANALYS (DATA-ERR) ERRORS ARE NOT SPECIFIED -HISTORY (921103C) + + COMPILED AT THE CENTRE - CJD + + - (931024U) MODIFIER 'SPA' ADDED TO SF8 OF SAN 002 -ENDBIB 16 +INC-SPECT .Fast neutron spectrum of the thermal reactor +DETECTOR (GELI,NAICR) .At 90 and 124 deg relative to the + incident neutron beam. Resolution ~4 keV at 1.5 MeV. +MONITOR Co-56 calibration gamma-source +SAMPLE .Metallic germanium, weight 30 gram, + Ge-73 content 74.3 %. +HISTORY (19921103C) + + Compiled at the centre - CJD + + + (19931024U) Modifier 'SPA' added to SF8 of SAN 002 + (20240916U) Upper -> lower case correction. + Dates were corrected for 4-digits year. + STATUS information was updated. +ENDBIB 17 COMMON 1 3 EN-DUMMY EV 1.0E+06 ENDCOMMON 3 -ENDSUBENT 23 -SUBENT 41106002 19931024 20050926 0000 -BIB 2 3 -REACTION (32-GE-73(N,INL)32-GE-73,,SPC,,REL/SPA) RELATION - QUANTITY IS NOT GIVEN -FLAG (1.) NEW GAMMA-TRANSITION -ENDBIB 3 -NOCOMMON -DATA 4 68 -E DATA DATA-ERR FLAG -KEV ARB-UNITS ARB-UNITS NO-DIM - 233.6 8.33 0.02 - 286.8 63. 3. - 297.2 18.1 0.4 - 325.8 15.8 0.3 - 335.3 1.6 0.2 1. - 340.5 19.1 0.2 1. - 350.7 0.4 0.2 - 377.8 4.5 0.3 1. - 388.1 17.5 0.5 - 412.4 4.0 0.2 1. - 430.3 18.5 0.4 - 431. 1. - 485.5 0.8 0.1 - 488.2 0.3 0.1 - 499.0 0.1 - 501. 1.1 0.2 - 531.0 10.88 0.04 - 541.7 1.4 0.3 - 562.5 8.6 0.3 - 590.0 13. 3. 1. - 617.6 2.5 0.2 1. - 645.9 6.0 0.3 - 650.8 0.3 0.1 - 658.9 33.5 0.5 - 679.3 0.3 0.1 - 708.8 1.1 0.2 1. - 729.8 1.9 0.2 1. - 739.4 0.5 0.2 - 741.6 8.4 0.5 - 741.7 1.0 - 764.1 5.3 0.2 1. - 768. 1.1 0.3 - 776.6 21.0 0.4 1. - 783.8 3.5 0.5 - 784.5 0.2 0.1 - 799.1 13.5 0.5 - 825.6 50. 2. - 837.9 4.0 0.5 1. - 851.2 5.7 0.2 1. - 867.8 36. 2. - 873.6 0.5 0.1 - 906.7 10.4 0.2 1. - 915.8 0.7 0.1 - 920.2 2.2 0.5 1. - 925.3 1.4 0.1 - 934.1 0.6 0.2 1. - 951.7 1.2 0.1 - 975.4 0.5 0.2 - 993.9 23.1 0.6 - 996.1 1.8 0.3 - 1010.2 1.5 0.3 1. - 1030.0 2.0 0.3 1. - 1045.8 6. 1. - 1062.8 14.9 0.3 1. - 1085.5 1.7 0.3 1. - 1172.3 0.4 0.1 1. - 1249.6 4.5 0.6 - 1324.5 1.5 0.3 1. - 1413.3 0.33 0.10 1. - 1445.6 0.20 0.05 1. - 1541.7 0.4 0.1 1. - 1591.0 0.2 0.1 1. - 1609.4 0.4 0.3 - 1610.9 0.7 0.2 1. - 1821.1 0.15 0.03 1. - 2004.1 1.0 0.2 1. - 2024.8 0.3 0.2 1. - 2072.7 0.8 0.3 1. +ENDSUBENT 24 +SUBENT 41106002 20240916 20250110 20250110 4220 +BIB 5 9 +REACTION (32-GE-73(N,INL)32-GE-73,,SPC,,SPA/REL) Relation + quantity is not given +FLAG (1.) New gamma-transition + (2.) New gamma-transition and improved level energies. + (3.) Approximated value of intensity +ERR-ANALYS (DATA-ERR) Errors are not specified +STATUS (TABLE,,Yu.G.Kosyak+,J,BAS,54,(11),80,1990) Table 1. +HISTORY (20240916A) LVL-INI values were added. + REL/SPA -> SPA/REL in REACTION. +ENDBIB 9 +NOCOMMON 0 0 +DATA 6 68 +E DATA DATA-ERR DATA-MIN LVL-INI FLAG +KEV ARB-UNITS ARB-UNITS ARB-UNITS KEV NO-DIM + 233.6 8.33 0.02 597.6 + 286.8 63. 3. 353.5 + 297.2 18.1 0.4 364.0 + 325.8 15.8 0.3 392.5 + 335.3 1.6 0.2 993.9 1. + 340.5 19.1 0.2 353.5 1. + 350.7 0.4 0.2 264.0 + 377.8 4.5 0.3 741.7 1. + 388.1 17.5 0.5 741.7 + 412.4 4.0 0.2 1010.2 2. + 430.3 18.5 0.4 499.0 + 431. 1. 930. 3. + 485.5 0.8 0.1 499.0 + 488.2 0.3 0.1 554.9 + 499.0 0.1 499.0 + 501. 1.1 0.2 894. + 531.0 10.88 0.04 597.6 + 541.7 1.4 0.3 554.9 + 562.5 8.6 0.3 915.8 + 590.0 13. 3. 658.8 1. + 617.6 2.5 0.2 1010.2 2. + 645.9 6.0 0.3 658.8 + 650.8 0.3 0.1 1043.3 + 658.9 33.5 0.5 658.8 + 679.3 0.3 0.1 1043.3 + 708.8 1.1 0.2 777.4 2. + 729.8 1.9 0.2 1992.7 2. + 739.4 0.5 0.2 1131.9 + 741.6 8.4 0.5 1609.4 + 741.7 1.0 741.7 + 764.1 5.3 0.2 777.4 2. + 768. 1.1 0.3 1131.9 + 776.6 21.0 0.4 1130.1 1. + 783.8 3.5 0.5 1525.5 + 784.5 0.2 0.1 1339.4 + 799.1 13.5 0.5 867.8 + 825.6 50. 2. 825.6 + 837.9 4.0 0.5 906.7 2. + 851.2 5.7 0.2 1757.9 2. + 867.8 36. 2. 867.8 + 873.6 0.5 0.1 2004.1 + 906.7 10.4 0.2 906.7 2. + 915.8 0.7 0.1 915.8 + 920.2 2.2 0.5 1312.7 2. + 925.3 1.4 0.1 993.9 + 934.1 0.6 0.2 2066.0 2. + 951.7 1.2 0.1 1609.4 + 975.4 0.5 0.2 1339.4 + 993.9 23.1 0.6 993.9 + 996.1 1.8 0.3 1388.6 + 1010.2 1.5 0.3 1010.2 2. + 1030.0 2.0 0.3 1043.3 1. + 1045.8 6. 1. 1871.6 + 1062.8 14.9 0.3 1131.6 2. + 1085.5 1.7 0.3 2217.1 2. + 1172.3 0.4 0.1 1525.5 1. + 1249.6 4.5 0.6 1262.9 + 1324.5 1.5 0.3 2101.9 2. + 1413.3 0.33 0.10 1912.7 1. + 1445.6 0.20 0.05 2361.4 2. + 1541.7 0.4 0.1 2319.1 2. + 1591.0 0.2 0.1 2188.6 2. + 1609.4 0.4 0.3 1609.4 + 1610.9 0.7 0.2 2004.1 1. + 1821.1 0.15 0.03 2319.1 2. + 2004.1 1.0 0.2 2004.1 1. + 2024.8 0.3 0.2 2038.1 2. + 2072.7 0.8 0.3 2141.5 2. ENDDATA 70 -ENDSUBENT 78 +ENDSUBENT 84 ENDENTRY 2 diff --git a/exforall/411/41125.x4 b/exforall/411/41125.x4 index 4e7557075..76def0be5 100644 --- a/exforall/411/41125.x4 +++ b/exforall/411/41125.x4 @@ -1,24 +1,22 @@ -ENTRY 41125 19950321 20050926 0000 -SUBENT 41125001 19950321 20050926 0000 -BIB 5 9 -TITLE PRECISION DETERMINATION OF THE HALF-LIFE OF CF-252 - AND TIME-DEPENDENCE OF NEUTRON FLUX FROM RA-BE - (ALPHA,N) NEUTRON SOURCE -AUTHOR (V.T.SHCHEBOLEV,N.N.MOISEEV,Z.A.RAMENDIK) +ENTRY 41125 20240916 20250110 20250110 4220 +SUBENT 41125001 20240916 20250110 20250110 4220 +BIB 5 14 +TITLE Precision determination of 252Cf half-life and the + time dependence of the neutron flux of Ra-Be(alpha,n) + neutron source +AUTHOR (V.T.Shchebolev,N.N.Moiseev,Z.A.Ramendik) +REFERENCE (J,AE/T,73,1015,1992) + (J,AE,73,502,1992) Issue 6. INSTITUTE (4RUSFRT) -REFERENCE (J,AE,73,(6),502,9212) -HISTORY (930716C) + + COMPILED AT THE CENTRE - CJD + + - (950321D) - - DELETED BECAUSE OF THE IRRELEVANCY - OF DATA TO THE CENTRE'S TASK - - -ENDBIB 9 -NOCOMMON -ENDSUBENT 12 -SUBENT 41125002 19950321 20050926 0000 -BIB 2 2 -REACTION (98-CF-252(0,F)2-HE-4,PRE,FY) -DETECTOR (SOLST) -ENDBIB 2 -NOCOMMON -NODATA -ENDSUBENT 6 +HISTORY (19930716C) + + Compiled at the centre - CJD + + + (19950321D) - - Deleted because of the irrelevancy + of data to the centre's task - - + (20240916U) Upper -> lower case correction. + Dates were corrected for 4-digits year. + Ref. J,AE/T,73,1015,1992 was added. + Subent 002 was deleted - see comment in HISTORY . +ENDBIB 14 +NOCOMMON 0 0 +ENDSUBENT 17 +SUBENT 41125002 20240916 20250110 20250110 4220 ENDENTRY 2 diff --git a/exforall/411/41137.x4 b/exforall/411/41137.x4 index 5cbfbf5ae..9548a9fe6 100644 --- a/exforall/411/41137.x4 +++ b/exforall/411/41137.x4 @@ -1,36 +1,40 @@ -ENTRY 41137 19990817 19991117 20050926 0000 -SUBENT 41137001 19990817 19991117 20050926 0000 -BIB 12 18 -TITLE NEUTRONS' RESONANCES SPIN DETERMINATION ON THE FORM - OF MULTIPLICITY SPECTRUM OF THE CAPTURE GAMMA-QUANTA -AUTHOR (YU.V.GRIGOR'EV,G.P.GEORGIEV,N.B.YANEVA) -INSTITUTE (4RUSFEI) GRIGOR'EV - (4ZZZDUB) GEORGIEV - (3BULBLA) YANEVA -REFERENCE (R,FEI-2277,19921026) DATA TABLE IS GIVEN -FACILITY (REAC,4ZZZDUB) IBR-30 REACTOR -METHOD (TOF) FLIGHT BASE IS 502 M +ENTRY 41137 20240916 20250110 20250110 4220 +SUBENT 41137001 20240916 20250110 20250110 4220 +BIB 11 20 +TITLE Neutrons' resonances spin determination on the form + of multiplicity spectrum of the capture gamma-quanta +AUTHOR (Yu.V.Grigor'ev,G.P.Georgiev,N.B.Yaneva) +INSTITUTE (4RUSFEI) Grigor'ev + (4ZZZDUB) Georgiev + (3BULBLA) Yaneva +REFERENCE (R,FEI-2277,1992) Data table is given +FACILITY (REAC,4ZZZDUB) IBR-30 reactor +METHOD (TOF) Flight base is 502 m DETECTOR (NAICR) -SAMPLE ALUMINIUM CONTAINERS FILLED WITH SAMARIUM OXIDE - SM-147 CONTENT IS 96.4 PC, SM-147 THICKNESSES ARE - 3.58E-4 AND 8.94E-5 ATOMS/BARN -MONITOR ABSOLUTE MEASUREMENTS -STATUS DATA TAKEN FROM THE REFERENCE -HISTORY (19931230C) + + COMPILED AT THE CENTRE - CJD + + - (19990817U) . . DATES CORRECTED -ERR-ANALYS ERRORS ARE NOT GIVEN -ENDBIB 18 +SAMPLE Aluminium containers filled with samarium oxide, + Sm-147 content is 96.4 %, Sm-147 thicknesses are + 3.58E-4 and 8.94E-5 atoms/barn +MONITOR Absolute measurements +ERR-ANALYS Errors are not given +HISTORY (19931230C) + + Compiled at the centre - CJD + + + (19990817U) . . Dates corrected + (20240916U) Upper -> lower case correction. + Dates were corrected for 4-digits year. + STATUS information was updated. +ENDBIB 20 COMMON 1 3 EN-RSL NSEC/M 8. ENDCOMMON 3 -ENDSUBENT 25 -SUBENT 41137002 19990817 19991117 20050926 0000 -BIB 1 2 -REACTION 1(62-SM-147(N,0),,J) SPIN OF THE RESONANCE LEVEL - 2(62-SM-147(N,0),,PTY) PARITY OF THE RESONANCE LEVEL -ENDBIB 2 +ENDSUBENT 27 +SUBENT 41137002 20240916 20250110 20250110 4220 +BIB 2 4 +REACTION 1(62-SM-147(N,0),,J) + 2(62-SM-147(N,0),,PTY) +STATUS (TABLE,,Yu.V.Grigor'ev+,R,FEI-2277,1992) + Table on pages 5-7. +ENDBIB 4 NOCOMMON 0 0 DATA 3 37 EN-RES DATA 1DATA 2 @@ -73,5 +77,5 @@ EV NO-DIM NO-DIM 274.4 3. -1. 283.3 4. -1. ENDDATA 39 -ENDSUBENT 46 +ENDSUBENT 48 ENDENTRY 2 diff --git a/exforall/411/41145.x4 b/exforall/411/41145.x4 index 0d71f30a9..b0e8e6f62 100644 --- a/exforall/411/41145.x4 +++ b/exforall/411/41145.x4 @@ -1,52 +1,58 @@ -ENTRY 41145 20020321 20050616 20050926 0000 -SUBENT 41145001 20020321 20050616 20050926 0000 -BIB 12 19 -INSTITUTE (4RUSMOS) BASKOVA, VOVK, GERUS - (4RUSKUR) GOVOR, DEMIDOV, KURKIN -REFERENCE (R,IAE-4544/2,198711) DATA TABLES ARE GIVEN -AUTHOR (K.A.BASKOVA,A.B.VOVK,G.M.GERUS,L.I.GOVOR,A.M.DEMIDOV, - V.A.KURKIN) -TITLE GAMMA-RADIATION INVESTIGATION ON CD-111 AND CD-113 - NUCLEI FROM THE REACTION (N,N'GAMMA) AND (N,G) -FACILITY (REAC,4RUSKUR) REACTOR IR-8 +ENTRY 41145 20240916 20250110 20250110 4220 +SUBENT 41145001 20240916 20250110 20250110 4220 +BIB 11 24 +TITLE Gamma-radiation investigation on Cd-111 and Cd-113 + nuclei from the reaction (n,n'gamma) and (n,gamma) +AUTHOR (K.A.Baskova,A.B.Vovk,G.M.Gerus,L.I.Govor,A.M.Demidov, + V.A.Kurkin) +REFERENCE (R,IAE-4544/2,1987) Data tables are given +INSTITUTE (4RUSMOS) Baskova, Vovk, Gerus + (4RUSKUR) Govor, Demidov, Kurkin +FACILITY (REAC,4RUSKUR) Reactor IR-8 INC-SOURCE (REAC) -INC-SPECT FILTERED FAST AND RESONANCE NEUTRON BEAMS OF THE - THERMAL REACTOR +INC-SPECT Filtered fast and resonance neutron beams of the + thermal reactor. DETECTOR (HPGE) -MONITOR GIVEN IN PROPER SUBENT -ERR-ANALYS ERRORS ARE NOT SPECIFIED, PROPOSED STATISTICAL -STATUS DATA ARE TAKEN FROM THE REFERENCE IAE-4544/2 -HISTORY (19940615C) + + COMPILED AT THE CENTRE - CJD + + - (19950422U) - - REACTION CODE IN SAN 002-009 CORRECTED - (20010311A) DATE is corrected +ADD-RES (DECAY) Levels scheme for 111Cd - table 9, + for 113Cd - table 10. + Spin and parity for 111Cd - table 11, + for 113Cd -table 12 +ERR-ANALYS (DATA-ERR) Errors are not specified +HISTORY (19940615C) + + Compiled at the centre - CJD + + + (19950422U) - - REACTION code in SAN 002-009 corrected + (20010311A) Date is corrected (20020321U) . . Reference code corrected -ENDBIB 19 + (20240916U) Upper -> lower case correction. + Dates were corrected for 4-digits year. + STATUS information was updated. +ENDBIB 24 NOCOMMON 0 0 -ENDSUBENT 22 -SUBENT 41145002 20010311 20050616 20050926 0000 -BIB 7 14 +ENDSUBENT 27 +SUBENT 41145002 20240916 20250110 20250110 4220 +BIB 5 15 REACTION 1((48-CD-110(N,G)48-CD-111,,SPC,,SPA)// (48-CD-110(N,G)48-CD-111,,SPC,,SPA)) 2((48-CD-110(N,G)48-CD-111-M,,SPC,,SPA)// (48-CD-110(N,G)48-CD-111-M,,SPC,,SPA)) -INC-SPECT SHEER NEUTRON BEAM AT THE REACTOR PERIPHERY FILTERED - BY THE 50 MM LEAD PLATE, 1 GRAM/CM2 OF B4-C AND - BERILLIUM CONVERTER -SAMPLE METALLIC SAMPLE 30 GRAM WEIGHT, CD-110 CONTENT 96 PC -MONITOR (48-CD-110(N,G)48-CD-111,,SPC) -ERR-ANALYS (E-ERR) ERROR OF THE NOMINATOR GAMMA ENERGY -STATUS TABLE 1, COL. 3, 4 OF REFERENCE -HISTORY (19940615U) 'SPA' ADDED TO REACTION SF8 - (20010311A) EXPLICIT RATIO INTRODUCED. DATA VALUES - DIMINISHED IN 100 TIMES -ENDBIB 14 +INC-SPECT Sheer neutron beam at the reactor periphery filtered + by the 50 mm lead plate, 1 gram/cm2 of B(4)C and + berillium converter +SAMPLE Metallic sample 30 gram weight, Cd-110 content 96 %. +STATUS (TABLE,,K.A.Baskova+,R,IAE-4544/2,1987) + Table 1, col. 3, 4 +HISTORY (19940615U) 'SPA' added to REACTION SF8 + (20010311A) Explicit ratio introduced. Data values + diminished in 100 times + (20240916A) E-ERR -> E-NM-ERR. + MONITOR line was deleted ( ratio is given) +ENDBIB 15 COMMON 2 3 EN-DUMMY E-DN EV KEV 100. 342.2 ENDCOMMON 3 DATA 6 360 -E-NM E-ERR DATA 1DATA-ERR 1DATA 2DATA-ERR 2 +E-NM E-NM-ERR DATA 1DATA-ERR 1DATA 2DATA-ERR 2 KEV KEV NO-DIM NO-DIM NO-DIM NO-DIM 171.3 0.3 57. E-2 6. E-2 203.8 0.6 0.30 E-2 0.06 E-2 @@ -409,31 +415,35 @@ KEV KEV NO-DIM NO-DIM NO-DIM NO-DIM 4406.1 0.5 1.37 E-2 0.16 E-2 4417.4 0.4 2.2 E-2 0.2 E-2 ENDDATA 362 -ENDSUBENT 385 -SUBENT 41145003 20010311 20050616 20050926 0000 -BIB 7 14 +ENDSUBENT 386 +SUBENT 41145003 20240916 20250110 20250110 4220 +BIB 6 18 REACTION ((48-CD-111(N,INL)48-CD-111-M,,SPC,,FIS)// - (48-CD-111(N,INL)48-CD-111-M,,SPC,,FIS)) RELATIVE TO - THE LINE 342.29 KEV TAKEN FOR 100 -INC-SPECT RADIAL NEUTRON BEAM FROM THERMAL REACTOR FILTERED WIT - 1 MM CADMIUM PLATE, 1 GRAM/CM2 B4-C, 50 MM U-238, - 1 GRAM/CM2 B-10 -SAMPLE METALLIC CADMIUM, WEIGHT 15 GRAM, CD-111 CONTENT 96 P -ERR-ANALYS (E-ERR) ERROR OF THE NOMINATOR GAMMA ENERGY -FLAG (1.) METASTABLE INITIAL LEVEL -STATUS TABLE 1, COL. 1, 2 OF REFERENCE -HISTORY (19940615U) 'SPA' ADDED TO REACTION SF8 - (20010311A) 'SPA' CHANGED TO 'FIS' IN REACTION SF8 - EXPLICIT RATIO INTRODUCED. DATA VALUES DIMINISHED - IN 100 TIMES -ENDBIB 14 + (48-CD-111(N,INL)48-CD-111-M,,SPC,,FIS)) +INC-SPECT Radial neutron beam from thermal reactor filtered with + 1 mm cadmium plate, 1 gram/cm2 B(4)C, 50 mm U-238, + 1 gram/cm2 B-10 +SAMPLE Metallic cadmium, weight 15 gram, Cd-111 content 96 % +FLAG (1.) Metastable initial level + (2.) In Table 6 this gamma energy is printed with a + blank instead of one digit "67 .8", supposed by + compilers as "679.8" taken into account information + from NuDat-3. +STATUS (TABLE,,K.A.Baskova+,R,IAE-4544/2,1987) + Table 1, Col. 1, 2 +HISTORY (19940615U) 'SPA' added to REACTION SF8 + (20010311A) 'SPA' changed to 'FIS' in REACTION SF8. + Explicit ratio introduced. DATA values diminished + in 100 times + (20240916A) E-ERR -> E-NM-ERR. Flag 2. was introduced. +ENDBIB 18 COMMON 2 3 EN-DUMMY E-DN EV KEV 1.0E+06 342.29 ENDCOMMON 3 DATA 5 320 -E-NM E-ERR DATA DATA-ERR FLAG +E-NM E-NM-ERR DATA DATA-ERR FLAG KEV KEV NO-DIM NO-DIM NO-DIM 96.7 0.2 3.1 E-2 0.6 E-2 150.77 0.20 22. E-2 2. E-2 @@ -495,7 +505,7 @@ KEV KEV NO-DIM NO-DIM NO-DIM 638.91 0.15 0.26 E-2 0.07 E-2 646.13 0.10 4.2 E-2 0.4 E-2 666.19 0.20 0.70 E-2 0.21 E-2 - 679.65 0.20 0.84 E-2 0.03 E-2 + 679.65 0.20 0.84 E-2 0.03 E-2 2. 