2025-03-04

IAEA-NDS · Mar 5, 2025 · ae83bec · ae83bec
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diff --git a/exforall/312/31276.x4 b/exforall/312/31276.x4
@@ -1,18 +1,18 @@
-ENTRY            31276   20110509   20110803   20110720       3150
-SUBENT        31276001   20110509   20110803   20110720       3150
-BIB                 12         29
+ENTRY            31276   20250108   20250304   20250304       3216
+SUBENT        31276001   20250108   20250304   20250304       3216
+BIB                 12         30
 TITLE      Determination of thermal neutron absorption
             cross-section in boron using spherical transmission
             method.
 AUTHOR     (G.Singh, A.K.Ghatak)
 INSTITUTE  (3INDDLH)
-REFERENCE  (J,PIA,27,216,1961)
+REFERENCE  (J,PSI/A,27,216,1961)
 FACILITY   (REAC,3INDDLH)
 INC-SOURCE (RA-BE) A 100 mc Ra-alpha-Be neutron source was placed
             at the centre of an aluminium sphere which was filled
-            with paraffin wax. The radius of the sphere was 10-30
-            cm which corresponds to the optimum thermal neutron
-            output from a paraffin wax moderator
+            with paraffin wax. The radius of the sphere was
+           10-30 cm which corresponds to the optimum thermal
+           neutron output from a paraffin wax moderator
 INC-SPECT  Thermal spectrum.
 SAMPLE     Precise B-10 abundance in sample is unknown.
            Three different concentrations of the boric acid
@@ -25,14 +25,15 @@ DETECTOR   The outcoming neutrons were detected by an indium foil
             was extrapolated to zero time. Initial activity due
             to thermal neutrons only was obtained by the cadmium
             difference technique.
-STATUS     (TABLE) Table 2 of Proc.Ind.Acad.Sci.A27(1961)216
-HISTORY    (19771115T) Converted from EXFOR 70276
+STATUS     (TABLE,,G.Singh+,J,PSI/A,27,216,1961) Table 2
+HISTORY    (19771115T) Converted from EXFOR 70276.
            (20090912A) SD:Updated to new date formats,lower case.
             Cosmetic changes. Description of experiment added.
            (20110509A) On. INC-SOURCE corrected
-ENDBIB              29
+           (20250108U) On. REFERENCE: PIA -> PSI/A
+ENDBIB              30
 NOCOMMON             0          0
-ENDSUBENT           32
+ENDSUBENT           33
 SUBENT        31276002