701.6 0.5 1.6 E-2 0.6 E-2 704.66 0.15 4.2 E-2 0.9 E-2 715.65 0.15 3.7 E-2 0.7 E-2 @@ -756,19 +766,20 @@ KEV KEV NO-DIM NO-DIM NO-DIM 3135.4 0.7 0.23 E-2 0.05 E-2 3148.6 1.0 0.10 E-2 0.03 E-2 ENDDATA 322 -ENDSUBENT 345 -SUBENT 41145004 20010311 20050616 20050926 0000 -BIB 6 9 -REACTION (48-CD-110(N,G)48-CD-111,,SPC,,REL/SPA) RFERENCE - QUANTITY NOT GIVEN -INC-SPECT SHEER NEUTRON BEAM AT THE REACTOR PERIPHERY FILTERED - BY THE 50 MM LEAD PLATE, 1 GRAM/CM2 OF B4-C AND - BERILLIUM CONVERTER -SAMPLE METALLIC SAMPLE 30 GRAM WEIGHT, CD-110 CONTENT 96 PC -MONITOR NO INFORMATION -STATUS TABLE 3 OF REFERENCE -HISTORY (19940615U) 'SPA' ADDED TO REACTION SF8 -ENDBIB 9 +ENDSUBENT 349 +SUBENT 41145004 20240916 20250110 20250110 4220 +BIB 6 10 +REACTION (48-CD-110(N,G)48-CD-111,,SPC,,SPA/REL) Reference + quantity is not given in the article +INC-SPECT Sheer neutron beam at the reactor periphery filtered + by the 50 mm lead plate, 1 gram/cm2 of B(4)C and + berillium converter +SAMPLE Metallic sample 30 gram weight, Cd-110 content 96 % +MONITOR No information +STATUS (TABLE,,K.A.Baskova+,R,IAE-4544/2,1987) Table 3 +HISTORY (19940615U) 'SPA' added to REACTION SF8 + (20240916A) REL/SPA -> SPA/REL in REACTION. +ENDBIB 10 COMMON 1 3 EN-DUMMY EV @@ -849,100 +860,109 @@ KEV KEV ARB-UNITS ARB-UNITS 4406.1 0.5 1.37 0.16 4417.4 0.4 2.2 0.2 ENDDATA 73 -ENDSUBENT 91 -SUBENT 41145005 20010311 20050616 20050926 0000 -BIB 7 12 +ENDSUBENT 92 +SUBENT 41145005 20240916 20250110 20250110 4220 +BIB 7 17 REACTION ((48-CD-110(N,G)48-CD-111,,SPC,,SPA)// (48-CD-110(N,G)48-CD-111,,SPC,,SPA)) -INC-SPECT SHEER NEUTRON BEAM AT THE REACTOR PERIPHERY FILTERED - BY THE 50 MM LEAD PLATE, 1 GRAM/CM2 OF B4-C AND - BERILLIUM CONVERTER -SAMPLE METALLIC SAMPLE 30 GRAM WEIGHT, CD-110 CONTENT 96 PC -ERR-ANALYS (E-ERR) ERROR IN THE NOMONATOR GAMMA ENERGY -FLAG (1.) THIS LEVEL WAS NOT KNOWN BEFORE -STATUS TABLE 4 OF REFERENCE -HISTORY (19940615U) 'SPA' ADDED TO REACTION SF8 - (20010311A) EXPLICIT RATION INTRODUCED. DATA VALUES - DIMINISHED IN 100 TIMES -ENDBIB 12 +INC-SPECT Sheer neutron beam at the reactor periphery filtered + by the 50 mm lead plate, 1 gram/cm2 of B(4)C and + berillium converter +SAMPLE Metallic sample 30 gram weight, Cd-110 Content 96 % +COMMENT Of authors. These levels were not known before: + 1078.4, 1340.0, 1391.3, 1546.5, 1739.8, 1789.5, 1828.7, + 1843.2, 2045.3, 2326.6 keV. +ADD-RES Spin and parity of levels are given in table 4. +STATUS (TABLE,,K.A.Baskova+,R,IAE-4544/2,1987) Table 4 +HISTORY (19940615U) 'SPA' added to REACTION SF8 + (20010311A) Explicit ratio introduced. Data values + diminished in 100 times + (20240916A) E-ERR -> E-NM-ERR. + LVL-FIN, LVL-FIN-ER were added. + FLAG infromation was moved in COMMENT. +ENDBIB 17 COMMON 2 3 EN-DUMMY E-DN EV KEV 100. 6975.5 ENDCOMMON 3 -DATA 5 20 -E-NM E-ERR DATA DATA-ERR FLAG -KEV KEV NO-DIM NO-DIM NO-DIM - 6732.0 0.15 23. E-2 6. E-2 - 6634.6 0.8 97. E-2 18. E-2 - 6109.7 0.5 206. E-2 36. E-2 - 5959.1 0.7 111. E-2 39. E-2 - 5897.1 0.5 191. E-2 28. E-2 1. - 5859.1 1.5 74. E-2 18. E-2 - 5785.9 0.8 30. E-2 9. E-2 - 5649.1 0.5 260. E-2 52. E-2 - 5635.5 0.5 159. E-2 38. E-2 1. - 5584.2 0.5 91. E-2 17. E-2 1. - 5502.6 0.7 145. E-2 29. E-2 - 5429.0 1.5 72. E-2 13. E-2 1. - 5424.0 2.0 24. E-2 7. E-2 - 5235.7 0.5 98. E-2 25. E-2 1. - 5186.0 0.5 56. E-2 14. E-2 1. - 5146.8 1.5 199. E-2 40. E-2 1. - 5132.3 0.8 248. E-2 60. E-2 1. - 4930.2 1.0 168. E-2 42. E-2 1. - 4694.2 0.8 111. E-2 28. E-2 - 4648.9 0.8 135. E-2 34. E-2 1. -ENDDATA 22 -ENDSUBENT 43 -SUBENT 41145006 20010311 20050616 20050926 0000 -BIB 6 11 +DATA 6 21 +E-NM E-NM-ERR DATA DATA-ERR LVL-FIN LVL-FIN-ER +KEV KEV NO-DIM NO-DIM KEV KEV + 6975.5 0.5 1. 0. + 6732.0 0.15 23. E-2 6. E-2 243.5 1.6 + 6634.6 0.8 97. E-2 18. E-2 340.9 1.0 + 6109.7 0.5 206. E-2 36. E-2 865.8 0.7 + 5959.1 0.7 111. E-2 39. E-2 1016.4 0.9 + 5897.1 0.5 191. E-2 28. E-2 1078.4 0.7 + 5859.1 1.5 74. E-2 18. E-2 1116.4 1.6 + 5785.9 0.8 30. E-2 9. E-2 1189.6 1.0 + 5649.1 0.5 260. E-2 52. E-2 1326.4 0.7 + 5635.5 0.5 159. E-2 38. E-2 1340.0 0.7 + 5584.2 0.5 91. E-2 17. E-2 1391.3 0.7 + 5502.6 0.7 145. E-2 29. E-2 1472.9 0.8 + 5429.0 1.5 72. E-2 13. E-2 1546.5 1.6 + 5424.0 2.0 24. E-2 7. E-2 1551.5 2.1 + 5235.7 0.5 98. E-2 25. E-2 1739.8 0.7 + 5186.0 0.5 56. E-2 14. E-2 1789.5 0.7 + 5146.8 1.5 199. E-2 40. E-2 1828.7 1.6 + 5132.3 0.8 248. E-2 60. E-2 1843.2 1.0 + 4930.2 1.0 168. E-2 42. E-2 2045.3 1.1 + 4694.2 0.8 111. E-2 28. E-2 2281.3 1.0 + 4648.9 0.8 135. E-2 34. E-2 2326.6 1.0 +ENDDATA 23 +ENDSUBENT 49 +SUBENT 41145006 20240916 20250110 20250110 4220 +BIB 6 13 REACTION ((48-CD-112(N,G)48-CD-113,,SPC,,SPA)// (48-CD-112(N,G)48-CD-113,,SPC,,SPA)) -INC-SPECT SHEER NEUTRON BEAM AT THE REACTOR PERIPHERY FILTERED - BY THE 50 MM LEAD PLATE, 1 GRAM/CM2 OF B4-C AND - BERILLIUM CONVERTER -SAMPLE METALLIC SAMPLE 30 GRAM WEIGHT, CD-110 CONTENT 96 PC -ERR-ANALYS (E-ERR) ERROR IN THE NOMINATOR GAMMA ENERGY -STATUS DATA FROM TABLE 5 OF REFERENCE -HISTORY (19940615U) 'SPA' ADDED TO REACTION SF8 - (20010311A) EXPLICIT RATIO INTRODUCED - DATA VALUES DIMINISHED IN 100 TIMES -ENDBIB 11 +INC-SPECT Sheer neutron beam at the reactor periphery filtered + by the 50 mm lead plate, 1 gram/cm2 of B(4)C and + berillium converter +SAMPLE Metallic sample 30 gram weight, Cd-110 content 96 % +ADD-RES Spin and parity of levels are given in table 5. +STATUS (TABLE,,K.A.Baskova+,R,IAE-4544/2,1987) Table 5 +HISTORY (19940615U) 'SPA' added to REACTION SF8 + (20010311A) Explicit ratio introduced + DATA values diminished in 100 times + (20240916A) E-ERR -> E-NM-ERR. + LVL-FIN, LVL-FIN-ER were added. +ENDBIB 13 COMMON 2 3 EN-DUMMY E-DN EV KEV 100. 6541.8 ENDCOMMON 3 -DATA 4 10 -E-NM E-ERR DATA DATA-ERR -KEV KEV NO-DIM NO-DIM - 6243.4 0.5 87. E-2 16. E-2 - 6225.4 0.5 44. E-2 8. E-2 - 5958.0 0.5 64. E-2 11. E-2 - 5861.5 0.6 71. E-2 16. E-2 - 5658.2 0.5 144. E-2 21. E-2 - 5554.5 0.9 57. E-2 7. E-2 - 5491.7 0.6 65. E-2 15. E-2 - 5415.1 0.6 62. E-2 11. E-2 - 5347.3 0.5 101. E-2 23. E-2 - 5062.1 0.5 72. E-2 7. E-2 -ENDDATA 12 -ENDSUBENT 32 -SUBENT 41145007 20010311 20050616 20050926 0000 -BIB 7 12 +DATA 6 11 +E-NM E-NM-ERR DATA DATA-ERR LVL-FIN LVL-FIN-ER +KEV KEV NO-DIM NO-DIM KEV KEV + 6541.8 0.5 1. 0. + 6243.4 0.5 87. E-2 16. E-2 298.4 0.6 + 6225.4 0.5 44. E-2 8. E-2 316.4 0.6 + 5958.0 0.5 64. E-2 11. E-2 583.8 0.6 + 5861.5 0.6 71. E-2 16. E-2 680.3 0.7 + 5658.2 0.5 144. E-2 21. E-2 883.6 0.6 + 5554.5 0.9 57. E-2 7. E-2 987.8 0.8 + 5491.7 0.6 65. E-2 15. E-2 1050.1 0.7 + 5415.1 0.6 62. E-2 11. E-2 1126.7 0.7 + 5347.3 0.5 101. E-2 23. E-2 1194.5 0.6 + 5062.1 0.5 72. E-2 7. E-2 1479.7 0.6 +ENDDATA 13 +ENDSUBENT 35 +SUBENT 41145007 20240916 20250110 20250110 4220 +BIB 6 12 REACTION ((48-CD-113(N,INL)48-CD-113,,SPC,,FIS)// (48-CD-113(N,INL)48-CD-113,,SPC,,FIS)) -INC-SPECT RADIAL NEUTRON BEAM FROM THERMAL REACTOR FILTERED WIT - 1 MM CADMIUM PLATE, 1 GRAM/CM2 B4-C, 50 MM U-238, - 1 GRAM/CM2 B-10 -SAMPLE METALLIC CADMIUM, WEIGHT 15 GRAM, CD-111 CONTENT 96 P -ERR-ANALYS (E-ERR) ERROR IN THE NOMINATOR GAMMA ENERGY -FLAG (1.) METASTABLE INITIAL LEVEL -STATUS DATA FROM TABLE 2 OF REFERENCE -HISTORY (19940615U) 'SPA' ADDED TO REACTION SF8 - (20010311A) EXPLICIT RATIO GIVEN. DATA VALUES - DIMINISHED IN 100 TIMES. 'SPA' CHANGED TO 'FIS' IN SF8 +INC-SPECT Radial neutron beam from thermal reactor filtered wit + 1 mm cadmium plate, 1 gram/cm2 B(4)C, 50 mm U-238, + 1 gram/cm2 B-10 +SAMPLE Metallic cadmium, weight 15 gram, CD-111 content 96 % +FLAG (1.) Metastable initial level +STATUS (TABLE,,K.A.Baskova+,R,IAE-4544/2,1987) Table 2 +HISTORY (19940615U) 'SPA' added to REACTION SF8 + (20010311A) Explicit ratio given. DATA values + diminished in 100 times. 'SPA' changed to 'FIS' in SF8 + (20240916A) E-ERR -> E-NM-ERR. ENDBIB 12 COMMON 2 3 EN-DUMMY E-DN @@ -950,7 +970,7 @@ EV KEV 1.0E+06 298.58 ENDCOMMON 3 DATA 5 335 -E-NM E-ERR DATA DATA-ERR FLAG +E-NM E-NM-ERR DATA DATA-ERR FLAG KEV KEV NO-DIM NO-DIM NO-DIM 96.9 0.2 1.6 E-2 0.3 E-2 142.35 0.02 34. E-2 3. E-2 @@ -1289,214 +1309,216 @@ KEV KEV NO-DIM NO-DIM NO-DIM 3213.6 0.8 0.04 E-2 0.02 E-2 ENDDATA 337 ENDSUBENT 358 -SUBENT 41145008 20010311 20050616 20050926 0000 -BIB 3 8 +SUBENT 41145008 20240916 20250110 20250110 4220 +BIB 4 8 REACTION (48-CD-111(N,INL)48-CD-111,PAR,DA,G,LEG/RS/FIS) -STATUS (DEP,41145002) - (DEP,41145003) - (DEP,41145004) - (DEP,41145005) - DATA FROM TABLES 6, 8 OF REFERENCE -HISTORY (19940615U) 'SPA' ADDED TO REACTION SF8 - (20010311U) 'SPA' CHANGED TO 'FIS' IN REACTION SF8 +ADD-RES Initial level energy, spin and parity of initial and + final levels are given in table 6. +STATUS (TABLE,,K.A.Baskova+,R,IAE-4544/2,1987) Tables 6,8 + (DEP,41145003) Gamma intensities +HISTORY (19940615U) 'SPA' added to REACTION SF8 + (20010311U) 'SPA' changed to 'FIS' in REACTION SF8 + (20240916A) Subent was re-compiled. ENDBIB 8 -COMMON 2 3 -EN-DUMMY NUMBER -EV NO-DIM - 1.0E+06 2. +COMMON 1 3 +EN-DUMMY +EV + 1.0E+06 ENDCOMMON 3 -DATA 3 104 -E DATA DATA-ERR -KEV NO-DIM NO-DIM - 2. 67.8 0.156 - 2. 171.2 0.36 - 2. 245.4 0.13 - 2. 278.0 0.31 - 2. 284.3 0.055 - 2. 342.1 0.040 - 2. 374.8 0.078 - 2. 410.8 0.250 - 2. 446.1 0.168 - 2. 495.4 0.06 - 2. 507.6 0.018 - 2. 524.3 0.155 - 2. 620.1 0.17 - 2. 646.1 0.02 - 2. 715.6 0.043 - 2. 741.0 0.311 - 2. 752.8 0.282 - 2. 773.4 0.145 - 2. 793.4 0.17 - 2. 812.0 0.19 - 2. 825.6 0.129 - 2. 829.8 0.37 - 2. 832.9 0.084 - 2. 866.6 0.180 - 2. 873.1 0.08 - 2. 876.4 0.037 - 2. 881.4 0.55 - 2. 932.5 0.039 - 2. 943.4 0.789 - 2. 969.6 0.30 - 2. 999.2 0.213 - 2. 1016.8 0.041 - 2. 1029.4 0.21 - 2. 1036.2 0.054 - 2. 1049.7 0.160 - 2. 1078.4 0.01 - 2. 1115.6 0.215 - 2. 1130.6 0.015 - 2. 1146.5 0.031 - 2. 1150.7 0.238 - 2. 1190.1 0.046 - 2. 1325.9 0.16 - 2. 1340.3 0.001 - 2. 1424.0 0.04 - 2. 1494.6 0.01 - 2. 1552.2 0.37 - 2. 1575.5 0.18 - 2. 1632.7 0.05 - 2. 1641.0 0.005 - 2. 1683.1 0.23 - 2. 1692.2 0.063 - 2. 1842.5 0.03 - 4. 67.8 0.078 - 4. 171.2 0.13 - 4. 245.4 0.05 - 4. 278.0 0.02 - 4. 284.3 0.008 - 4. 342.1 0.008 - 4. 374.8 0.022 - 4. 410.8 0.018 - 4. 446.1 0.016 - 4. 495.4 0.01 - 4. 507.6 0.015 - 4. 524.3 0.02 - 4. 620.1 0.01 - 4. 646.1 0.02 - 4. 715.6 0.038 - 4. 741.0 0.04 - 4. 752.8 0.04 - 4. 773.4 0.02 - 4. 793.4 - 4. 812.0 - 4. 825.6 0.001 - 4. 829.8 0.07 - 4. 832.9 0.003 - 4. 866.6 0.02 - 4. 873.1 0.05 - 4. 876.4 0.04 - 4. 881.4 0.20 - 4. 932.5 0.012 - 4. 943.4 0.217 - 4. 969.6 0.071 - 4. 999.2 0.18 - 4. 1016.8 0.03 - 4. 1029.4 0.02 - 4. 1036.2 0.014 - 4. 1049.7 0.03 - 4. 1078.4 0.03 - 4. 1115.6 0.01 - 4. 1130.6 0.008 - 4. 1146.5 0.019 - 4. 1150.7 0.064 - 4. 1190.1 0.019 - 4. 1325.9 0.04 - 4. 1340.3 0.06 - 4. 1424.0 - 4. 1494.6 0.06 - 4. 1552.2 0.06 - 4. 1575.5 0.01 - 4. 1632.7 0.06 - 4. 1641.0 0.04 - 4. 1683.1 0.04 - 4. 1692.2 0.005 - 4. 1842.5 +DATA 4 104 +E NUMBER DATA DATA-ERR +KEV NO-DIM NO-DIM NO-DIM + 171.2 2. -0.36 0.03 + 171.2 4. 0.13 0.10 + 245.4 2. 0.13 0.04 + 245.4 4. -0.05 0.03 + 278.0 2. -0.31 0.05 + 278.0 4. 0.02 0.06 + 284.3 2. 0.055 0.009 + 284.3 4. -0.008 0.011 + 342.1 2. 0.040 0.005 + 342.1 4. -0.008 0.010 + 374.8 2. 0.078 0.021 + 374.8 4. -0.022 0.025 + 410.8 2. -0.250 0.012 + 410.8 4. 0.018 0.016 + 446.1 2. 0.168 0.012 + 446.1 4. -0.016 0.017 + 495.4 2. -0.06 0.05 + 495.4 4. 0.01 0.07 + 507.6 2. 0.018 0.003 + 507.6 4. -0.015 0.004 + 524.3 2. 0.155 0.023 + 524.3 4. 0.02 0.03 + 620.1 2. 0.17 0.03 + 620.1 4. -0.01 0.04 + 646.1 2. 0.02 0.03 + 646.1 4. -0.02 0.04 + 679.8 2. -0.156 0.014 + 679.8 4. -0.078 0.017 + 715.6 2. 0.043 0.019 + 715.6 4. -0.038 0.011 + 741.0 2. 0.311 0.024 + 741.0 4. -0.04 0.03 + 752.8 2. 0.282 0.024 + 752.8 4. -0.04 0.03 + 773.4 2. 0.145 0.024 + 773.4 4. 0.02 0.03 + 793.4 2. 0.17 0.04 + 793.4 4. 0.00 0.04 + 812.0 2. 0.19 0.06 + 812.0 4. 0. + 825.6 2. -0.129 0.007 + 825.6 4. 0.001 0.010 + 832.9 2. -0.084 0.015 + 832.9 4. 0.003 0.022 + 839.8 2. 0.37 0.04 + 839.8 4. 0.07 0.07 + 866.6 2. -0.180 0.022 + 866.6 4. 0.02 0.03 + 873.1 2. 0.08 0.10 + 873.1 4. -0.05 0.06 + 876.4 2. 0.037 0.016 + 876.4 4. -0.04 0.09 + 881.4 2. 0.55 0.04 + 881.4 4. 0.20 0.05 + 932.5 2. 0.039 0.06 + 932.5 4. 0.012 0.014 + 943.4 2. 0.789 0.018 + 943.4 4. 0.217 0.024 + 969.6 2. 0.300 0.021 + 969.6 4. -0.071 0.023 + 999.2 2. -0.213 0.022 + 999.2 4. 0.18 0.05 + 1016.8 2. -0.041 0.008 + 1016.8 4. -0.03 0.04 + 1029.4 2. 0.21 0.04 + 1029.4 4. -0.02 0.05 + 1036.2 2. -0.054 0.014 + 1036.2 4. -0.014 0.017 + 1049.7 2. 0.160 0.025 + 1049.7 4. -0.03 0.03 + 1078.4 2. 0.01 0.03 + 1078.4 4. -0.03 0.04 + 1115.6 2. -0.215 0.020 + 1115.6 4. -0.01 0.03 + 1130.6 2. 0.015 0.016 + 1130.6 4. -0.008 0.010 + 1146.5 2. 0.031 0.018 + 1146.5 4. -0.019 0.022 + 1150.7 2. 0.238 0.014 + 1150.7 4. 0.064 0.019 + 1190.1 2. -0.046 0.020 + 1190.1 4. -0.019 0.025 + 1325.9 2. -0.16 0.04 + 1325.9 4. -0.04 0.05 + 1340.3 2. -0.001 0.021 + 1340.3 4. 0.06 0.07 + 1424.0 2. 0.04 0.05 + 1424.0 4. 0. + 1494.6 2. 0.01 0.03 + 1494.6 4. 0.06 0.07 + 1552.2 2. 0.37 0.06 + 1552.2 4. -0.06 0.08 + 1575.5 2. -0.18 0.03 + 1575.5 4. 0.01 0.04 + 1632.7 2. 0.05 0.08 + 1632.7 4. -0.06 0.07 + 1641.0 2. 0.005 0.008 + 1641.0 4. 0.04 0.09 + 1683.1 2. -0.23 0.10 + 1683.1 4. 0.04 0.09 + 1692.2 2. 0.063 0.008 + 1692.2 4. -0.005 0.012 + 1842.5 2. 0.03 0.07 + 1842.5 4. 0. ENDDATA 106 ENDSUBENT 123 -SUBENT 41145009 20010311 20050616 20050926 0000 -BIB 3 6 +SUBENT 41145009 20240916 20250110 20250110 4220 +BIB 4 8 REACTION (48-CD-113(N,INL)48-CD-113,PAR,DA,G,LEG/RS/FIS) -STATUS (DEP,41145006) - (DEP,41145007) - DATA FROM TABLES 7, 8 OF REFERENCE -HISTORY (19940615U) 'SPA' ADDED TO REACTION SF8 - (20010311U) 'SPA' CHANGED TO 'FIS' IN REACTION SF8 -ENDBIB 6 -COMMON 2 3 -EN-DUMMY NUMBER -EV NO-DIM - 1.0E+06 2. +ADD-RES Initial level energy, spin and parity of initial and + final levels are given in table 7. +STATUS (TABLE,,K.A.Baskova+,R,IAE-4544/2,1987) Tables 7,8 + (DEP,41145007) Gamma intensities. +HISTORY (19940615U) 'SPA' added to REACTION SF8 + (20010311U) 'SPA' changed to 'FIS' in REACTION SF8 + (20240916A) Subent was re-compiled. +ENDBIB 8 +COMMON 1 3 +EN-DUMMY +EV + 1.0E+06 ENDCOMMON 3 -DATA 3 66 -E DATA DATA-ERR -KEV NO-DIM NO-DIM - 2. 142.4 0.27 - 2. 217.0 0.026 - 2. 249.9 0.28 - 2. 258.7 0.135 - 2. 298.6 0.018 - 2. 316.2 0.086 - 2. 322.3 0.15 - 2. 333.0 0.101 - 2. 339.3 0.037 - 2. 364.4 0.037 - 2. 374.6 0.127 - 2. 382.0 0.17 - 2. 392.4 0.065 - 2. 410.0 0.28 - 2. 412.8 0.16 - 2. 500.5 0.42 - 2. 528.8 0.28 - 2. 583.9 0.236 - 2. 588.9 0.30 - 2. 617.5 0.153 - 2. 680.6 0.111 - 2. 691.0 0.14 - 2. 717.1 0.044 - 2. 721.2 0.100 - 2. 878.6 0.111 - 2. 896.7 0.113 - 2. 952.0 0.141 - 2. 988.4 0.006 - 2. 1033.0 0.10 - 2. 1049.8 0.035 - 2. 1126.2 0.074 - 2. 1176.8 0.01 - 2. 1445.7 .132 - 4. 142.4 0.07 - 4. 217.0 0.05 - 4. 249.9 0.01 - 4. 258.7 0.003 - 4. 298.6 0.02 - 4. 316.2 0.10 - 4. 322.3 0.08 - 4. 333.0 0.016 - 4. 339.3 0.003 - 4. 364.4 0.044 - 4. 374.6 0.01 - 4. 382.0 0.06 - 4. 392.4 0.02 - 4. 410.0 0.08 - 4. 412.8 0.03 - 4. 500.5 0.05 - 4. 528.8 0.05 - 4. 583.9 0.050 - 4. 588.9 0.12 - 4. 617.5 0.08 - 4. 680.6 0.001 - 4. 691.0 0.08 - 4. 717.1 0.005 - 4. 721.2 0.008 - 4. 878.6 0.049 - 4. 896.7 0.048 - 4. 952.0 0.009 - 4. 988.4 0.002 - 4. 1033.0 0.07 - 4. 1049.8 0.03 - 4. 1126.2 0.002 - 4. 1176.8 0.02 - 4. 1445.7 0.065 +DATA 4 66 +E NUMBER DATA DATA-ERR +KEV NO-DIM NO-DIM NO-DIM + 142.4 2. -0.27 0.04 + 142.4 4. -0.07 0.04 + 217.0 2. 0.026 0.025 + 217.0 4. 0.05 0.06 + 249.9 2. -0.28 0.05 + 249.9 4. 0.01 0.06 + 258.7 2. 0.135 0.016 + 258.7 4. -0.003 0.021 + 298.6 2. 0.018 0.024 + 298.6 4. 0.02 0.03 + 316.2 2. 0.086 0.013 + 316.2 4. -0.10 0.19 + 322.3 2. 0.15 0.03 + 322.3 4. -0.08 0.04 + 333.0 2. 0.101 0.016 + 333.0 4. -0.016 0.024 + 339.3 2. -0.037 0.016 + 339.3 4. -0.003 0.023 + 364.4 2. -0.037 0.018 + 364.4 4. -0.044 0.025 + 374.6 2. 0.127 0.025 + 374.6 4. -0.01 0.03 + 382.0 2. 0.17 0.03 + 382.0 4. 0.06 0.03 + 392.4 2. 0.065 0.025 + 392.4 4. -0.02 0.04 + 410.0 2. -0.28 0.04 + 410.0 4. 0.08 0.05 + 412.8 2. 0.16 0.05 + 412.8 4. 0.03 0.04 + 500.5 2. -0.42 0.06 + 500.5 4. 0.05 0.07 + 528.8 2. 0.28 0.07 + 528.8 4. -0.05 0.08 + 583.9 2. 0.236 0.012 + 583.9 4. -0.050 0.013 + 588.9 2. 0.30 0.03 + 588.9 4. -0.12 0.03 + 617.5 2. 0.153 0.022 + 617.5 4. -0.08 0.03 + 680.6 2. -0.111 0.016 + 680.6 4. 0.001 0.022 + 691.0 2. 0.14 0.03 + 691.0 4. -0.08 0.04 + 717.1 2. -0.044 0.025 + 717.1 4. 0.005 0.004 + 721.2 2. 0.100 0.005 + 721.2 4. 0.008 0.008 + 878.6 2. -0.111 0.021 + 878.6 4. 0.049 0.025 + 896.7 2. 0.113 0.010 + 896.7 4. 0.048 0.014 + 952.0 2. -0.141 0.018 + 952.0 4. 0.009 0.011 + 988.4 2. -0.006 0.012 + 988.4 4. 0.002 0.015 + 1033.0 2. -0.10 0.04 + 1033.0 4. -0.07 0.06 + 1049.8 2. 0.035 0.012 + 1049.8 4. -0.03 0.04 + 1126.2 2. -0.074 0.009 + 1126.2 4. 0.002 0.011 + 1176.8 2. -0.01 0.04 + 1176.8 4. -0.02 0.05 + 1445.7 2. -0.132 0.009 + 1445.7 4. -0.065 0.013 ENDDATA 68 -ENDSUBENT 83 +ENDSUBENT 85 ENDENTRY 9 diff --git a/exforall/411/41147.x4 b/exforall/411/41147.x4 index 0035489ae..30e16c545 100644 --- a/exforall/411/41147.x4 +++ b/exforall/411/41147.x4 @@ -1,328 +1,42 @@ -ENTRY 41147 20060127 20060525 20060324 4137 -SUBENT 41147001 20060127 20060525 20060324 4137 -BIB 10 34 -TITLE Measurement And Comparison With Calculation Of - Reaction Velocities (N,Gamma), (N,2n), (N,F) In - Spherical Assemblies Consisting Of Metallic Uranium - And Thorium At Placing In Their Center 14-MeV - Neutron Source -AUTHOR (V.A.ZAGRYADSKIY,M.I.KRAYNEV,D.V.MARKOVSKIY, - V.I.NOVIKOV,YU.P.SEL'DYAKOV,D.YU.CHUVILIN, - G.E.SHATALOV) +ENTRY 41147 20240916 20250110 20250110 4220 +SUBENT 41147001 20240916 20250110 20250110 4220 +BIB 9 25 +TITLE Measurement and comparison with calculation of + (n,gamma), (n,2n), (n,f) reaction velocities in + spherical assemblies consisting of metallic uranium + and thorium at placing a 14-MeV neutron source in the + assemblies center +AUTHOR (V.A.Zagryadskiy,M.I.Kraynev,D.V.Markovskiy, + V.M.Novikov,Yu.P.Sel'dyakov,D.Yu.Chuvilin, + G.E.Shatalov) +REFERENCE (R,IAE-4480/8,1987) Main ref. Data tables are given INSTITUTE (4RUSKUR) -REFERENCE (R,IAE-4480/8,1987) Main Ref. Data tables are given - (R,IAE-4197/8,1985) Experimental Details -FACILITY (VDG) +REL-REF (I,,V.M.Novikov+,R,IAE-4197/8,1985) Exp. details +FACILITY (VDG,4RUSKUR) MONITOR (29-CU-65(N,2N)29-CU-64,,SIG) METHOD (ACTIV) -STATUS Data Are Taken From Main Reference -ERR-ANALYS (ERR-T) Total Error - (ERR-1) Error Of Photon Peak Area Determination - (ERR-2) Error Of Gamma-spectrometer Efficiency - (ERR-3) Error Of Gamma-quanta Self-absorption - Determination - (ERR-4) Error Of Absolute Neutron Yield Determination - (ERR-5) Error Of Absolute Nucleus Number - Determination - (ERR-6) Error Of Nuclear Decay Quantum Yield - Determination - (ERR-7) Error Of Fission Fragments Number - Determination - (ERR-8) Error Of Numerical Integration On The Volume - Of The Assembly HISTORY (19940519C) + + Compiled at the centre - CJD + + (20050127A) M.M. Reaction codes of Sub.2-11 were - corrected.Units of data were corrected in according to + corrected.Units of data were corrected according to a comment of author D.V.Markovskiy. - Dates were corrected for 4-digits Year. -ENDBIB 34 -COMMON 8 6 -ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 -ERR-7 ERR-8 -PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT -PER-CENT PER-CENT - 2.5 1.5 1.5 2. 0.1 2. - 5. 2. -ENDCOMMON 6 -ENDSUBENT 44 -SUBENT 41147002 20060127 20060525 20060324 4137 -BIB 7 20 -REACTION (90-TH-232(N,2N)90-TH-231,,SGV,,FCT/SPA) - Reaction rate normalized to one neutron of source, - averaged over assembly volume. -SAMPLE Thin metallic foils of 0.22 mm thicknes,10mm diameter. - Copper foils of 0.5 mm thickness, 10 mm diameter - Cu-65 content is 99.8 %. - Foils were placed at 100 mm distance from target - center at angles of 0,25,50,70,100,120,140 degrees to - deuteron beam direction. -INC-SOURCE (D-T) Neutron generator in the center. - 10E+10 neutrons/sec. -INC-SPECT Only direct neutrons of 14.MeV source were taken into - account -DETECTOR (GE-IN) BDR1-200 germanium detector with berylium - window for Th-231 activity measurement. - (NAICR) NaI(Tl) scincilation gamma-spectrometer for - copper activity measurement. -DECAY-DATA (90-TH-231,25.52HR,DG,84.2) - (29-CU-64,12.7HR,DG,511.) -STATUS From Table 1 of main reference. -ENDBIB 20 -NOCOMMON 0 -DATA 3 1 -EN DATA ERR-T -EV 1/SEC 1/SEC - 1.4E+07 0.198 0.009 -ENDDATA 3 + Dates were corrected for 4-digits year. + (20240916A) ERR-ANALYS was updated (Table 2). + Upper -> lower case correction. + STATUS information was updated. + (20241202D) Data Subents were deleted according to a + comment from NDS,IAEA - data are not for EXFOR. + (If it needs, data can be found in archive.) +ENDBIB 25 +NOCOMMON 0 0 ENDSUBENT 28 -SUBENT 41147003 20060127 20060525 20060324 4137 -BIB 8 26 -REACTION (90-TH-232(N,2N)90-TH-231,,SGV,,FCT/SPA) - Reaction rate normalized to one neutron of source, - averaged over assembly volume. -SAMPLE Thin metallic foils of 0.22 mm thicknes,10mm diameter. - Copper foils of 0.5 mm thickness, 10 mm diameter - Cu-65 content is 99.8 %. - Foils were placed at 60,70,86,101,116,130 mm distance - from target.Thorium blocks between foils. - Thorium assembly of outside diameter- 260mm, inside - diameter - 120mm had a channel of 50mm(for neutron - generater placing) and radial channels at angles of - 0,25,50,70,100,120,140 degrees to deuteron beam - direction. I -INC-SOURCE (D-T) Neutron generator in the center of thorium - assembly. 10E+10 neutrons/sec. -INC-SPECT Direct 14-MeV neutrons plus secondary neutrons were - taken into account. -DETECTOR (GE-IN) BDR1-200 germanium detector with berylium - window for Th-231 activity measurement. - (NAICR) NaI(Tl) crystal scincilation gamma-spectrometer - for copper activity measurement. -DECAY-DATA (90-TH-231,25.52HR,DG,84.2) - (29-CU-64,12.7HR,DG,511.) -STATUS From Table 1 of main reference. -COMMENT Reaction rate for secondary neutrons spectrum was - determined to be 0.035+-0.013 1/sec. -ENDBIB 26 -NOCOMMON 0 -DATA 3 1 -EN-DUMMY DATA ERR-T -EV 1/SEC 1/SEC - 1.4E+07 0.233 0.010 -ENDDATA 3 -ENDSUBENT 34 -SUBENT 41147004 20060127 20060525 20060324 4137 -BIB 8 20 -REACTION (90-TH-232(N,F),,SGV,,FCT/SPA) - Reaction rate normalized to one neutron of source, - averaged over assembly volume. -SAMPLE Thin metallic foils of 0.22 mm thicknes,10mm diameter. - Copper foils of 0.5 mm thickness, 10 mm diameter - Cu-65 content is 99.8 % -INC-SOURCE (D-T) Neutron generator in the center. - 10E+10 neutrons/sec. -INC-SPECT Only direct neutrons of 14.MeV source were taken into - account -DETECTOR (SISD) DKPs-25 silicon detector for determination of - relative distribution of reaction rate in assembly - volume. - (GELI) Gamma-spectrometer with coaxial Ge-Li detector - for absolute reaction rate determination -PART-DET (FF) - (G) -DECAY-DATA (42-MO-99,2.7489D,DG,140.5) - (58-CE-143,33.039HR,DG,293.3) -STATUS From Table 1 of main reference. -ENDBIB 20 -NOCOMMON 0 -DATA 3 1 -EN DATA ERR-T -EV 1/SEC 1/SEC - 1.4E+07 0.0558 0.0032 -ENDDATA 3 -ENDSUBENT 28 -SUBENT 41147005 20060127 20060525 20060324 4137 -BIB 9 22 -REACTION (90-TH-232(N,F),,SGV,,FCT/SPA) - Reaction rate normalized to one neutron of source, - averaged over assembly volume. -SAMPLE Thin metallic foils of 0.22 mm thicknes,10mm diameter. - Copper foils of 0.5 mm thickness, 10 mm diameter, - Cu-65 content is 99.8 pc -INC-SOURCE (D-T) Neutron generator in the center of thorium - assembly. 10E+10 neutrons/sec. -INC-SPECT Direct 14-MeV neutrons plus secondary neutrons were - taken into account. -DETECTOR (SISD) DKPs-25 silicon detector for determination of - relative distribution of reaction rate in assembly - volume. - (GELI) Gamma-spectrometer with coaxial Ge-Li detector - for absolute reaction rate determination -PART-DET (FF) - (G) -DECAY-DATA (42-MO-99,2.7489D,DG,140.5) - (58-CE-143,33.039HR,DG,293.3) -STATUS From Table 1 of main reference -COMMENT Reaction rate for secondary neutrons spectrum was - determined to be 0.0208+-0.0047 1/sec. -ENDBIB 22 -NOCOMMON 0 -DATA 3 1 -EN-DUMMY DATA ERR-T -EV 1/SEC 1/SEC - 1.4E+07 0.0766 0.0034 -ENDDATA 3 -ENDSUBENT 30 -SUBENT 41147006 20060127 20060525 20060324 4137 -BIB 5 11 -REACTION (90-TH-232(N,G)90-TH-233,,SGV,,FCT/SPA) - Reaction rate normalized to one neutron of source, - averaged over assembly volume. -SAMPLE Thin metallic foil, 0.22 mm thicknes, 10mm diameter - Copper foil 0.5 mm thickness, 10 mm diameter - Cu-65 content is 99.8 % -INC-SOURCE (D-T) Neutron generator in the center of thorium - assembly. 10E+10 neutrons/sec. -INC-SPECT Direct 14-MeV neutrons plus secondary neutrons were - taken into account. -STATUS From Table 1 of main reference -ENDBIB 11 -NOCOMMON 0 -DATA 3 1 -EN-DUMMY DATA ERR-T -EV 1/SEC 1/SEC - 1.4E+07 0.0506 0.002 -ENDDATA 3 -ENDSUBENT 19 -SUBENT 41147007 20060127 20060525 20060324 4137 -BIB 8 15 -REACTION (92-U-238(N,2N)92-U-237,,SGV,,FCT/SPA) - Reaction rate normalized to one neutron of source, - averaged over assembly volume. -SAMPLE Thin metallic foils,0.15 mm thickness, 10 mm diameter - U-238 content is 99.6 %, U-235 - 0.4%. - Copper foil 0.5 mm thickness, 10 mm diameter - Cu-65 content is 99.8 % -DETECTOR (GELI) Gamma-spectrometer with coaxial Ge-Li detector - for activity determination -PART-DET (G) -DECAY-DATA (92-U-237,,DG,208.) -INC-SOURCE (D-T) Neutron generator in the center of uranium - assembly. 10E+10 neutrons/sec. -INC-SPECT Direct 14-MeV neutrons were taken into account. -STATUS From Table 3 of main reference -ENDBIB 15 -NOCOMMON 0 -DATA 3 1 -EN DATA ERR-T -EV 1/SEC 1/SEC - 1.4E+07 0.199 0.010 -ENDDATA 3 -ENDSUBENT 23 -SUBENT 41147008 20060127 20060525 20060324 4137 -BIB 9 18 -REACTION (92-U-238(N,2N)92-U-237,,SGV,,FCT/SPA) - Reaction rate normalized to one neutron of source, - averaged over assembly volume. -SAMPLE Thin metallic foils,0.15 mm thickness, 10 mm diameter - U-238 content is 99.6 %, U-235 - 0.4%. - Copper foil 0.5 mm thickness, 10 mm diameter - Cu-65 content is 99.8 % -DETECTOR (GELI) Gamma-spectrometer with coaxial Ge-Li detector - for activity determination -PART-DET (G) -DECAY-DATA (92-U-237,,DG,208.) -INC-SOURCE (D-T) Neutron generator in the center of uranium - assembly. 10E+10 neutrons/sec. -INC-SPECT Direct 14-MeV neutrons plus secondary neutrons were - taken into account. -STATUS From Table 3 of main reference -COMMENT Reaction rate for secondary neutrons spectrum was - determined to be 0.055+-0.016 1/sec. -ENDBIB 18 -NOCOMMON 0 -DATA 3 1 -EN-DUMMY DATA ERR-T -EV 1/SEC 1/SEC - 1.4E+07 0.254 0.012 -ENDDATA 3 -ENDSUBENT 26 -SUBENT 41147009 20060127 20060525 20060324 4137 -BIB 7 15 -REACTION (92-U-238(N,F),,SGV,,FCT/SPA) - Reaction rate normalized to one neutron of source, - averaged over assembly volume. -SAMPLE Metallic plate, 1 mm thickness, 10 mm diameter - U-238 content is 99.6 %, U-235 -0.4%. - Copper foil 0.5 mm thickness, 10 mm diameter - Cu-65 content is 99.8 % -DETECTOR (GELI) Gamma-spectrometer with coaxial Ge-Li detector - for activity determination -DECAY-DATA (58-CE-143,,DG,293.3) - (57-LA-140,,DG,1596.5) -INC-SOURCE (D-T) Neutron generator in the center of uranium - assembly. 10E+10 neutrons/sec. -INC-SPECT Direct 14-MeV neutrons were taken into account. -STATUS From Table 3 of main reference -ENDBIB 15 -NOCOMMON 0 -DATA 3 1 -EN DATA ERR-T -EV 1/SEC 1/SEC - 1.4E+07 0.250 0.013 -ENDDATA 3 -ENDSUBENT 23 -SUBENT 41147010 20060127 20060525 20060324 4137 -BIB 8 18 -REACTION (92-U-238(N,F),,SGV,,FCT/SPA) - Reaction rate normalized to one neutron of source, - averaged over assembly volume. -SAMPLE Metallic plate, 1 mm thickness, 10 mm diameter - U-238 content is 99.6 %, U-235 -0.4%. - Copper foil 0.5 mm thickness, 10 mm diameter - Cu-65 content is 99.8 % -DETECTOR (GELI) Gamma-spectrometer with coaxial Ge-Li detector - for activity determination -DECAY-DATA (58-CE-143,,DG,293.3) - (57-LA-140,,DG,1596.5) -INC-SOURCE (D-T) Neutron generator in the center of uranium - assembly. 10E+10 neutrons/sec. -INC-SPECT Direct 14-MeV neutrons plus secondary neutrons were - taken into account. -STATUS From Table 3 of main reference -COMMENT Reaction rate for secondary neutrons spectrum was - determined to be 0.237+-0.024 1/sec. -ENDBIB 18 -NOCOMMON 0 -DATA 3 1 -EN-DUMMY DATA ERR-T -EV 1/SEC 1/SEC - 1.4E+07 0.487 0.020 -ENDDATA 3 -ENDSUBENT 26 -SUBENT 41147011 20060127 20060525 20060324 4137 -BIB 7 15 -REACTION (92-U-238(N,G)92-U-239,,SGV,,FCT/SPA) - Reaction rate normalized to one neutron of source, - averaged over assembly volume. -SAMPLE Thin metallic foil, 0.15 mm thicknes, 10 mm diameter - U-238 content is 99.6 %, U-235 -0.4%. - Copper foil 0.5 mm thickness, 10 mm diameter - Cu-65 content is 99.8 % -DETECTOR (GELI) Gamma-spectrometer with coaxial Ge-Li detector - for activity determination -INC-SOURCE (D-T) Neutron generator in the center of uranium - assembly. 10E+10 neutrons/sec. -INC-SPECT Direct 14-MeV neutrons plus secondary neutrons were - taken into account. -DECAY-DATA (93-NP-239,,DG,277.6) -STATUS From Table 3 of main reference -ENDBIB 15 -NOCOMMON 0 -DATA 3 1 -EN-DUMMY DATA ERR-T -EV 1/SEC 1/SEC - 1.4E+07 0.295 0.012 -ENDDATA 3 -ENDSUBENT 23 +SUBENT 41147002 20240916 20250110 20250110 4220 +SUBENT 41147003 20240916 20250110 20250110 4220 +SUBENT 41147004 20240916 20250110 20250110 4220 +SUBENT 41147005 20240916 20250110 20250110 4220 +SUBENT 41147006 20240916 20250110 20250110 4220 +SUBENT 41147007 20240916 20250110 20250110 4220 +SUBENT 41147008 20240916 20250110 20250110 4220 +SUBENT 41147009 20240916 20250110 20250110 4220 +SUBENT 41147010 20240916 20250110 20250110 4220 +SUBENT 41147011 20240916 20250110 20250110 4220 ENDENTRY 11 diff --git a/exforall/411/41149.x4 b/exforall/411/41149.x4 index 78df5e6e1..65bfca883 100644 --- a/exforall/411/41149.x4 +++ b/exforall/411/41149.x4 @@ -1,83 +1,96 @@ -ENTRY 41149 20010311 20011019 20050926 0000 -SUBENT 41149001 20010311 20011019 20050926 0000 -BIB 10 14 +ENTRY 41149 20240916 20250110 20250110 4220 +SUBENT 41149001 20240916 20250110 20250110 4220 +BIB 10 18 +TITLE Gamma-ray intensities at the decay of 166mHo +AUTHOR (V.N.Danilenko,N.V.Kurenkov,A.B.Malinin,S.V.Matveev, + E.K.Stepanov) +REFERENCE (C,88BAKU,,114,1988) Data table is given INSTITUTE (4RUSFRT) -REFERENCE (C,88BAKU,,114,198804) DATA TABLE IS GIVEN -AUTHOR (V.N.DANILENKO,N.V.KURENKOV,A.B.MALININ,S.V.MATVEEEV, - E.K.STEPANOV) -TITLE GAMMA-RAY INTENSITIES AT THE DECAY OF HO-166-M -FACILITY (REAC) REACTOR WITH HIGH NEUTRON FLUX -INC-SPECT FAST SPECTRUM OF THE THERMAL REACTOR -MONITOR NO INFORMATION -ERR-ANALYS (ERR-S) STATISTICAL ERROR FOR 0.68 CONFIDENCE - PROBABILITY -STATUS DATA ARE TAKEN FROM THE REFERENCE -HISTORY (19940530C) + + COMPILED AT THE CENTRE - CJD + + - (19950424U) - - REACTION CODE IN SAN 002 CORRECTED +FACILITY (REAC) Reactor With High Neutron Flux +INC-SPECT Fast spectrum of the thermal reactor +MONITOR No information +DETECTOR Gamma spectrometer, energy resolution 2.3 keV for + 1332. keV line. +ERR-ANALYS (ERR-S) Statistical error for 0.68 confidence + probability +HISTORY (19940530C) + + Compiled at the centre - CJD + + + (19950424U) - - REACTION code in SAN 002 corrected (20010311A) DATE is corrected -ENDBIB 14 + (20240916A) Subent 002 was corrected. + Upper -> lower case correction. + STATUS information was updated. +ENDBIB 18 COMMON 1 3 EN-DUMMY EV 1.0E+06 ENDCOMMON 3 -ENDSUBENT 21 -SUBENT 41149002 20010311 20011019 20050926 0000 -BIB 2 3 -REACTION (67-HO-165(N,G)67-HO-166-M,,SPC,,REL/FIS) REFERENCE - QUANTITY IS NOT GIVEN -HISTORY (19950424U) 'PAR' REMOVED IN REACTION SF5 -ENDBIB 3 -NOCOMMON 0 0 +ENDSUBENT 25 +SUBENT 41149002 20240916 20250110 20250110 4220 +BIB 4 8 +REACTION ((67-HO-165(N,G)67-HO-166-M,,SPC,,FIS)// + (67-HO-165(N,G)67-HO-166-M,,SPC,,FIS)) +DECAY-DATA (67-HO-166-M,1200.YR) +STATUS (TABLE,,V.N.Danilenko+,C,88BAKU,,114,1988) +HISTORY (19950424U) 'PAR' removed in REACTION SF5 + (20240916A) REACTION was corrected as ratio. + E -> E-NM, E-DN was introduced. + Data were divided by 100. to obtain units NO-DIM +ENDBIB 8 +COMMON 1 3 +E-DN +KEV + 810.3 +ENDCOMMON 3 DATA 3 46 -E DATA ERR-S -KEV ARB-UNITS ARB-UNITS - 80.5 22.1 0.5 - 94.7 0.26 0.03 - 119.0 0.30 0.04 - 121.3 0.53 0.05 - 135.3 0.236 0.019 - 140.8 0.34 0.14 - 160.1 0.187 0.018 - 161.8 0.197 0.018 - 184.4 125.7 1.3 - 190.8 0.33 0.03 - 214.8 0.78 0.04 - 215.9 4.51 0.09 - 231.4 0.345 0.018 - 259.8 1.89 0.04 - 280.5 50.8 0.5 - 300.8 6.37 0.06 - 339.7 0.32 0.03 - 365.7 4.26 0.04 - 410.9 19.81 0.14 - 451.5 5.11 0.07 - 464.8 2.09 0.05 - 496.9 0.208 0.020 - 520.9 0.301 0.016 - 529.8 16.75 0.13 - 571.0 9.71 0.08 - 594.4 0.99 0.03 - 611.5 2.38 0.07 - 640.0 0.184 0.015 - 644.5 0.267 0.020 - 670.5 9.47 0.08 - 691.2 2.29 0.03 - 711.7 95.0 8.0 - 736.7 0.694 0.017 - 752.3 21.12 0.20 - 778.8 5.30 0.06 - 810.3 100.0 - 830.6 16.98 0.08 - 875.6 1.253 0.013 - 951.0 4.77 0.03 - 1010.3 0.128 0.012 - 1120.3 0.62 0.16 - 1146.9 0.351 0.021 - 1241.5 1.379 0.015 - 1282.1 0.332 0.009 - 1400.7 0.896 0.017 - 1427.3 0.887 0.012 +E-NM DATA ERR-S +KEV NO-DIM NO-DIM + 80.5 22.1 E-02 0.5 E-02 + 94.7 0.26 E-02 0.03 E-02 + 119.0 0.30 E-02 0.04 E-02 + 121.3 0.53 E-02 0.05 E-02 + 135.3 0.236E-02 0.019E-02 + 140.8 0.34 E-02 0.14 E-02 + 160.1 0.187E-02 0.018E-02 + 161.8 0.197E-02 0.018E-02 + 184.4 125.7 E-02 1.3 E-02 + 190.8 0.33 E-02 0.03 E-02 + 214.8 0.78 E-02 0.04 E-02 + 215.9 4.51 E-02 0.09 E-02 + 231.4 0.345E-02 0.018E-02 + 259.8 1.89 E-02 0.04 E-02 + 280.5 50.8 E-02 0.5 E-02 + 300.8 6.37 E-02 0.06 E-02 + 339.7 0.32 E-02 0.03 E-02 + 365.7 4.26 E-02 0.04 E-02 + 410.9 19.81 E-02 0.14 E-02 + 451.5 5.11 E-02 0.07 E-02 + 464.8 2.09 E-02 0.05 E-02 + 496.9 0.208E-02 0.020E-02 + 520.9 0.301E-02 0.016E-02 + 529.8 16.75 E-02 0.13 E-02 + 571.0 9.71 E-02 0.08 E-02 + 594.4 0.99 E-02 0.03 E-02 + 611.5 2.38 E-02 0.07 E-02 + 640.0 0.184E-02 0.015E-02 + 644.5 0.267E-02 0.020E-02 + 670.5 9.47 E-02 0.08 E-02 + 691.2 2.29 E-02 0.03 E-02 + 711.7 95.0 E-02 8.0 E-02 + 736.7 0.694E-02 0.017E-02 + 752.3 21.12 E-02 0.20 E-02 + 778.8 5.30 E-02 0.06 E-02 + 810.3 100.0 E-02 + 830.6 16.98 E-02 0.08 E-02 + 875.6 1.253E-02 0.013E-02 + 951.0 4.77 E-02 0.03 E-02 + 1010.3 0.128E-02 0.012E-02 + 1120.3 0.62 E-02 0.16 E-02 + 1146.9 0.351E-02 0.021E-02 + 1241.5 1.379E-02 0.015E-02 + 1282.1 0.332E-02 0.009E-02 + 1400.7 0.896E-02 0.017E-02 + 1427.3 0.887E-02 0.012E-02 ENDDATA 48 -ENDSUBENT 56 +ENDSUBENT 65 ENDENTRY 2 diff --git a/exforall/411/41150.x4 b/exforall/411/41150.x4 index a9ceed486..3ce7b37f5 100644 --- a/exforall/411/41150.x4 +++ b/exforall/411/41150.x4 @@ -1,66 +1,106 @@ -ENTRY 41150 19940615 20050926 0000 -SUBENT 41150001 19940615 20050926 0000 -BIB 10 10 -AUTHOR (M.R.BEYTIN'SH,P.K.PROKOF'EV) +ENTRY 41150 20240916 20250110 20250110 4220 +SUBENT 41150001 20240916 20250110 20250110 4220 +BIB 9 14 +TITLE Investigation of W-183 in the reacton (n,n'gamma) +AUTHOR (M.R.Beytin'sh,P.K.Prokof'ev) +REFERENCE (C,88BAKU,,125,1988) INSTITUTE (4LATIFL) -REFERENCE (C,88BAKU,,125,8804) -TITLE INVESTIGATION OF W-183 IN THE REACTON (N,N'GAMMA) -FACILITY (REAC) IRT-M REACTOR -DETECTOR (HPGE) GERMANIUM DETECTOR -MONITOR NO INFORMATION -STATUS DATA TAKEN FROM THE REFERENCE -ERR-ANALYS (ERR-S) NOT SPECIFIED, SUPPOSED STATISTICAL -HISTORY (940607C) + + COMPILED AT THE CENTRE - CJD + + -ENDBIB 10 -NOCOMMON -ENDSUBENT 13 -SUBENT 41150002 19940615 20050926 0000 -BIB 4 6 -REACTION (74-W-183(N,INL)74-W-183,,SPC,,REL) REFERENCE - QUANTITY IS NOT GIVEN -SAMPLE METALLIC TUNGSTEN POWDER, WEIGHT 8 GRAM, - W-183 CONTENT IS 98.PC -INC-SPECT FAST NEUTRON SPECTRUM OF THE THERMAL REACTOR -FLAG (1.) GAMMA-LINE FROM SEVERAL LEVELS -ENDBIB 6 +FACILITY (REAC,4LATIFL) IRT-M reactor +DETECTOR (HPGE) Germanium detector of 78 cm3 volume, energy + resolution 1.8 keV for 1.33 MeV energy +MONITOR No information +ERR-ANALYS (DATA-ERR) Not specified +HISTORY (19940607C) + + Compiled at the centre - CJD + + + (20240916A) Subent 002 was corrected. + Upper -> lower case correction. + Dates were corrected for 4-digits year. + STATUS information was updated. ERR-S -> DATA-ERR. +ENDBIB 14 +NOCOMMON 0 0 +ENDSUBENT 17 +SUBENT 41150002 20240916 20250110 20250110 4220 +BIB 6 8 +REACTION (74-W-183(N,INL)74-W-183,,SPC,,REL) Reference + quantity is not given +SAMPLE Metallic tungsten powder, weight 8 gram, + (74-W-183,ENR=0.98) W-183 content is 98.%. +INC-SPECT Fast neutron spectrum of the thermal reactor +FLAG (1.) Gamma-line from several levels +STATUS (TABLE,,M.R.Beytin'sh+,C,88BAKU,,125,1988) +HISTORY (20240916A) LVL-INI, LVL-INI-ER were added. +ENDBIB 8 COMMON 1 3 EN-DUMMY EV 1.0E+6 ENDCOMMON 3 -DATA 5 30 -E E-ERR DATA ERR-S FLAG -KEV KEV ARB-UNITS ARB-UNITS NO-DIM - 144.14 0.09 59. 06. - 159.32 0.08 140. 20. - 166.32 0.08 190. 20. - 175.84 0.05 360. 40. - 186.16 0.06 180. 20. - 202.56 0.08 90. 10. - 215.26 0.22 044. 05. - 264.88 0.01 38. 6. - 268.27 0.04 280. 30. - 325.68 0.09 120. 20. - 935.1 0.5 036. 4. - 944.0 0.4 540. 50. - 953.1 0.6 120. 10. - 981.8 0.5 170. 20. - 996.9 0.4 330. 30. - 1000.05 0.15 470. 50. - 1043.1 0.3 300. 30. 1. - 1089.3 0.4 600. 60. - 1204.5 0.6 3200. 300. - 1250.7 0.6 760. 30. - 1379.05 0.11 1300. 200. 1. - 1431.8 0.4 520. 50. - 1458.3 0.7 100. 10. - 1478.8 0.6 800. 80. - 1490.2 0.4 290. 30. - 1510.3 0.6 50. 6. - 1536.3 0.6 200. 20. - 1556.8 0.7 500. 50. - 1697.3 1.1 055. 6. - 1743.6 1.7 180. 20. -ENDDATA 32 -ENDSUBENT 47 +DATA 7 31 +E E-ERR DATA DATA-ERR FLAG LVL-INI +LVL-INI-ER +KEV KEV ARB-UNITS ARB-UNITS NO-DIM KEV +KEV + 144.14 0.09 59. 06. 556.4 + 0.4 + 159.32 0.08 140. 20. 634.61 + 0.16 + 166.32 0.08 190. 20. 475.67 + 0.11 + 175.84 0.05 360. 40. 485.33 + 0.10 + 186.16 0.06 180. 20. 810.5 + 0.3 + 202.56 0.08 90. 10. 687.89 + 0.12 + 215.26 0.22 044. 05. 810.5 + 0.3 + 264.88 0.01 38. 6. 556.4 + 0.4 + 268.27 0.04 280. 30. 475.67 + 0.11 + 325.68 0.09 120. 20. 634.61 + 0.16 + 935.1 0.5 036. 4. 981.9 + 0.6 + 944.0 0.4 540. 50. 1043.1 + 0.5 + 953.1 0.6 120. 10. 1000.1 + 0.7 + 981.8 0.5 170. 20. 981.9 + 0.6 + 996.9 0.4 330. 30. 1043.1 + 0.5 + 1000.05 0.15 470. 50. 1000.1 + 0.7 + 1043.1 0.3 300. 30. 1. 1043.1 + 0.5 + 1043.1 0.3 300. 30. 1. 1089.3 + 0.4 + 1089.3 0.4 600. 60. 1089.3 + 0.4 + 1204.5 0.6 3200. 300. 1250.9 + 0.7 + 1250.7 0.6 760. 30. 1250.9 + 0.7 + 1379.05 0.11 1300. 200. 1. 1478.7 + 0.7 + 1431.8 0.4 520. 50. 1478.7 + 0.7 + 1458.3 0.7 100. 10. 1556.8 + 0.8 + 1478.8 0.6 800. 80. 1478.7 + 0.7 + 1490.2 0.4 290. 30. 1536.4 + 0.6 + 1510.3 0.6 50. 6. 1556.8 + 0.8 + 1536.3 0.6 200. 20. 1536.4 + 0.6 + 1556.8 0.7 500. 50. 1556.8 + 0.8 + 1697.3 1.1 055. 6. 1743.9 + 1.1 + 1743.6 1.7 180. 20. 1743.9 + 1.1 +ENDDATA 66 +ENDSUBENT 83 ENDENTRY 2 diff --git a/exforall/411/41151.x4 b/exforall/411/41151.x4 index 7d65982f2..b8959fc0d 100644 --- a/exforall/411/41151.x4 +++ b/exforall/411/41151.x4 @@ -1,37 +1,44 @@ -ENTRY 41151 19990820 19991117 20050926 0000 -SUBENT 41151001 19990820 19991117 20050926 0000 -BIB 13 20 -TITLE DETERMINATION OF THE PARAMETERS OF CROSS-SECTIONS - RESONANCE STRUCTURE FOR TH-232 IN THE ENERGY RANGE - 4.65 - 46500 EV -AUTHOR (YU.V.GRIGOR'EV,G.N.MANTUROV,V.V.SINITSA,G.P.GEORGIEV, - B.I.IVANOV,I.A.SIRAKOV,N.B.YANEVA) -INSTITUTE (4RUSFEI) GRIGOR'EV, MANTUROV, SINITSA - (4ZZZDUB) GEORGIEV, IVANOV, SIRAKOV, YANEVA -REFERENCE (R,FEI-2120,199009) DATA TABLES ARE GIVEN -FACILITY (REAC,4ZZZDUB) FAST PULSE REACTOR IBR-30 -METHOD (TOF) FLIGHT BASE IS 59.4 M -MONITOR NOINFORMATION -DETECTOR (SCIN) LIQUID SCINTILLATION DETECTOR +ENTRY 41151 20240916 20250110 20250110 4220 +SUBENT 41151001 20240916 20250110 20250110 4220 +BIB 13 25 +TITLE Calculational-experimental investigation of resonance + structure of total and capture cross sections for + Th-232 in energy ragion 4.65 eV - 46.5 keV +AUTHOR (Yu.V.Grigor'ev,G.N.Manturov,V.V.Sinitsa,G.P.Georgiev, + B.I.Ivanov,I.A.Sirakov,N.B.Yaneva) +REFERENCE (R,FEI-2120,1990) Data tables are given +INSTITUTE (4RUSFEI) Grigor'ev, Manturov, Sinitsa + (4ZZZDUB) Georgiev, Ivanov, Sirakov, Yaneva +FACILITY (REAC,4ZZZDUB) Fast pulse reactor IBR-30 +METHOD (TOF) Flight base is 59.4 m +MONITOR No information +DETECTOR (SCIN) Liquid scintillation detector PART-DET (G,N) -SAMPLE .METALLIC THORIUM DISKS 47 MM IN DIAMETER -INC-SPECT .CADMIUM, INDIUM, MANGANESE, TITANUM FILTERS WERE - INSERTED IN THE NEUTRON BEAM FOR CORRECTION OF THE - NEUTRON SPECTRUM -STATUS .DATA ARE TAKEN FROM THE REFERENCE -HISTORY (19940607C) + + COMPILED AT THE CENTRE - CJD + + - (19990820A) . . DATES CORRECTED. NEW SUBENTS ADDED -ENDBIB 20 +SAMPLE .Metallic thorium disks 47 mm in diameter +INC-SPECT .Cadmium, indium, manganese, titanum filters were + inserted in the neutron beam for correction of the + neutron spectrum +STATUS .Data are taken from the reference +HISTORY (19940607C) + + Compiled at the centre - CJD + + + (19990820A) . . Dates Corrected. New Subents added + (20240916A) Title was corrected as given in English + abstract of the article. + Data Subents were corrected. + Upper -> lower case correction. + STATUS information was updated. +ENDBIB 25 NOCOMMON 0 0 -ENDSUBENT 23 -SUBENT 41151002 19990820 19991117 20050926 0000 -BIB 2 5 -REACTION ((90-TH-232(N,TOT),,SIG,,RAW/AV)= - (90-TH-232(N,TOT),,SIF,,AV)) TRANSMISSION = SELF- - INDICATION FUNCTION AVERAGED OVER ENERGY INTERVAL - GIVEN IN THE DATA TABLE -ERR-ANALYS (DATA-ERR) ERROR IS NOT SPECIFIED -ENDBIB 5 +ENDSUBENT 28 +SUBENT 41151002 20240916 20250110 20250110 4220 +BIB 4 7 +REACTION (90-TH-232(N,TOT),,TRN) +ERR-ANALYS (DATA-ERR) Error is not specified +STATUS (TABLE,,Yu.V.Grigor'ev+,R,FEI-2120,1990) Table 1. +HISTORY (20240916A) REACTION was corrected: + (90-TH-232(N,TOT),,SIG,,RAW/AV)= + (90-TH-232(N,TOT),,SIF,,AV) + -> (90-TH-232(N,TOT),,TRN) +ENDBIB 7 NOCOMMON 0 0 DATA 5 72 EN-MAX EN-MIN THICKNESS DATA DATA-ERR @@ -109,13 +116,13 @@ EV EV ATOMS/B NO-DIM NO-DIM 1.0 E+01 4.65E+00 1.3 E-02 0.840 0.01 1.0 E+01 4.65E+00 6.5 E-03 0.915 0.01 ENDDATA 74 -ENDSUBENT 84 -SUBENT 41151003 19940607 19991117 20050926 0000 -BIB 2 4 -REACTION (90-TH-232(N,G)90-TH-233,,SIF,,RAW/AV) SELF-INDICATION - FUNCTION AVERAGED OVER ENERGY INTERVAL GIVEN - IN THE DATA TABLE -ERR-ANALYS (DATA-ERR) ERROR IS NOT SPECIFIED +ENDSUBENT 86 +SUBENT 41151003 20240916 20250110 20250110 4220 +BIB 3 4 +REACTION (90-TH-232(N,G)90-TH-233,,SIF,,RAW/AV) Self-indication + function averaged over energy interval given +ERR-ANALYS (DATA-ERR) Error is not specified +STATUS (TABLE,,Yu.V.Grigor'ev+,R,FEI-2120,1990) Table 1. ENDBIB 4 NOCOMMON 0 0 DATA 5 57 @@ -150,7 +157,7 @@ EV EV ATOMS/B NO-DIM NO-DIM 4.65E+02 2.15E+02 6.5 E-03 0.874 0.01 2.15E+02 1.0 E+02 1.49E-01 0.132 0.02 2.15E+02 1.0 E+02 9.76E-02 0.256 0.02 - 2.15E+02 1.0 E+02 5.17E-03 0.473 0.02 + 2.15E+02 1.0 E+02 5.17E-02 0.473 0.02 2.15E+02 1.0 E+02 2.58E-02 0.674 0.012 2.15E+02 1.0 E+02 1.3 E-02 0.785 0.01 2.15E+02 1.0 E+02 6.5 E-03 0.859 0.01 @@ -168,7 +175,7 @@ EV EV ATOMS/B NO-DIM NO-DIM 4.65E+01 2.15E+01 6.5 E-03 0.835 0.01 2.15E+01 1.0 E+01 1.49E-01 0.163 0.02 2.15E+01 1.0 E+01 9.76E-02 0.306 0.02 - 2.15E+01 1.0 E+01 5.17E-03 0.532 0.015 + 2.15E+01 1.0 E+01 5.17E-02 0.532 0.015 2.15E+01 1.0 E+01 2.58E-02 0.733 0.01 2.15E+01 1.0 E+01 1.3 E-02 0.850 0.01 2.15E+01 1.0 E+01 6.5 E-03 0.919 0.01 @@ -180,15 +187,17 @@ EV EV ATOMS/B NO-DIM NO-DIM 1.0 E+01 4.65E+00 6.5 E-03 0.915 0.01 ENDDATA 59 ENDSUBENT 68 -SUBENT 41151004 19990820 19991117 20050926 0000 -BIB 2 3 -REACTION (90-TH-232(N,TOT),,SIG,,AV) AVERAGED OVER ENERGY - INTERVAL GIVEN IN THE DATA TABLE -ERR-ANALYS (ERR-T) TOTAL ERROR -ENDBIB 3 +SUBENT 41151004 20240916 20250110 20250110 4220 +BIB 4 5 +REACTION (90-TH-232(N,TOT),,SIG,,AV) Averaged over energy + interval given in the data table +ERR-ANALYS (DATA-ERR) Experimental uncertainty +STATUS (TABLE,,Yu.V.Grigor'ev+,R,FEI-2120,1990) Table 2. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 5 NOCOMMON 0 0 DATA 4 12 -EN-MAX EN-MIN DATA ERR-T +EN-MAX EN-MIN DATA DATA-ERR EV EV B PER-CENT 4.65E+04 2.15E+04 13.9 7. 2.15E+04 1.0 E+04 14.6 @@ -203,5 +212,5 @@ EV EV B PER-CENT 2.15E+01 1.0 E+01 12.3 1.0 E+01 4.65E+00 12.4 25. ENDDATA 14 -ENDSUBENT 22 +ENDSUBENT 24 ENDENTRY 4 diff --git a/exforall/411/41157.x4 b/exforall/411/41157.x4 index 219b5149b..0a5acb417 100644 --- a/exforall/411/41157.x4 +++ b/exforall/411/41157.x4 @@ -1,18 +1,23 @@ -ENTRY 41157 19940914 20050926 0000 -SUBENT 41157001 19940914 20050926 0000 -BIB 11 23 -TITLE YIELDS OF DELAYED NEUTRON PRECURSORS IN THE FISSION - OF ACTINIDES -AUTHOR (A.N.GUDKOV,S.V.KRIVASHEEV,A.B.KOLDOBSKIY, - V.V.KOVALENKO,E.YU.BOBKOV,V.M.ZHIVUN) -REFERENCE (J,RCA,57,69,92) DATA TABLES ARE GIVEN - (R,MIF-058-88,88) PRELIMINARY PUBLICATION +ENTRY 41157 20240916 20250110 20250110 4220 +SUBENT 41157001 20240916 20250110 20250110 4220 +BIB 10 31 +TITLE Yields of delayed neutron precursors in the fission + of actinides +AUTHOR (A.N.Gudkov, S.V.Krivasheyev, A.B.Koldobski, + V.V.Kovalenko, E.Yu.Bobkov, V.M.Givun) + S.V.Krivasheyev=S.V.Krivasheev; V.M.Givun=V.M.Zhivun +REFERENCE (J,RCA,57,69,1992) Data tables are given + (R,MIF-058-88,1988) Preliminary publication INSTITUTE (4RUSMIF,4RUSFEI,4RUSLIN) -MONITOR NO INFORMATION -DETECTOR (BF3) BATTERY OF 24 BF3 COUNTERS -ANALYSIS METHOD OF INCREMENTAL DECONVOLUTION, T.J.KENNETT, - W.V.PRESTWICH, NUCL.INSTR. AND METHODS, VOL.203, P.31 - 1982 +DETECTOR (BF3) Battery of 24 BF3 counters in a water tank. +ANALYSIS Method of incremental deconvolution, see REL-REF of + T.J.Kennett+. +REL-REF (M,,T.J.Kennett+,J,NIM,203,317,1982) + (R,,V.M.Sluchevska+,J,YK,,(3/38),29,1980) + Decay constants and yields + (R,,R.W.Waldo+,J,PR/C,23,1113,1981) + (R,,L.Tomlinson,R,AERE-R-6993,1972) + (R,,G.Benedetti+,J,NSE,80,379,1982) DECAY-DATA (35-BR-87,55.7SEC) (35-BR-88,16.0SEC) (35-BR-89,4.38SEC) @@ -21,25 +26,47 @@ DECAY-DATA (35-BR-87,55.7SEC) (53-I-137,24.5SEC) (53-I-138,6.53SEC) (53-I-139,2.38SEC) -ERR-ANALYS (ERR-T) TOTAL ERROR -STATUS DATA ARE TAKEN FROM THE REFERENCE ONE -HISTORY (940914C) + + COMPILED AT THE CENTRE - CJD + + -ENDBIB 23 -NOCOMMON -ENDSUBENT 26 -SUBENT 41157002 19940914 20050926 0000 -BIB 3 3 +ERR-ANALYS (DATA-ERR) Total error +HISTORY (19940914C) + + Compiled at the centre - CJD + + + (20240916A) Upper -> lower case correction. + Dates were corrected for 4-digits year. + STATUS information was updated. + ERR-T -> DATA-ERR in all data Subents. +ENDBIB 31 +NOCOMMON 0 0 +ENDSUBENT 34 +SUBENT 41157002 20240916 20250110 20250110 4220 +BIB 7 22 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY) FACILITY (REAC,4RUSMIF) -INC-SPECT THERMAL NEUTRON SPECTRUM OF THE REACTOR -ENDBIB 3 +INC-SPECT Thermal neutron spectrum of the reactor +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.06+-0.005) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0126 1/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of + R.W.Waldo+. +REL-REF (R,,V.M.Sluchevska+,J,YK,,(3/38),29,1980) + Decay constant and yield used for normalization. + (N,,W.Grimm,T,GRIMM,1978) + Exp.data used for comparison (%/fis): + Br-87 - 2.25+-0.16, I-137 - 1.91+-0.20, + Br-88 - 2.56+-0.33, I-138 - 0.62+-0.54, + Br-89 - 1.18+-0.56. + (N,21550007,R.Brissot+,J,NP/A,255,461,1975) + Exp.data used for comparison + (N,12926018,R.W.Waldo+,J,PR/C,23,1113,1981) + Exp.data used for comparison. +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 2. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 22 COMMON 1 3 EN-DUMMY EV 2.53E-02 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 2.27 0.28 35. 88. 1.26 0.24 @@ -50,22 +77,61 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 0.70 0.21 53. 139. 0.15 0.05 ENDDATA 10 -ENDSUBENT 22 -SUBENT 41157003 19940914 20050926 0000 -BIB 3 3 +ENDSUBENT 41 +SUBENT 41157003 20240916 20250110 20250110 4220 +BIB 7 42 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) FACILITY (REAC,4RUSMIF) -INC-SPECT THERMAL NEUTRON SPECTRUM OF THE REACTOR -ENDBIB 3 +INC-SPECT thermal neutron spectrum of the reactor +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.054+-0.007) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0124 1/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of + R.W.Waldo+. +REL-REF (R,,V.M.Sluchevska+,J,YK,,(3/38),29,1980) + Decay constant and yield used for normalization. + (N,,E.Lund+,R,BNL-51778,137,1983) + Exp.data used for comparison: + Br-87 - 2.13+-0.20, Br-88 - 1.71+-0.21, + Rb-93 - 3.50+-0.55, Br-98 - 0.92+-0.15 + Rb-94 - 2.11+-0.44 + (N,21550006,R.Brissot+,J,NP/A,255,461,1975) + Exp.data used for comparison + (N,13475001,J.E.Sattizahn+,J,JIN,12,206,1960) + Exp.data used for comparison: Br-87 - 2.70+-0.81 + (N,21689001,W.Lang+,J,NP/A,345,34,1980) + Exp.data used for comparison: + Br-87 - 1.79+-0.05, Rb-93 - 3.44+-0.09, + Br-89 - 1.00+-0.06 + (N,21273002,J.V.Kratz+,C,73ROCH,2,95,1973) + Exp.data used for comparison. + (N,12926019,R.W.Waldo+,J,PR/C,23,1113,1981) + Exp.data used for comparison. + (N,10722001,R.B.Strittmatter,T,STRITTMATTER,1978) + Exp.data used for comparison: + Br-87 - 1.91+-0.04, Rb-93 - 3.44+-0.09 + Br-89 - 1.11+-0.05 + (N,23356001,P.Del Marmol+,J,RCA,16,4,1971) + Exp.data used for comparison: + I-137 - 3.30+-0.50 + (N,21605001,G.Siegert+,J,PR/C,14,1864,1976) + Exp.data used for comparison: + Br-88 - 1.90+-0.08, Br-89 - 1.32+-0.08 + (N,,L.G.Manevich+,R,IAE-4308/4,1985) + Exp.data used for comparison: Rb-94 - 1.73+-0.08 +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 3. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 42 COMMON 1 3 EN-DUMMY EV 2.53E-02 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS - 35. 87. 2.1 0.32 + 35. 87. 2.11 0.32 35. 88. 2.19 0.35 35. 89. 1.11 0.17 37. 93. 3.87 0.74 @@ -74,20 +140,27 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 1.24 0.28 53. 139. 0.89 0.19 ENDDATA 10 -ENDSUBENT 22 -SUBENT 41157004 19940914 20050926 0000 -BIB 3 3 +ENDSUBENT 61 +SUBENT 41157004 20240916 20250110 20250110 4220 +BIB 6 10 REACTION (90-TH-229(N,F)ELEM/MASS,CUM,FY) FACILITY (REAC,4RUSMIF) -INC-SPECT THERMAL NEUTRON SPECTRUM OF THE REACTOR -ENDBIB 3 +INC-SPECT Thermal neutron spectrum of the reactor +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.198+-0.016) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0132 1/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 4. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 10 COMMON 1 3 EN-DUMMY EV 2.53E-02 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 6.77 0.78 35. 88. 3.83 0.46 @@ -98,20 +171,32 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 0.61 0.10 53. 139. 0.30 0.12 ENDDATA 10 -ENDSUBENT 22 -SUBENT 41157005 19940914 20050926 0000 -BIB 3 3 +ENDSUBENT 29 +SUBENT 41157005 20240916 20250110 20250110 4220 +BIB 7 15 REACTION (98-CF-249(N,F)ELEM/MASS,CUM,FY) FACILITY (REAC,4RUSMIF) -INC-SPECT THERMAL NEUTRON SPECTRUM OF THE REACTOR -ENDBIB 3 +INC-SPECT Thermal neutron spectrum of the reactor +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.0077+-0.0006) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0129 1/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of + R.W.Waldo+. +REL-REF (R,12926001,R.W.Waldo+,J,PR/C,23,1113,1981) + Decay constant and yield used for normalization. + (N,12926030,R.W.Waldo+,J,PR/C,23,1113,1981) + Exp.data used for comparison: 0.30+-0.03 +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 4. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 15 COMMON 1 3 EN-DUMMY EV 2.53E-02 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 0.28 0.10 35. 88. 0.13 0.05 @@ -122,20 +207,30 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 0.121 0.047 53. 139. 0.038 0.018 ENDDATA 10 -ENDSUBENT 22 -SUBENT 41157006 19940914 20050926 0000 -BIB 3 3 +ENDSUBENT 34 +SUBENT 41157006 20240916 20250110 20250110 4220 +BIB 7 13 REACTION (92-U-233(N,F)ELEM/MASS,CUM,FY) FACILITY (REAC,4RUSFEI) -INC-SPECT FAST NEUTRON SPECTRUM OF THE REACTOR -ENDBIB 3 +INC-SPECT Fast neutron spectrum of the reactor +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.071+-0.005) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0128/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of + R.W.Waldo+. +REL-REF (R,,G.Benedetti+,J,NSE,80,379,1982) + Decay constant and yield used for normalization. +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 5. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 13 COMMON 1 3 EN-DUMMY EV 1.00E+06 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 2.60 0.32 35. 88. 1.85 0.25 @@ -146,20 +241,30 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 0.77 0.17 53. 139. 0.49 0.16 ENDDATA 10 -ENDSUBENT 22 -SUBENT 41157007 19940914 20050926 0000 -BIB 3 3 +ENDSUBENT 32 +SUBENT 41157007 20240916 20250110 20250110 4220 +BIB 7 13 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) FACILITY (REAC,4RUSFEI) -INC-SPECT FAST NEUTRON SPECTRUM OF THE REACTOR -ENDBIB 3 +INC-SPECT Fast neutron spectrum of the reactor +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.063+-0.007) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0127 1/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of + R.W.Waldo+. +REL-REF (R,,V.M.Sluchevska+,J,YK,,(3/38),29,1980) + Decay constant and yield used for normalization. +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 5. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 13 COMMON 1 3 EN-DUMMY EV 1.00E+06 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 2.34 0.44 35. 88. 2.09 0.48 @@ -170,20 +275,27 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 1.70 0.62 53. 139. 0.74 0.32 ENDDATA 10 -ENDSUBENT 22 -SUBENT 41157008 19940914 20050926 0000 -BIB 3 3 +ENDSUBENT 32 +SUBENT 41157008 20240916 20250110 20250110 4220 +BIB 6 10 REACTION (92-U-236(N,F)ELEM/MASS,CUM,FY) FACILITY (REAC,4RUSFEI) -INC-SPECT FAST NEUTRON SPECTRUM OF THE REACTOR -ENDBIB 3 +INC-SPECT Fast neutron spectrum of the reactor +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.060+-0.010) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0124 1/sec) and the decay constant for + 87Br(0.01247 1/sec) +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 5. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 10 COMMON 1 3 EN-DUMMY EV 1.00E+06 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 2.34 0.67 35. 88. 2.10 0.50 @@ -194,20 +306,30 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 1.44 0.53 53. 139. 0.22 0.13 ENDDATA 10 -ENDSUBENT 22 -SUBENT 41157009 19940914 20050926 0000 -BIB 3 3 +ENDSUBENT 29 +SUBENT 41157009 20240916 20250110 20250110 4220 +BIB 7 13 REACTION (93-NP-237(N,F)ELEM/MASS,CUM,FY) FACILITY (REAC,4RUSFEI) -INC-SPECT FAST NEUTRON SPECTRUM OF THE REACTOR -ENDBIB 3 +INC-SPECT Fast neutron spectrum of the reactor +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.0490+-0.0031) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0127 1/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of + R.W.Waldo+. +REL-REF (R,,G.Benedetti+,J,NSE,80,379,1982) + Decay constant and yield used for normalization. +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 6. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 13 COMMON 1 3 EN-DUMMY EV 1.00E+06 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 1.82 0.26 35. 88. 1.74 0.33 @@ -218,20 +340,32 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 0.99 0.24 53. 139. 0.53 0.18 ENDDATA 10 -ENDSUBENT 22 -SUBENT 41157010 19940914 20050926 0000 -BIB 3 3 +ENDSUBENT 32 +SUBENT 41157010 20240916 20250110 20250110 4220 +BIB 7 15 REACTION (94-PU-240(N,F)ELEM/MASS,CUM,FY) FACILITY (REAC,4RUSFEI) -INC-SPECT FAST NEUTRON SPECTRUM OF THE REACTOR -ENDBIB 3 +INC-SPECT Fast neutron spectrum of the reactor +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.0265+-0.0025) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0128 1/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of + R.W.Waldo+. +REL-REF (R,,G.Benedetti+,J,NSE,80,379,1982) + Decay constant and yield used for normalization. + (N,12926024,R.W.Waldo+,J,PR/C,23,1113,1981) + Exp.data used for comparison: 0.92+-0.13 +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 6. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 15 COMMON 1 3 EN-DUMMY EV 1.00E+06 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 0.97 0.19 35. 88. 0.93 0.22 @@ -242,20 +376,30 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 0.56 0.19 53. 139. 0.33 0.12 ENDDATA 10 -ENDSUBENT 22 -SUBENT 41157011 19940914 20050926 0000 -BIB 3 3 +ENDSUBENT 34 +SUBENT 41157011 20240916 20250110 20250110 4220 +BIB 7 13 REACTION (94-PU-241(N,F)ELEM/MASS,CUM,FY) FACILITY (REAC,4RUSFEI) -INC-SPECT FAST NEUTRON SPECTRUM OF THE REACTOR -ENDBIB 3 +INC-SPECT Fast neutron spectrum of the reactor +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.0276+-0.0012) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0128 1/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of + R.W.Waldo+. +REL-REF (R,,G.Benedetti+,J,NSE,80,379,1982) + Decay constant and yield used for normalization. +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 6. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 13 COMMON 1 3 EN-DUMMY EV 1.00E+06 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 1.01 0.20 35. 88. 1.13 0.20 @@ -266,20 +410,30 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 1.58 0.46 53. 139. 0.72 0.24 ENDDATA 10 -ENDSUBENT 22 -SUBENT 41157012 19940914 20050926 0000 -BIB 3 3 +ENDSUBENT 32 +SUBENT 41157012 20240916 20250110 20250110 4220 +BIB 7 13 REACTION (95-AM-241(N,F)ELEM/MASS,CUM,FY) FACILITY (REAC,4RUSFEI) -INC-SPECT FAST NEUTRON SPECTRUM OF THE REACTOR -ENDBIB 3 +INC-SPECT Fast neutron spectrum of the reactor +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.0192+-0.0021) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0122 1/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of + R.W.Waldo+. +REL-REF (R,,,J,NSE,80,379,1982) + Decay constant and yield used for normalization. +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 6. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 13 COMMON 1 3 EN-DUMMY EV 1.00E+06 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 0.77 0.13 35. 88. 0.78 0.17 @@ -290,19 +444,29 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 0.74 0.29 53. 139. 0.20 0.07 ENDDATA 10 -ENDSUBENT 22 -SUBENT 41157013 19940914 20050926 0000 -BIB 2 2 +ENDSUBENT 32 +SUBENT 41157013 20240916 20250110 20250110 4220 +BIB 6 12 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY) FACILITY (VDG,4RUSLIN) -ENDBIB 2 +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.049+-0.004) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0127 1/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of + R.W.Waldo+. +REL-REF (R,,L.Tomlinson,R,AERE-R-6993,1972) + Decay constant and yield used for normalization. +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 7. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 12 COMMON 1 3 EN EV 1.47E+07 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 1.82 0.22 35. 88. 1.41 0.28 @@ -313,19 +477,27 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 1.18 0.33 53. 139. 0.22 0.12 ENDDATA 10 -ENDSUBENT 21 -SUBENT 41157014 19940914 20050926 0000 -BIB 2 2 +ENDSUBENT 31 +SUBENT 41157014 20240916 20250110 20250110 4220 +BIB 5 10 REACTION (92-U-236(N,F)ELEM/MASS,CUM,FY) FACILITY (VDG,4RUSLIN) -ENDBIB 2 +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.033+-0.006) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0124 1/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of + R.W.Waldo+. +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 7. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 10 COMMON 1 3 EN EV 1.47E+07 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 1.29 0.29 35. 88. 1.57 0.40 @@ -336,19 +508,34 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 1.10 0.35 53. 139. 0.47 0.17 ENDDATA 10 -ENDSUBENT 21 -SUBENT 41157015 19940914 20050926 0000 -BIB 2 2 +ENDSUBENT 29 +SUBENT 41157015 20240916 20250110 20250110 4220 +BIB 6 17 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) FACILITY (VDG,4RUSLIN) -ENDBIB 2 +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.049+-0.005) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0123 1/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of + R.W.Waldo+. +REL-REF (N,,W.Grimm,T,GRIM,1973) University of Mainz. + Exp. data used for comparison: + Br-87 - 1.38+-0.16 + I-137 - 3.15+-0.41 + Br-88 - 1.33+-0.27 + I-138 - 0.55+-0.06 + Br-89 - 1.38+-0.16 +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 7. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 17 COMMON 1 3 EN EV 1.47E+07 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 1.94 0.31 35. 88. 1.90 0.37 @@ -359,19 +546,27 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 1.94 0.33 53. 139. 0.37 0.19 ENDDATA 10 -ENDSUBENT 21 -SUBENT 41157016 19940914 20050926 0000 -BIB 2 2 +ENDSUBENT 36 +SUBENT 41157016 20240916 20250110 20250110 4220 +BIB 5 10 REACTION (93-NP-237(N,F)ELEM/MASS,CUM,FY) FACILITY (VDG,4RUSLIN) -ENDBIB 2 +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.030+-0.004) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0127 1/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of + R.W.Waldo+. +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 7. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 10 COMMON 1 3 EN EV 1.47E+07 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 1.11 0.18 35. 88. 0.80 0.15 @@ -382,19 +577,29 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 0.44 0.10 53. 139. 0.16 0.06 ENDDATA 10 -ENDSUBENT 21 -SUBENT 41157017 19940914 20050926 0000 -BIB 2 2 +ENDSUBENT 29 +SUBENT 41157017 20240916 20250110 20250110 4220 +BIB 6 12 REACTION (94-PU-242(N,F)ELEM/MASS,CUM,FY) FACILITY (VDG,4RUSLIN) -ENDBIB 2 +ANALYSIS Data were normalized to the yield of the first delayed + neutron group (Y1=0.027+-0.004) taking acount of the + difference between decay constant of first group + (LAMBDA1=0.0126 1/sec) and the decay constant for + 87Br(0.01247 1/sec) as described in REL-REF of + R.W.Waldo+. +REL-REF (R,,L.Tomlinson,R,AERE-R-6993,1972) + Decay constant and yield used for normalization. +STATUS (TABLE,,A.N.Gudkov+,J,RCA,57,69,1992) Table 7. +HISTORY (20240916A) ERR-T -> DATA-ERR +ENDBIB 12 COMMON 1 3 EN EV 1.47E+07 ENDCOMMON 3 DATA 4 8 -ELEMENT MASS DATA ERR-T +ELEMENT MASS DATA DATA-ERR NO-DIM NO-DIM PC/FIS PC/FIS 35. 87. 1.04 0.20 35. 88. 1.00 0.23 @@ -405,5 +610,5 @@ NO-DIM NO-DIM PC/FIS PC/FIS 53. 138. 0.82 0.27 53. 139. 0.25 0.12 ENDDATA 10 -ENDSUBENT 21 +ENDSUBENT 31 ENDENTRY 17 diff --git a/exforall/411/41159.x4 b/exforall/411/41159.x4 index faaef5f48..4edd05b73 100644 --- a/exforall/411/41159.x4 +++ b/exforall/411/41159.x4 @@ -1,19 +1,19 @@ -ENTRY 41159 20051111 20060215 20060215 4136 -SUBENT 41159001 20051111 20060215 20060215 4136 -BIB 14 30 -TITLE THERMAL NEUTRON CAPTURE STUDIES ON BA-135 -AUTHOR (V.A.BONDARENKO,I.L.KUVAGA,P.T.PROKOFJEV,V.A.KHITROV, - YU.V.KHOLNOV,LE-HONG-KHIEM,YU.P.POPOV,A.M.SUKHOVOY, - S.BRANT,V.PAAR,V.LOPAC) +ENTRY 41159 20240916 20250110 20250110 4220 +SUBENT 41159001 20240916 20250110 20250110 4220 +BIB 14 32 +TITLE Thermal-neutron-capture studies on 135Ba +AUTHOR (V.A.Bondarenko,I.L.Kuvaga,P.T.Prokofjev,V.A.Khitrov, + Yu.V.Kholnov,Le Hong Khiem,Yu.P.Popov,A.M.Sukhovoj, + S.Brant,V.Paar,V.Lopac) INSTITUTE (4LATIFL) Bondarenko, Kuvaga, Prokofjev - (4ZZZDUB) Khitrov, Kholnov, Le-Hong-Khiem, Popov, - Sukhovoy + (4ZZZDUB) Khitrov, Kholnov, Le Hong Khiem, Popov, + Sukhovoj (3CROZAG) Brant, Paar, Lopac REFERENCE (J,NP/A,551,54,1993) -FACILITY (REAC,4LATIFL) 5 MW Reactor. +FACILITY (REAC,4LATIFL) 5 MW reactor. Scattering by graphite in tangential through-channel, Pb and Fe collimators, 510 mm Si-monocrystal as filter - ,borated polyethylene. + , and borated polyethylene. METHOD (COINC) Coincidence counting rate 40 counts/sec. (GSPEC) INC-SPECT Thermal neutrons of the reactor @@ -25,66 +25,73 @@ DETECTOR (HPGE) Two HPGe detectors,10% and 12 % efficiency, PART-DET (G) SAMPLE Ba-C-O3, weight 4.2 g, Ba-134 content is 85.5 %, Ba-135 content is 6 %, Ba-136,137 content is 1.4 %, - Ba-138 content is 5.7 %, Ba-130,132 is 0.1 % - Sample was enclose in polyethylene foil. + Ba-138 content is 5.7 %, Ba-130,132 content is 0.1 %. + Sample was enclosed in polyethylene foil. ERR-ANALYS (DATA-ERR) Errors are not specified STATUS Data are taken from the reference -HISTORY (19940929C) + + COMPILED AT THE CENTRE - CJD + + +HISTORY (19940929C) + + Compiled at the centre - CJD + + (20051111A) M.M. Entry was corrected. Dates corrected. -ENDBIB 30 + (20240916U) Upper -> lower case correction. + STATUS information was updated. +ENDBIB 32 COMMON 1 3 EN-DUMMY EV 2.53E-02 ENDCOMMON 3 -ENDSUBENT 37 -SUBENT 41159002 20051111 20060215 20060215 4136 -BIB 6 6 +ENDSUBENT 39 +SUBENT 41159002 20240916 20250110 20250110 4220 +BIB 8 9 REACTION (56-BA-134(N,G)56-BA-135,,SIG) Total capture c-s MONITOR ((MONIT)13-AL-27(N,G)13-AL-28,,SIG) -MONIT-REF (,S.F.MUGHABGHAB+,B,NEUT.CS 1A,,1981) +MONIT-REF (,S.F.Mughabghab+,B,NEUT.CS 1A,,,1981) +DECAY-MON (14-SI-28,,DG,1779.) After 100% beta decay of 28Al. SAMPLE Mixed target of barium oxide and pure aluminium metal. CORRECTION Correction on internal conversion. +STATUS (TABLE,,V.A.Bondarenko+,J,NP/A,551,54,1993) + Text on page 57. HISTORY (20051111U) SAMPLE and CORRECTION lines were added. -ENDBIB 6 +ENDBIB 9 NOCOMMON 0 0 DATA 4 1 DATA DATA-ERR MONIT MONIT-ERR B B B B 1.4 0.4 0.230 0.003 ENDDATA 3 -ENDSUBENT 14 -SUBENT 41159003 20051111 20060215 20060215 4136 -BIB 5 5 +ENDSUBENT 17 +SUBENT 41159003 20240916 20250110 20250110 4220 +BIB 6 9 REACTION (56-BA-134(N,G)56-BA-135-M,,SIG) MONITOR ((MONIT)13-AL-27(N,G)13-AL-28,,SIG) -MONIT-REF (,S.F.MUGHABGHAB+,B,NEUT.CS 1A,,1981) +MONIT-REF (,S.F.Mughabghab+,B,NEUT.CS 1A,,,1981) LEVEL-PROP (56-BA-135-M,E-LVL=0.268,SPIN=5.5,PARITY=-1.) + Conversion coefficient 5.39 was taken into account. + Decay constant 0.0242 1/hr. +STATUS (TABLE,,V.A.Bondarenko+,J,NP/A,551,54,1993) + Text on page 59. HISTORY (20051111A)(M.M.)LEVEL-PROP,MONIT-REF WERE added. -ENDBIB 5 +ENDBIB 9 NOCOMMON 0 0 DATA 4 1 DATA DATA-ERR MONIT MONIT-ERR B B B B 0.11 0.02 0.230 0.003 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41159004 20051111 20060215 20060215 4136 -BIB 7 13 +ENDSUBENT 17 +SUBENT 41159004 20240916 20250110 20250110 4220 +BIB 6 11 REACTION (56-BA-134(N,G)56-BA-135,,SPC,,MXW) Units in article are gammas per thousand of captured neutrons. Recalculated by compiler. MONITOR No information -EN-SEC (LVL-INI,56-BA-135) Initial level energy - (E,G) FLAG (1.) Observed in concidence. (2.) LVL-INI is tentative ERR-ANALYS (E-ERR) error in gamma energy -STATUS From Table 1 of Referernce. +STATUS (TABLE,,V.A.Bondarenko+,J,NP/A,551,54,1993) Table 1 HISTORY (20051111A) STATUS was added.DATA units were corrected. DATA and DATA-ERR were multiplied by 1.E-3. LVL-INI was added. FLAG values were corrected. -ENDBIB 13 +ENDBIB 11 NOCOMMON 0 0 DATA 6 171 E E-ERR DATA DATA-ERR FLAG LVL-INI @@ -261,5 +268,5 @@ KEV KEV PRT/INC PRT/INC NO-DIM KEV 6383.8 0.5 4.2 E-3 0.7 E-3 6972. 6971.98 0.41 9.3 E-3 0.7 E-3 6972. ENDDATA 173 -ENDSUBENT 191 +ENDSUBENT 189 ENDENTRY 4 diff --git a/exforall/411/41181.x4 b/exforall/411/41181.x4 index 84a27df60..ff4ef28ac 100644 --- a/exforall/411/41181.x4 +++ b/exforall/411/41181.x4 @@ -1,25 +1,26 @@ -ENTRY 41181 19960416 20050616 20050926 0000 -SUBENT 41181001 19960416 20050616 20050926 0000 -BIB 6 10 -TITLE ABSOLUTE MEASURMENT OF NEUTRON INDUCED FISSION - CROSS-SECTIONS OF U-235, U-238, NP-237 AND PU-239 -AUTHOR (K.MERLA,P.HAUSCH,C.M.HERBACH,G.MUSIOL,G.PAUSCH, - U.TODT,L.V.DRAPCHINSKIY,V.A.KALININ,V.I.SHPAKOV) -INSTITUTE (4RUSRI ) DRAPCHINSKIY, KALININ, SHPAKOV - (2GERDRE) MERLA, HAUSCH, HERBACH, MUSIOL, PAUSCH, TODT -REFERENCE (C,91JUELIC,,510,9105) DATA TABLE IS GIVEN -STATUS DATA ARE TAKEN FROM THE REFERENCE -HISTORY (951226C) + + COMPILED AT THE CENTRE - CJD + + - (960416D) ENTRY DELETED AS NOT BELONGING TO 4-AREA -ENDBIB 10 +ENTRY 41181 20240916 20250110 20250110 4220 +SUBENT 41181001 20240916 20250110 20250110 4220 +BIB 5 11 +TITLE Absolute measurment of neutron induced fission + cross-sections of U-235, U-238, Np-237 and Pu-239 +AUTHOR (K.Merla,P.Hausch,C.M.Herbach,G.Musiol,G.Pausch, + U.Todt,L.V.Drapchinskiy,V.A.Kalinin,V.I.Shpakov) +INSTITUTE (4RUSRI ) Drapchinskiy, Kalinin, Shpakov + (2GERDRE) Merla, Hausch, Herbach, Musiol, Pausch, Todt +REFERENCE (C,91JUELIC,,510,1991) Data table is given +HISTORY (19951226C) + + Compiled at the centre - CJD + + + (19960416D) ENTRY deleted as not belonging to 4-area + (20240916U) Upper -> lower case correction. + Dates were corrected for 4-digits year. +ENDBIB 11 NOCOMMON 0 0 -ENDSUBENT 13 -NOSUBENT 41181002 19960416 20050616 20050926 0000 -NOSUBENT 41181003 19960416 20050616 20050926 0000 -NOSUBENT 41181004 19960416 20050616 20050926 0000 -NOSUBENT 41181005 19960416 20050616 20050926 0000 -NOSUBENT 41181006 19960416 20050616 20050926 0000 -NOSUBENT 41181007 19960416 20050616 20050926 0000 -NOSUBENT 41181008 19960416 20050616 20050926 0000 -NOSUBENT 41181009 19960416 20050616 20050926 0000 +ENDSUBENT 14 +SUBENT 41181002 20240916 20250110 20250110 4220 +SUBENT 41181003 20240916 20250110 20250110 4220 +SUBENT 41181004 20240916 20250110 20250110 4220 +SUBENT 41181005 20240916 20250110 20250110 4220 +SUBENT 41181006 20240916 20250110 20250110 4220 +SUBENT 41181007 20240916 20250110 20250110 4220 +SUBENT 41181008 20240916 20250110 20250110 4220 +SUBENT 41181009 20240916 20250110 20250110 4220 ENDENTRY 9 diff --git a/exforall/411/41193.x4 b/exforall/411/41193.x4 index 5a213aae5..efefaeb1c 100644 --- a/exforall/411/41193.x4 +++ b/exforall/411/41193.x4 @@ -1,52 +1,68 @@ -ENTRY 41193 20010311 20011019 20050926 0000 -SUBENT 41193001 20010311 20011019 20050926 0000 -BIB 11 18 -INSTITUTE (4ZZZDUB,4UKRIJI) -REFERENCE (R,JINR-P3-91-244,199106) -AUTHOR (YU.ANDRZEJEVSKI,YU.M.GLEDENOV,G.V.ZAMYSLOV, - A.I.KISLITSKIY,G.B.LYUBANSKIY,V.A.PSHENICHNYY, - V.I.SALACKIY,N.P.FEDOSEEV) -TITLE AR-36(N,ALPHA) AND V-50(N,P) CROSS-SECTION - MEASUREMENT FOR THERMAL NEUTRON ENERGIES -FACILITY (REAC,4UKRIJI) REACTOR WWR-M -INC-SPECT THERMAL NEUTRONS AFTER MONOCRYSTALLINE SILICIUM - FILTER -DETECTOR (IOCH) TWO-GRID IONIZATION CHAMBER +ENTRY 41193 20240916 20250110 20250110 4220 +SUBENT 41193001 20240916 20250110 20250110 4220 +BIB 10 23 +TITLE Measurement of the cross sections of the + 36Ar(n,alpha)33S and 50V(n,p)50Ti reactions induced by + thermal neutrons +AUTHOR (Ju.Andrzejevski,Yu.M.Gledenov,G.V.Zamyslov, + A.I.Kislitskiy,G.B.Lyubanskiy,V.A.Pshenichnyy, + V.I.Salatskiy,N.P.Fedoseev) +REFERENCE (R,JINR-P3-91-244,1991) +INSTITUTE (4ZZZDUB,4UKRIJD) +FACILITY (REAC,4UKRIJD) Reactor WWR-M +INC-SPECT Thermal neutrons after monocrystalline silicon + filter. 1.3E+7 n/cm2*sec at sample position. +DETECTOR (IOCH) Two-grid ionization chamber MONITOR (79-AU-197(N,G)79-AU-198,,SIG) -ERR-ANALYS (DATA-ERR) ERRORS ARE NOT SPECIFIED -STATUS DATA ARE TAKEN FROM THE REFERENCE -HISTORY (19960628C) + + COMPILED AT THE CENTRE - CJD + + - (19970115U) + + CORRECTED - 'MXW' ADDED TO REACTION + For neutron beam parameters measurement. +ERR-ANALYS (DATA-ERR) Errors are not specified +HISTORY (19960628C) + + Compiled at the centre - CJD + + + (19970115U) + + Corrected - 'MXW' added to REACTION SF8 - (20010311A) DATE is corrected -ENDBIB 18 + (20010311A) Date is corrected + (20240916U) Upper -> lower case correction. + STATUS information was updated. + Title and 1st author name were corrected as given in + an abstract on last page of the article. +ENDBIB 23 NOCOMMON 0 0 -ENDSUBENT 21 -SUBENT 41193002 20010311 20011019 20050926 0000 -BIB 3 3 +ENDSUBENT 26 +SUBENT 41193002 20240916 20250110 20250110 4220 +BIB 5 7 REACTION (18-AR-36(N,A)16-S-33,,SIG,,MXW) -SAMPLE NATURAL ARGON MIXTURE, AR-36 CONTENT IS 0.337 % -HISTORY (19970115U) 'MXW' ADDED TO REACTION SF8 -ENDBIB 3 +SAMPLE Natural argon mixture, Ar-36 content is 0.337 % +REL-REF (D,V1991112,S.F.Mughabghab+,B,NEUT.CS 1A,,18-1,1981) + 5.5+-0.1 mb +STATUS (TABLE,,Ju.Andrzejevski+,R,JINR-P3-91-244,1991) + Text on page 6 +HISTORY (19970115U) 'MXW' added to REACTION SF8 +ENDBIB 7 NOCOMMON 0 0 DATA 3 1 EN-MEAN DATA DATA-ERR -EV B B - 2.5E-02 6.3E-03 6.E-04 +EV MB MB + 2.5E-02 6.3 0.6 ENDDATA 3 -ENDSUBENT 11 -SUBENT 41193003 20010311 20011019 20050926 0000 -BIB 3 4 +ENDSUBENT 15 +SUBENT 41193003 20240916 20250110 20250110 4220 +BIB 6 11 REACTION (23-V-50(N,P)22-TI-50,,SIG,,MXW) -SAMPLE VANADIUM OXIDE ENRICHED IN V-50 ISITOPE - V-50 CONTENT IS 17 PC, THICKNESS 0.18 MILLIGRAM/CM2 -HISTORY (19970115U) 'MXW' ADDED TO REACTION SF8 -ENDBIB 4 +SAMPLE Vanadium oxide enriched in V-50 isitope. + V-50 content is 17 %, thickness 0.18 milligram/cm2. + 70 x 80 mm square. +CORRECTION Contribution of epi-thermal neutrons was measured by + B-10 filter of 1.9E+21 nucl/cm2 thickness. +REL-REF (D,21820002,P.D'hondt+,C,82ANTWER,,147,1982) + 400+-20 microb. +STATUS (TABLE,,Ju.Andrzejevski+,R,JINR-P3-91-244,1991) + Text on page 6 +HISTORY (19970115U) 'MXW' added to REACTION SF8 +ENDBIB 11 NOCOMMON 0 0 DATA 3 1 EN-MEAN DATA DATA-ERR -EV B B - 2.5E-2 2.77E-04 4.2E-05 +EV MB MB + 2.5E-2 0.277 0.042 ENDDATA 3 -ENDSUBENT 12 +ENDSUBENT 19 ENDENTRY 3 diff --git a/exforall/411/41199.x4 b/exforall/411/41199.x4 index 9981f05b4..d2132fefe 100644 --- a/exforall/411/41199.x4 +++ b/exforall/411/41199.x4 @@ -1,206 +1,210 @@ -ENTRY 41199 19970115 20050926 0000 -SUBENT 41199001 19970115 20050926 0000 -BIB 11 19 -TITLE THE PRECISE MEASUREMENTS OF INTEGRAL (OVER SPECTRUM - OF CF-252) TOTAL NEUTRON CROSS-SECTION AND TRANS- - MISSION COEFFICIENTS FOR TESTING OF DIFFERENTIAL - TOTAL CROSS-SECTION -AUTHOR (B.YA.GUZHOVSKIY,A.N.GREBENNIKOV,V.P.GORELOV, - G.G.FARAFONOV,V.S.RUDNEV) +ENTRY 41199 20240916 20250110 20250110 4220 +SUBENT 41199001 20240916 20250110 20250110 4220 +BIB 14 34 +TITLE The precise measurements of integral (over spectrum + of Cf-252) total neutron cross-sections and + transmission coefficients for the testing of + differential total cross-section +AUTHOR (B.Ya.Guzhovskii,A.N.Grebennikov,V.P.Gorelov, + G.G.Farafontov,V.S.Rudnev) INSTITUTE (4RUSEPA) -REFERENCE (C,94GATLIN,,254,9405) DATA ARE GIVEN -INC-SPECT CF-252 SPONTANEOUS FISSION NEUTRON SPECTRUM -INC-SOURCE (CF252) -DETECTOR (LONGC) -MONITOR ABSOLUTE MEASUREMENTS -METHOD TRANSMISSION -STATUS DATA ARE TAKEN FROM THE MAIN REFERENCE -HISTORY (960724C) + + COMPILED AT THE CENTRE - CJD + + - (961030A) * * SUBENTS 41199013-41199023 DELETED - AS NOT RELEVANT TO THE DATA GIVEN IN THE REFERENCE * * - + + ENTRY CORRECTED IN THE CJD-CENTRE + + - (970115U) * * CORRECTED - REACTION SF8 ADDED -ENDBIB 19 +REFERENCE (C,94GATLIN,,254,1994) Data are given +INC-SPECT Cf-252 spontaneous fission neutron spectrum +INC-SOURCE (CF252) 4.E+8 n/sec +SAMPLE Natural samples of diameter 20-40 mm, thickness + 5-10 mm (+-10mkm) +DETECTOR (LONGC) Measurement of direct flux, of background and + with sample. +MONITOR Absolute measurements +METHOD (TRN) +ADD-RES (COMP) Calculated integral total cross-sections for + evaluated data libraries ENDL-82, BROND-2, JENDL-3, + ENDF/B-VI in Table 2. +ERR-ANALYS (ERR-1,,0.1) Neutron flux statistical uncertainty. + (ERR-S) Statistical at the level 0.95 +MISC-COL (MISC) 2-sigma uncertainty as given in Table 1. +HISTORY (19960724C) + + Compiled at the centre - CJD + + + (19961030A) * * SUBENTS 41199013-41199023 deleted + as not relevant to the data given in the reference * * + + + ENTRY corrected in the CJD-centre + + + (19970115U) * * Corrected - REACTION SF8 added + (20240916A) BIB information was updated. + ERR-S values were re-calulated (2-sigma -> 1-sigma). + Upper -> lower case correction. + Dates were corrected for 4-digits year. + STATUS information was updated. + EN-MEAN=1.0E+06 eV -> KT-DUMMY=1.42 MeV according to + a comment from NDS,IAEA. +ENDBIB 34 COMMON 1 3 -EN-MEAN -EV - 1.0E+06 +KT-DUMMY +MEV + 1.42 ENDCOMMON 3 -ENDSUBENT 26 -SUBENT 41199002 19970115 20050926 0000 -BIB 4 5 +ENDSUBENT 41 +SUBENT 41199002 20240916 20250110 20250110 4220 +BIB 4 4 REACTION (4-BE-9(N,TOT),,SIG,,FIS) -SAMPLE DIAMETER 20-40 MM, THICKNESS 5-10 MM, DENSITY - 1.858 GRAM/CM3 -ERR-ANALYS (ERR-S) STATISTICAL AT THE LEVEL 0.95 -HISTORY (970115U) 'FIS' ADDED TO REACTION SF8 -ENDBIB 5 +SAMPLE Density 1.858 +- 0.002 gram/cm3 +STATUS (TABLE,,B.Ya.Guzhovskii+,C,94GATLIN,,254,1994) Table 1 +HISTORY (19970115U) 'FIS' added to REACTION SF8 +ENDBIB 4 NOCOMMON 0 0 -DATA 2 1 -DATA ERR-S -B B - 2.802 0.005 +DATA 3 1 +DATA ERR-S MISC +B B B + 2.802 0.0025 0.005 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41199003 19970115 20050926 0000 -BIB 4 5 +ENDSUBENT 12 +SUBENT 41199003 20240916 20250110 20250110 4220 +BIB 4 4 REACTION (6-C-12(N,TOT),,SIG,,FIS) -SAMPLE DIAMETER 20-40 MM, THICKNESS 5-10 MM, DENSITY - 1.717 GRAM/CM3 -ERR-ANALYS (ERR-S) STATISTICAL AT THE LEVEL 0.95 -HISTORY (970115U) 'FIS' ADDED TO REACTION SF8 -ENDBIB 5 +SAMPLE Density 1.717 +- 0.002 gram/cm3 +STATUS (TABLE,,B.Ya.Guzhovskii+,C,94GATLIN,,254,1994) Table 1 +HISTORY (19970115U) 'FIS' added to REACTION SF8 +ENDBIB 4 NOCOMMON 0 0 -DATA 2 1 -DATA ERR-S -B B - 2.350 0.003 +DATA 3 1 +DATA ERR-S MISC +B B B + 2.350 0.0015 0.003 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41199004 19970115 20050926 0000 -BIB 4 5 +ENDSUBENT 12 +SUBENT 41199004 20240916 20250110 20250110 4220 +BIB 4 4 REACTION (13-AL-27(N,TOT),,SIG,,FIS) -SAMPLE DIAMETER 20-40 MM, THICKNESS 5-10 MM, DENSITY - 2.697 GRAM/CM3 -ERR-ANALYS (ERR-S) STATISTICAL AT THE LEVEL 0.95 -HISTORY (970115U) 'FIS' ADDED TO REACTION SF8 -ENDBIB 5 +SAMPLE Density 2.697 +- 0.002 gram/cm3 +STATUS (TABLE,,B.Ya.Guzhovskii+,C,94GATLIN,,254,1994) Table 1 +HISTORY (19970115U) 'FIS' added to REACTION SF8 +ENDBIB 4 NOCOMMON 0 0 -DATA 2 1 -DATA ERR-S -B B - 3.214 0.005 +DATA 3 1 +DATA ERR-S MISC +B B B + 3.214 0.0025 0.005 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41199005 19970115 20050926 0000 -BIB 4 5 +ENDSUBENT 12 +SUBENT 41199005 20240916 20250110 20250110 4220 +BIB 4 4 REACTION (26-FE-0(N,TOT),,SIG,,FIS) -SAMPLE DIAMETER 20-40 MM, THICKNESS 5-10 MM, DENSITY - 7.865 GRAM/CM3 -ERR-ANALYS (ERR-S) STATISTICAL AT THE LEVEL 0.95 -HISTORY (970115U) 'FIS' ADDED TO REACTION SF8 -ENDBIB 5 +SAMPLE Density 7.865 +- 0.002 gram/cm3 +STATUS (TABLE,,B.Ya.Guzhovskii+,C,94GATLIN,,254,1994) Table 1 +HISTORY (19970115U) 'FIS' added to REACTION SF8 +ENDBIB 4 NOCOMMON 0 0 -DATA 2 1 -DATA ERR-S -B B - 3.263 0.005 +DATA 3 1 +DATA ERR-S MISC +B B B + 3.263 0.0025 0.005 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41199006 19970115 20050926 0000 -BIB 4 5 +ENDSUBENT 12 +SUBENT 41199006 20240916 20250110 20250110 4220 +BIB 4 4 REACTION (28-NI-0(N,TOT),,SIG,,FIS) -SAMPLE DIAMETER 20-40 MM, THICKNESS 5-10 MM, DENSITY - 8.870 GRAM/CM3 -ERR-ANALYS (ERR-S) STATISTICAL AT THE LEVEL 0.95 -HISTORY (970115U) 'FIS' ADDED TO REACTION SF8 -ENDBIB 5 +SAMPLE Density 8.870 +- 0.002 gram/cm3 +STATUS (TABLE,,B.Ya.Guzhovskii+,C,94GATLIN,,254,1994) Table 1 +HISTORY (19970115U) 'FIS' added to REACTION SF8 +ENDBIB 4 NOCOMMON 0 0 -DATA 2 1 -DATA ERR-S -B B - 3.494 0.024 +DATA 3 1 +DATA ERR-S MISC +B B B + 3.494 0.012 0.024 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41199007 19970115 20050926 0000 -BIB 4 5 +ENDSUBENT 12 +SUBENT 41199007 20240916 20250110 20250110 4220 +BIB 4 4 REACTION (29-CU-0(N,TOT),,SIG,,FIS) -SAMPLE DIAMETER 20-40 MM, THICKNESS 5-10 MM, DENSITY - 8.923 GRAM/CM3 -ERR-ANALYS (ERR-S) STATISTICAL AT THE LEVEL 0.95 -HISTORY (970115U) 'FIS' ADDED TO REACTION SF8 -ENDBIB 5 +SAMPLE Density 8.923 +- 0.002 gram/cm3 +STATUS (TABLE,,B.Ya.Guzhovskii+,C,94GATLIN,,254,1994) Table 1 +HISTORY (19970115U) 'FIS' added to REACTION SF8 +ENDBIB 4 NOCOMMON 0 0 -DATA 2 1 -DATA ERR-S -B B - 3.541 0.018 +DATA 3 1 +DATA ERR-S MISC +B B B + 3.541 0.009 0.018 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41199008 19970115 20050926 0000 -BIB 4 5 +ENDSUBENT 12 +SUBENT 41199008 20240916 20250110 20250110 4220 +BIB 4 4 REACTION (41-NB-93(N,TOT),,SIG,,FIS) -SAMPLE DIAMETER 20-40 MM, THICKNESS 5-10 MM, DENSITY - 8.500 GRAM/CM3 -ERR-ANALYS (ERR-S) STATISTICAL AT THE LEVEL 0.95 -HISTORY (970115U) 'FIS' ADDED TO REACTION SF8 -ENDBIB 5 +SAMPLE Density 8.500 +- 0.002 gram/cm3 +STATUS (TABLE,,B.Ya.Guzhovskii+,C,94GATLIN,,254,1994) Table 1 +HISTORY (19970115U) 'FIS' added to REACTION SF8 +ENDBIB 4 NOCOMMON 0 0 -DATA 2 1 -DATA ERR-S -B B - 5.904 0.006 +DATA 3 1 +DATA ERR-S MISC +B B B + 5.904 0.003 0.006 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41199009 19970115 20050926 0000 -BIB 4 5 +ENDSUBENT 12 +SUBENT 41199009 20240916 20250110 20250110 4220 +BIB 4 4 REACTION (42-MO-0(N,TOT),,SIG,,FIS) -SAMPLE DIAMETER 20-40 MM, THICKNESS 5-10 MM, DENSITY - 10.208 GRAM/CM3 -ERR-ANALYS (ERR-S) STATISTICAL AT THE LEVEL 0.95 -HISTORY (970115U) 'FIS' ADDED TO REACTION SF8 -ENDBIB 5 +SAMPLE Density 10.208 +- 0.002 gram/cm3 +STATUS (TABLE,,B.Ya.Guzhovskii+,C,94GATLIN,,254,1994) Table 1 +HISTORY (19970115U) 'FIS' added to REACTION SF8 +ENDBIB 4 NOCOMMON 0 0 -DATA 2 1 -DATA ERR-S -B B - 5.800 0.025 +DATA 3 1 +DATA ERR-S MISC +B B B + 5.800 0.0124 0.025 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41199010 19970115 20050926 0000 -BIB 4 5 +ENDSUBENT 12 +SUBENT 41199010 20240916 20250110 20250110 4220 +BIB 4 4 REACTION (73-TA-181(N,TOT),,SIG,,FIS) -SAMPLE DIAMETER 20-40 MM, THICKNESS 5-10 MM, DENSITY - 16.600 GRAM/CM3 -ERR-ANALYS (ERR-S) STATISTICAL AT THE LEVEL 0.95 -HISTORY (970115U) 'FIS' ADDED TO REACTION SF8 -ENDBIB 5 +SAMPLE Density 16.600 +- 0.002 gram/cm3 +STATUS (TABLE,,B.Ya.Guzhovskii+,C,94GATLIN,,254,1994) Table 1 +HISTORY (19970115U) 'FIS' added to REACTION SF8 +ENDBIB 4 NOCOMMON 0 0 -DATA 2 1 -DATA ERR-S -B B - 6.979 0.007 +DATA 3 1 +DATA ERR-S MISC +B B B + 6.979 0.0035 0.007 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41199011 19970115 20050926 0000 -BIB 4 5 +ENDSUBENT 12 +SUBENT 41199011 20240916 20250110 20250110 4220 +BIB 4 4 REACTION (74-W-0(N,TOT),,SIG,,FIS) -SAMPLE DIAMETER 20-40 MM, THICKNESS 5-10 MM, DENSITY - 19.240 GRAM/CM3 -ERR-ANALYS (ERR-S) STATISTICAL AT THE LEVEL 0.95 -HISTORY (970115U) 'FIS' ADDED TO REACTION SF8 -ENDBIB 5 +SAMPLE Density 19.240 +- 0.002 gram/cm3 +STATUS (TABLE,,B.Ya.Guzhovskii+,C,94GATLIN,,254,1994) Table 1 +HISTORY (19970115U) 'FIS' added to REACTION SF8 +ENDBIB 4 NOCOMMON 0 0 -DATA 2 1 -DATA ERR-S -B B - 6.875 0.014 +DATA 3 1 +DATA ERR-S MISC +B B B + 6.875 0.007 0.014 ENDDATA 3 -ENDSUBENT 13 -SUBENT 41199012 19970115 20050926 0000 -BIB 4 5 +ENDSUBENT 12 +SUBENT 41199012 20240916 20250110 20250110 4220 +BIB 4 4 REACTION (92-U-238(N,TOT),,SIG,,FIS) -SAMPLE DIAMETER 20-40 MM, THICKNESS 5-10 MM, DENSITY - 18.838 GRAM/CM3 -ERR-ANALYS (ERR-S) STATISTICAL AT THE LEVEL 0.95 -HISTORY (970115U) 'FIS' ADDED TO REACTION SF8 -ENDBIB 5 +SAMPLE Density 18.838 +- 0.002 gram/cm3 +STATUS (TABLE,,B.Ya.Guzhovskii+,C,94GATLIN,,254,1994) Table 1 +HISTORY (19970115U) 'FIS' added to REACTION SF8 +ENDBIB 4 NOCOMMON 0 0 -DATA 2 1 -DATA ERR-S -B B - 7.754 0.004 +DATA 3 1 +DATA ERR-S MISC +B B B + 7.754 0.002 0.004 ENDDATA 3 -ENDSUBENT 13 -NOSUBENT 41199013 19961030 20050926 0000 -NOSUBENT 41199014 19961030 20050926 0000 -NOSUBENT 41199015 19961030 20050926 0000 -NOSUBENT 41199016 19961030 20050926 0000 -NOSUBENT 41199017 19961030 20050926 0000 -NOSUBENT 41199018 19961030 20050926 0000 -NOSUBENT 41199019 19961030 20050926 0000 -NOSUBENT 41199020 19961030 20050926 0000 -NOSUBENT 41199021 19961030 20050926 0000 -NOSUBENT 41199022 19961030 20050926 0000 -NOSUBENT 41199023 19961030 20050926 0000 +ENDSUBENT 12 +SUBENT 41199013 20240916 20250110 20250110 4220 +SUBENT 41199014 20240916 20250110 20250110 4220 +SUBENT 41199015 20240916 20250110 20250110 4220 +SUBENT 41199016 20240916 20250110 20250110 4220 +SUBENT 41199017 20240916 20250110 20250110 4220 +SUBENT 41199018 20240916 20250110 20250110 4220 +SUBENT 41199019 20240916 20250110 20250110 4220 +SUBENT 41199020 20240916 20250110 20250110 4220 +SUBENT 41199021 20240916 20250110 20250110 4220 +SUBENT 41199022 20240916 20250110 20250110 4220 +SUBENT 41199023 20240916 20250110 20250110 4220 ENDENTRY 23 diff --git a/exforall/417/41776.x4 b/exforall/417/41776.x4 new file mode 100644 index 000000000..9549608be --- /dev/null +++ b/exforall/417/41776.x4 @@ -0,0 +1,606 @@ +ENTRY 41776 20241126 20250110 20250110 4220 +SUBENT 41776001 20241126 20250110 20250110 4220 +BIB 14 60 +TITLE Measurement of the cross section for the + neutron-induced fission of 237Np in the energy range + of 0.3-500 MeV +AUTHOR (A.S.Vorobyev, A.M.Gagarski, O.A.Shcherbakov, + L.A.Vaishnene, A.M.Tyagelskaya,N.M.Olkhovich, + A.L.Barabanov) +REFERENCE (J,JEL,120,373,2024) Engl.translation + #doi:10.1134/S0021364024602987 + (J,ZEP,120,385,2024) Issue 6. +INSTITUTE (4RUSLIN) A.S.Vorobyev, A.M.Gagarski, O.A.Shcherbakov, + L.A.Vaishnene, A.M.Tyagelskaya,N.M.Olkhovich + (4RUSMIF) A.L.Barabanov + (4RUSKUR) Central for 4RUSLIN. +FACILITY (SYNCY,4RUSLIN) Neutron complex GNEIS on the basis of + 1 GeV proton synchrocyclotron SC-1000. +INC-SOURCE (SPALL) +METHOD (TOF) TOF base 36.50+-0.05 m. + Measurements were carried out for two orientations of + the setup relative to the incident neutron beam. + The orientation was changed by rotating the setup + 180 deg around an axis perpendicular to the direction + of neutron beam motion . +SAMPLE Np-237 and U-235 samples were produced by painting + technique on 0.1 mm thick Al foils at Khlopin Radium + Institute. + 237Np : + chemical form - oxide NpO(2), + circle of a 80 mm diameter, + thickness 318+-16 mug/cm2, + enrichment (99.999+-0.001)%, + 235U: + rectangular form 50 x 100 mm + enrichment (99.992+-0.001)% + thickness 203+-11 mug/cm2. + The uniformity of the active layers was ~10%. + Measured ratio N(Np237)/N(U235) of the number of nuclei + was 1.630+-0.022. +DETECTOR (MWPC) Two position-sensitive multi-wire proportional + counters (MWPC) of 140 x 140 mm2 size for FF detection. + Registration efficiency about 45 %. + (FISCH) 238U fission ionization chamber for relative + monitoring of neutron flux. + .Photomultiplier tube as start detector. + (SOLST) Semiconductor silicon detectors were used to + measure the number of isotope nuclei in samples by + alpha-activity. +DECAY-DATA (93-NP-237,2.44E+6YR) 2.144+-0.007 yr. +CORRECTION For the anisotropy of the angular distribution of + fission fragments and for the limited solid detection + angle. + Correction was 1% as average, reaches 4% at neutron + energy near 0.6 MeV. +REL-REF (R,41686002,A.S.Vorobyev+,J,JEL,110,242,2019) Np-237 + (R,41757003,A.S.Vorobyev+,J,PR/C,108,014621,2023) U-235 + Dependencies of the anisotropy of the fission fragments + angular distribution for Np-237 and U-235 + on the neutron energy; was used at correction. +STATUS (APRVD) Approved by the author A.Vorobyev +HISTORY (20241126R) Data were received from the authors + (20241126C) M.M. +ENDBIB 60 +NOCOMMON 0 0 +ENDSUBENT 63 +SUBENT 41776002 20241126 20250110 20250110 4220 +BIB 3 11 +REACTION ((93-NP-237(N,F),,SIG)/(92-U-235(N,F),,SIG)) +ERR-ANALYS (ERR-T) Total uncertainty includes: + (ERR-S) Statistical uncertainty + (ERR-1,,0.3) Neutron flux attenuation + (ERR-2) Anisotropy of fission fragments + (ERR-3,,0.01) Samples purity + (ERR-4) Detection efficiency + (ERR-5) Ratio N(Np237)/N(U235) of the numbers of nuclei + in samples +STATUS (TABLE) Data were received from the authors. + Data are on Figs.5-7 +ENDBIB 11 +COMMON 3 3 +ERR-2 ERR-4 ERR-5 +PER-CENT PER-CENT PER-CENT + 0.6 0.3 1.4 +ENDCOMMON 3 +DATA 4 255 +EN DATA ERR-S ERR-T +MEV NO-DIM PER-CENT PER-CENT +425.6 1.02398 1.808 2.402 +361.9 1.03324 1.488 2.171 +313.2 1.0282 1.309 2.052 +274.2 1.02314 1.209 1.99 +243. 1.05277 1.058 1.903 +217.3 1.05287 1.033 1.888 +195.9 1.0344 1.019 1.881 +177.7 1.02143 1.007 1.875 +162. 1.03311 1.011 1.877 +148.6 1.04004 1.012 1.877 +136.8 1.01604 1.014 1.879 +126.4 1.0249 1.02 1.882 +117.3 1.00175 1.025 1.885 +109.2 1.01905 1.035 1.89 +101.9 1.02145 1.049 1.898 +95.29 1.02174 1.063 1.906 +89.4 1.02112 1.074 1.911 +84.02 1.0406 1.088 1.919 +79.19 1.03008 1.104 1.929 +74.73 1.00823 1.116 1.935 +70.68 1.02582 1.132 1.944 +66.91 1.03933 1.153 1.957 +63.51 1.01973 1.165 1.964 +60.34 1.02821 1.186 1.976 +57.39 1.02197 1.197 1.983 +54.68 1.03557 1.211 1.992 +52.15 1.03695 1.229 2.003 +49.82 1.0327 1.252 2.017 +47.61 1.01387 1.256 2.019 +45.59 1.05309 1.288 2.039 +43.66 1.0317 1.3 2.047 +41.87 1.02601 1.31 2.054 +40.19 1.04443 1.326 2.063 +38.6 1.05204 1.347 2.077 +37.13 1.02516 1.36 2.086 +35.71 1.03074 1.367 2.09 +34.4 1.03422 1.394 2.108 +33.15 1.02164 1.407 2.117 +31.97 1.04918 1.428 2.131 +30.86 1.04243 1.448 2.144 +29.79 1.03494 0.922 1.831 +27.37 1.04924 0.95 1.845 +25.23 1.06803 0.977 1.859 +23.35 1.0672 1. 1.871 +21.66 1.07307 1.034 1.889 +20.16 1.10275 1.067 1.907 +18.8 1.11995 1.086 1.918 +17.59 1.09398 1.082 1.916 +16.48 1.05932 1.087 1.919 +15.48 1.06789 1.101 1.927 +14.57 1.07227 1.12 1.937 +13.73 1.0722 1.141 1.95 +12.96 1.14798 1.175 1.97 +12.27 1.17402 1.175 1.97 +11.62 1.204 1.166 1.965 +11.03 1.25414 1.164 1.963 +10.48 1.24941 1.138 1.948 +9.968 1.24187 1.115 1.935 +9.494 1.27008 1.1 1.926 +9.051 1.25719 1.079 1.914 +8.643 1.26337 1.057 1.902 +8.256 1.29281 1.055 1.901 +7.9 1.27788 1.048 1.897 +7.564 1.34339 1.061 1.904 +7.25 1.3536 1.068 1.908 +6.956 1.38942 1.087 1.919 +6.678 1.45237 1.13 1.943 +6.415 1.50021 1.183 1.974 +6.171 1.50796 1.234 2.006 +5.941 1.53907 1.298 2.046 +5.721 1.48713 1.323 2.061 +5.513 1.44185 1.32 2.06 +5.317 1.41306 1.303 2.049 +5.132 1.42237 1.303 2.049 +4.956 1.40686 1.289 2.04 +4.789 1.40294 1.276 2.032 +4.63 1.39634 1.261 2.023 +4.478 1.42788 1.252 2.017 +4.334 1.40816 1.253 2.018 +4.196 1.4179 1.236 2.007 +4.068 1.38382 1.225 2. +3.942 1.41464 1.215 1.994 +3.823 1.41002 1.21 1.991 +3.71 1.36593 1.195 1.982 +3.601 1.37925 1.192 1.98 +3.497 1.38796 1.167 1.965 +3.398 1.37691 1.16 1.961 +3.303 1.3664 1.176 1.97 +3.211 1.39414 1.157 1.959 +3.124 1.37568 1.147 1.953 +3.04 1.36872 1.124 1.94 +2.959 1.38091 1.141 1.95 +2.882 1.34148 1.103 1.928 +2.807 1.36684 1.106 1.929 +2.735 1.35303 1.105 1.929 +2.666 1.36307 1.114 1.934 +2.6 1.36891 1.1 1.926 +2.536 1.35868 1.1 1.926 +2.474 1.35545 1.065 1.906 +2.416 1.34468 1.069 1.909 +2.358 1.34993 1.07 1.909 +2.302 1.35238 1.1 1.926 +2.249 1.36644 1.071 1.91 +2.198 1.34026 1.084 1.917 +2.148 1.3235 1.064 1.906 +2.1 1.33769 1.075 1.912 +2.053 1.32676 1.1 1.926 +2.009 1.32794 1.066 1.907 +1.965 1.32343 1.079 1.914 +1.923 1.29987 1.085 1.918 +1.883 1.32724 1.06 1.904 +1.843 1.30107 1.038 1.891 +1.805 1.32865 1.079 1.914 +1.768 1.3423 1.136 1.947 +1.731 1.30148 1.175 1.97 +1.697 1.32741 1.154 1.958 +1.663 1.29941 1.143 1.951 +1.63 1.31831 1.117 1.936 +1.599 1.28783 1.137 1.947 +1.568 1.31554 1.146 1.953 +1.538 1.28177 1.172 1.968 +1.509 1.32836 1.182 1.974 +1.48 1.3061 1.242 2.011 +1.453 1.27963 1.235 2.007 +1.426 1.28405 1.243 2.011 +1.4 1.3048 1.278 2.033 +1.374 1.27725 1.266 2.025 +1.35 1.26401 1.259 2.021 +1.326 1.27097 1.267 2.026 +1.302 1.25083 1.286 2.038 +1.28 1.27442 1.329 2.066 +1.257 1.25718 1.326 2.064 +1.236 1.24101 1.363 2.087 +1.215 1.26954 1.317 2.058 +1.194 1.25731 1.347 2.077 +1.174 1.2289 1.398 2.11 +1.155 1.25579 1.444 2.142 +1.136 1.26045 1.439 2.138 +1.117 1.21447 1.467 2.157 +1.099 1.23537 1.386 2.103 +1.081 1.19093 1.362 2.087 +1.064 1.22757 1.455 2.149 +1.047 1.2354 1.524 2.196 +1.031 1.22697 1.536 2.204 +1.015 1.24826 1.524 2.196 +0.9992 1.20573 1.52 2.193 +0.984 1.21929 1.578 2.234 +0.969 1.21584 1.571 2.229 +0.9544 1.18069 1.591 2.243 +0.9401 1.21358 1.565 2.225 +0.926 1.17671 1.569 2.228 +0.9124 1.20448 1.608 2.255 +0.899 1.19679 1.633 2.273 +0.8859 1.1804 1.702 2.323 +0.8731 1.19104 1.776 2.378 +0.8607 1.20292 1.923 2.489 +0.8484 1.17057 1.893 2.466 +0.8364 1.15596 1.865 2.445 +0.8248 1.16261 2.055 2.593 +0.8134 1.11133 2.045 2.585 +0.802 1.13522 1.899 2.471 +0.791 1.09169 1.977 2.531 +0.7802 1.08777 1.988 2.54 +0.7696 1.09796 2.019 2.565 +0.7593 1.06347 1.991 2.543 +0.7491 1.0677 2.006 2.554 +0.7391 1.0665 2.021 2.566 +0.7294 1.03041 2.179 2.693 +0.7197 0.94972 2.185 2.697 +0.7104 0.99294 2.02 2.565 +0.7012 0.98311 2.062 2.599 +0.6922 0.9133 2.076 2.609 +0.6833 0.92045 2.108 2.635 +0.6746 0.97539 2.175 2.689 +0.6662 0.88685 2.202 2.711 +0.6577 0.87409 2.315 2.803 +0.6495 0.84278 2.37 2.849 +0.6416 0.80686 2.339 2.823 +0.6336 0.80866 2.431 2.9 +0.6259 0.79862 2.33 2.816 +0.6183 0.78294 2.402 2.876 +0.6109 0.73388 2.4 2.874 +0.6035 0.72837 2.402 2.876 +0.5963 0.68942 2.416 2.888 +0.5893 0.66822 2.512 2.968 +0.5822 0.67866 2.607 3.049 +0.5754 0.63018 2.677 3.109 +0.5688 0.61675 2.743 3.166 +0.5621 0.58089 2.773 3.192 +0.5556 0.56936 2.699 3.128 +0.5493 0.5787 2.755 3.176 +0.5431 0.51895 2.923 3.323 +0.5368 0.49915 3.089 3.47 +0.5309 0.4732 3.458 3.802 +0.525 0.47553 3.321 3.678 +0.5191 0.46515 2.861 3.269 +0.5133 0.4405 2.793 3.209 +0.5077 0.42278 2.857 3.265 +0.5021 0.40016 2.921 3.322 +0.4966 0.4351 2.963 3.358 +0.4913 0.37406 3.166 3.539 +0.4859 0.36487 3.236 3.601 +0.4808 0.36752 3.399 3.749 +0.4755 0.33903 3.683 4.008 +0.4706 0.31501 3.778 4.096 +0.4656 0.31341 3.639 3.968 +0.4605 0.30915 4.723 4.981 +0.4423 0.23142 5.598 5.817 +0.4245 0.20924 6.362 6.556 +0.4079 0.15968 7.015 7.191 +0.3925 0.13197 7.467 7.633 +0.3774 0.09964 8.234 8.384 +0.3636 0.08837 10.33 10.45 +0.3502 0.08621 9.592 9.721 +0.3375 0.06912 10.034 10.158 +0.3259 0.0744 10.953 11.066 +0.3151 0.04931 13.457 13.55 +0.3044 0.055 12.917 13.013 +0.2935 0.03757 17.507 17.578 +0.2852 0.04581 16.891 16.965 +0.275 0.04848 15.416 15.496 +0.2669 0.05588 14.699 14.784 +0.2579 0.03741 18.006 18.076 +0.2496 0.02321 23.666 23.719 +0.2429 0.04345 18.939 19.005 +0.2339 0.02734 23.867 23.92 +0.228 0.03368 23.13 23.184 +0.2209 0.01302 36.719 36.753 +0.2156 0.03819 22.91 22.964 +0.2086 0.02175 30.93 30.97 +0.2026 0.02156 30.451 30.492 +0.1984 0.03602 26.167 26.215 +0.1916 0.02999 29.547 29.589 +0.187 0.02055 36.16 36.194 +0.1818 0.02843 29.102 29.145 +0.178 0.02632 29.23 29.273 +0.1731 0.02721 32.385 32.423 +0.1694 0.02585 34.212 34.248 +0.165 0.01988 38.291 38.324 +0.1613 0.01266 53.294 53.318 +0.1562 0.01475 46.935 46.962 +0.1545 0.00971 65.111 65.13 +0.1488 0.02381 43.429 43.458 +0.1457 0.01861 50.015 50.04 +0.1424 0.01991 50.069 50.094 +0.1394 0.02553 42.946 42.975 +0.1357 0.04215 31.25 31.29 +0.1323 0.01152 54.328 54.351 +0.1297 0.02055 42.771 42.8 +0.126 0.00872 62.588 62.608 +0.1241 0.03374 37.013 37.047 +0.1213 0.01778 46.359 46.386 +0.1187 0.02999 41.222 41.252 +0.1162 0.01454 52.004 52.028 +0.1146 0.02078 47.174 47.2 +ENDDATA 257 +ENDSUBENT 277 +SUBENT 41776003 20241126 20250110 20250110 4220 +BIB 5 9 +REACTION (93-NP-237(N,F),,SIG) +MONITOR (92-U-235(N,F),,SIG) +MONIT-REF (,A.D.Carlson+,J,NDS,148,143,2018) +ERR-ANALYS (ERR-T) Total uncertainty includes: + (ERR-1) Total uncertainty of ratio Np237/U235 + (MONIT-ERR) Uncertainty of U-235 monitor +STATUS (TABLE) Data were received from the authors. + Data are on Figs.8-10. + (DEP,41776002) Ratio of cross sections Np237/U235 +ENDBIB 9 +NOCOMMON 0 0 +DATA 6 242 +EN MONIT MONIT-ERR DATA ERR-T ERR-1 +MEV B PER-CENT B PER-CENT PER-CENT +425.6 1.5998 6.742 1.63816 7.157 2.402 +361.9 1.5954 6.3 1.64844 6.664 2.171 +313.2 1.57022 5.277 1.6145 5.662 2.052 +274.2 1.53388 4.871 1.56937 5.262 1.99 +243. 1.49819 4.715 1.57725 5.084 1.903 +217.3 1.46879 4.587 1.54645 4.96 1.888 +195.9 1.44593 4.5 1.49567 4.877 1.881 +177.7 1.45658 4.642 1.48779 5.007 1.875 +162. 1.445 4.475 1.49285 4.853 1.877 +148.6 1.45638 4.172 1.51469 4.575 1.877 +136.8 1.4654 4.27 1.4889 4.665 1.879 +126.4 1.483 4.44 1.51992 4.822 1.882 +117.3 1.51183 4.6 1.51447 4.971 1.885 +109.2 1.5389 4.74 1.56821 5.103 1.89 +101.9 1.55245 3.753 1.58575 4.205 1.898 +95.29 1.58102 3.718 1.6154 4.178 1.906 +89.4 1.62035 3.735 1.65458 4.196 1.911 +84.02 1.69967 3.6 1.76867 4.08 1.919 +79.19 1.71388 2.859 1.76543 3.449 1.929 +74.73 1.73751 2.668 1.75181 3.296 1.935 +70.68 1.7432 2.534 1.78821 3.194 1.944 +66.91 1.78771 2.4 1.85803 3.097 1.957 +63.51 1.83684 2.437 1.87309 3.13 1.964 +60.34 1.84873 2.675 1.90087 3.325 1.976 +57.39 1.87849 2.861 1.91976 3.481 1.983 +54.68 1.87648 3. 1.94322 3.601 1.992 +52.15 1.90323 3. 1.97355 3.607 2.003 +49.82 1.90189 2.691 1.96409 3.363 2.017 +47.61 1.92685 2.542 1.95358 3.246 2.019 +45.59 1.95387 2.32 2.0576 3.089 2.039 +43.66 1.9667 2.383 2.02904 3.141 2.047 +41.87 1.97643 2.313 2.02783 3.093 2.054 +40.19 1.99491 2.481 2.08353 3.227 2.063 +38.6 1.9844 2.5 2.08766 3.25 2.077 +37.13 2.00336 2.413 2.05376 3.189 2.086 +35.71 2.04704 2.286 2.10996 3.097 2.09 +34.4 2.1014 2.22 2.17332 3.061 2.108 +33.15 2.12693 2.2 2.17296 3.053 2.117 +31.97 2.13924 2.194 2.24445 3.058 2.131 +30.86 2.14812 1.972 2.23926 2.913 2.144 +29.79 2.1445 1.8 2.21944 2.567 1.831 +27.37 2.11799 1.874 2.22228 2.63 1.845 +25.23 2.12723 1.669 2.27195 2.498 1.859 +23.35 2.1254 1.735 2.26823 2.552 1.871 +21.66 2.10582 1.864 2.25969 2.654 1.889 +20.16 2.03256 1.516 2.2414 2.436 1.907 +18.8 2.0374 1.42 2.28178 2.387 1.918 +17.59 2.07499 1.5 2.26999 2.433 1.916 +16.48 2.12712 1.448 2.2533 2.404 1.919 +15.48 2.13944 1.4 2.28469 2.382 1.927 +14.57 2.09504 1.314 2.24646 2.341 1.937 +13.73 2.02689 1.327 2.17322 2.358 1.95 +12.96 1.8794 1.4 2.15752 2.417 1.97 +12.27 1.76555 1.4 2.07279 2.417 1.97 +11.62 1.70808 1.476 2.05653 2.457 1.965 +11.03 1.73408 1.406 2.17478 2.415 1.963 +10.48 1.74796 1.4 2.18392 2.399 1.948 +9.968 1.75964 1.4 2.18524 2.388 1.935 +9.494 1.76912 1.4 2.24692 2.381 1.926 +9.051 1.77798 1.4 2.23526 2.371 1.914 +8.643 1.789 1.4 2.26017 2.362 1.902 +8.256 1.7891 1.4 2.31296 2.361 1.901 +7.9 1.7662 1.4 2.257 2.358 1.897 +7.564 1.71047 1.4 2.29782 2.363 1.904 +7.25 1.622 1.4 2.19554 2.367 1.908 +6.956 1.52461 1.4 2.11832 2.375 1.919 +6.678 1.4084 1.4 2.04552 2.395 1.943 +6.415 1.29037 1.4 1.93582 2.42 1.974 +6.171 1.16724 1.4 1.76015 2.446 2.006 +5.941 1.07637 1.4 1.6566 2.479 2.046 +5.721 1.03874 1.374 1.54474 2.477 2.061 +5.513 1.03804 1.304 1.49671 2.438 2.06 +5.317 1.05539 1.3 1.49132 2.427 2.049 +5.132 1.06596 1.3 1.51619 2.426 2.049 +4.956 1.07711 1.3 1.51534 2.419 2.04 +4.789 1.09269 1.3 1.53298 2.412 2.032 +4.63 1.10695 1.3 1.54568 2.404 2.023 +4.478 1.11884 1.3 1.59756 2.4 2.017 +4.334 1.12431 1.3 1.5832 2.4 2.018 +4.196 1.12955 1.3 1.60159 2.391 2.007 +4.068 1.13442 1.3 1.56982 2.385 2. +3.942 1.14106 1.3 1.61419 2.38 1.994 +3.823 1.14939 1.3 1.62067 2.378 1.991 +3.71 1.1573 1.3 1.58079 2.37 1.982 +3.601 1.16493 1.3 1.60673 2.369 1.98 +3.497 1.17393 1.3 1.62936 2.356 1.965 +3.398 1.18251 1.3 1.6282 2.353 1.961 +3.303 1.19074 1.3 1.62703 2.361 1.97 +3.211 1.19871 1.3 1.67118 2.351 1.959 +3.124 1.20625 1.3 1.65942 2.347 1.953 +3.04 1.21353 1.3 1.66099 2.335 1.94 +2.959 1.22172 1.3 1.68707 2.344 1.95 +2.882 1.23057 1.3 1.65078 2.325 1.928 +2.807 1.2392 1.3 1.69378 2.326 1.929 +2.735 1.24553 1.3 1.68524 2.326 1.929 +2.666 1.25139 1.3 1.70573 2.33 1.934 +2.6 1.257 1.3 1.72072 2.324 1.926 +2.536 1.25988 1.3 1.71177 2.324 1.926 +2.474 1.26267 1.3 1.71149 2.307 1.906 +2.416 1.26528 1.3 1.7014 2.309 1.909 +2.358 1.26894 1.3 1.71299 2.31 1.909 +2.302 1.27286 1.3 1.7214 2.324 1.926 +2.249 1.27657 1.3 1.74436 2.31 1.91 +2.198 1.28009 1.3 1.71565 2.316 1.917 +2.148 1.28234 1.3 1.69717 2.307 1.906 +2.1 1.2845 1.3 1.71826 2.312 1.912 +2.053 1.28662 1.3 1.70702 2.324 1.926 +2.009 1.28859 1.3 1.71118 2.308 1.907 +1.965 1.2862 1.3 1.70219 2.314 1.914 +1.923 1.28284 1.3 1.66753 2.317 1.918 +1.883 1.27964 1.3 1.69838 2.305 1.904 +1.843 1.27644 1.3 1.66074 2.295 1.891 +1.805 1.2734 1.3 1.6919 2.314 1.914 +1.768 1.27012 1.3 1.70489 2.341 1.947 +1.731 1.26679 1.3 1.64871 2.36 1.97 +1.697 1.26373 1.3 1.67749 2.35 1.958 +1.663 1.26067 1.3 1.63813 2.344 1.951 +1.63 1.2577 1.3 1.65804 2.332 1.936 +1.599 1.25486 1.3 1.61606 2.341 1.947 +1.568 1.25068 1.3 1.64531 2.346 1.953 +1.538 1.24663 1.3 1.5979 2.359 1.968 +1.509 1.24272 1.3 1.65078 2.364 1.974 +1.48 1.2388 1.3 1.61799 2.394 2.011 +1.453 1.23516 1.3 1.58054 2.391 2.007 +1.426 1.23151 1.3 1.58132 2.395 2.011 +1.4 1.228 1.3 1.60229 2.413 2.033 +1.374 1.22505 1.3 1.5647 2.407 2.025 +1.35 1.22233 1.3 1.54504 2.403 2.021 +1.326 1.21961 1.3 1.5501 2.407 2.026 +1.302 1.21689 1.3 1.52212 2.418 2.038 +1.28 1.2144 1.3 1.54765 2.441 2.066 +1.257 1.21179 1.3 1.52344 2.439 2.064 +1.236 1.20941 1.3 1.5009 2.459 2.087 +1.215 1.20703 1.3 1.53238 2.434 2.058 +1.194 1.20465 1.3 1.51463 2.45 2.077 +1.174 1.20239 1.3 1.47761 2.479 2.11 +1.155 1.20023 1.3 1.50725 2.505 2.142 +1.136 1.19808 1.3 1.51012 2.502 2.138 +1.117 1.19593 1.3 1.45242 2.518 2.157 +1.099 1.19409 1.3 1.47514 2.472 2.103 +1.081 1.19571 1.3 1.42401 2.459 2.087 +1.064 1.19724 1.3 1.46969 2.511 2.149 +1.047 1.19877 1.3 1.48096 2.552 2.196 +1.031 1.20021 1.3 1.47262 2.559 2.204 +1.015 1.20165 1.3 1.49998 2.552 2.196 +0.9992 1.20316 1.304 1.45069 2.551 2.193 +0.984 1.2062 1.38 1.47071 2.626 2.234 +0.969 1.2015 1.4 1.46084 2.632 2.229 +0.9544 1.19028 1.372 1.40535 2.629 2.243 +0.9401 1.17312 1.3 1.42367 2.577 2.225 +0.926 1.16285 1.3 1.36834 2.579 2.228 +0.9124 1.15299 1.3 1.38875 2.603 2.255 +0.899 1.14352 1.3 1.36856 2.619 2.273 +0.8859 1.13723 1.3 1.34239 2.662 2.323 +0.8731 1.13109 1.3 1.34717 2.71 2.378 +0.8607 1.12514 1.3 1.35345 2.808 2.489 +0.8484 1.11971 1.3 1.3107 2.788 2.466 +0.8364 1.11755 1.3 1.29185 2.769 2.445 +0.8248 1.11546 1.3 1.29685 2.901 2.593 +0.8134 1.11341 1.3 1.23737 2.893 2.585 +0.802 1.11136 1.3 1.26164 2.792 2.471 +0.791 1.11478 1.3 1.21699 2.846 2.531 +0.7802 1.11932 1.3 1.21756 2.853 2.54 +0.7696 1.12377 1.3 1.23385 2.875 2.565 +0.7593 1.12809 1.3 1.1997 2.856 2.543 +0.7491 1.13173 1.3 1.20834 2.866 2.554 +0.7391 1.12873 1.3 1.20379 2.876 2.566 +0.7294 1.12582 1.3 1.16006 2.99 2.693 +0.7197 1.12291 1.3 1.06645 2.994 2.697 +0.7104 1.12012 1.3 1.11221 2.876 2.565 +0.7012 1.11736 1.3 1.09849 2.906 2.599 +0.6922 1.11747 1.3 1.02059 2.915 2.609 +0.6833 1.118 1.3 1.02907 2.939 2.635 +0.6746 1.11852 1.3 1.091 2.987 2.689 +0.6662 1.11903 1.3 0.99241 3.006 2.711 +0.6577 1.11954 1.3 0.97857 3.09 2.803 +0.6495 1.1199 1.3 0.94383 3.132 2.849 +0.6416 1.11832 1.3 0.90233 3.108 2.823 +0.6336 1.11672 1.3 0.90305 3.178 2.9 +0.6259 1.11518 1.3 0.8906 3.102 2.816 +0.6183 1.11366 1.3 0.87193 3.156 2.876 +0.6109 1.11218 1.3 0.81621 3.154 2.874 +0.6035 1.1107 1.3 0.809 3.156 2.876 +0.5963 1.11358 1.312 0.76773 3.172 2.888 +0.5893 1.12034 1.336 0.74863 3.255 2.968 +0.5822 1.12721 1.359 0.76499 3.338 3.049 +0.5754 1.13378 1.382 0.71448 3.403 3.109 +0.5688 1.13836 1.4 0.70208 3.462 3.166 +0.5621 1.13479 1.4 0.65918 3.485 3.192 +0.5556 1.13132 1.4 0.64413 3.427 3.128 +0.5493 1.12796 1.4 0.65275 3.471 3.176 +0.5431 1.12465 1.4 0.58363 3.606 3.323 +0.5368 1.12572 1.4 0.5619 3.742 3.47 +0.5309 1.13074 1.4 0.53507 4.052 3.802 +0.525 1.13575 1.4 0.54009 3.935 3.678 +0.5191 1.14009 1.396 0.53031 3.554 3.269 +0.5133 1.14067 1.366 0.50246 3.488 3.209 +0.5077 1.14123 1.339 0.48249 3.529 3.265 +0.5021 1.14179 1.311 0.4569 3.571 3.322 +0.4966 1.14173 1.314 0.49677 3.606 3.358 +0.4913 1.1413 1.335 0.42692 3.782 3.539 +0.4859 1.14087 1.356 0.41627 3.848 3.601 +0.4808 1.14046 1.377 0.41915 3.994 3.749 +0.4755 1.14004 1.398 0.38651 4.245 4.008 +0.4706 1.1444 1.4 0.3605 4.328 4.096 +0.4656 1.1494 1.4 0.36023 4.208 3.968 +0.4605 1.1545 1.4 0.35692 5.174 4.981 +0.4423 1.1764 1.4 0.27224 5.983 5.817 +0.4245 1.20168 1.4 0.25143 6.704 6.556 +0.4079 1.19106 1.4 0.19018 7.326 7.191 +0.3925 1.1959 1.4 0.15782 7.76 7.633 +0.3774 1.21583 1.4 0.12114 8.501 8.384 +0.3636 1.21763 1.354 0.1076 10.537 10.45 +0.3502 1.21602 1.301 0.10484 9.808 9.721 +0.3375 1.226 1.35 0.08474 10.247 10.158 +0.3259 1.23528 1.396 0.0919 11.154 11.066 +0.3151 1.23402 1.36 0.06085 13.618 13.55 +0.3044 1.23188 1.318 0.06775 13.079 13.013 +0.2935 1.23198 1.333 0.04629 17.628 17.578 +0.2852 1.23322 1.374 0.05649 17.021 16.965 +0.275 1.242 1.4 0.06022 15.56 15.496 +0.2669 1.25465 1.4 0.07011 14.85 14.784 +0.2579 1.26857 1.4 0.04745 18.13 18.076 +0.2496 1.28288 1.4 0.02978 23.76 23.719 +0.2429 1.29342 1.4 0.0562 19.056 19.005 +0.2339 1.3029 1.4 0.03562 23.96 23.92 +0.228 1.304 1.4 0.04392 23.227 23.184 +0.2209 1.32175 1.4 0.0172 36.779 36.753 +0.2156 1.335 1.4 0.05099 23.007 22.964 +0.2086 1.34872 1.4 0.02934 31.002 30.97 +0.2026 1.34752 1.4 0.02906 30.524 30.492 +0.1984 1.35052 1.4 0.04864 26.253 26.215 +0.1916 1.36548 1.4 0.04095 29.622 29.589 +0.187 1.3774 1.43 0.02831 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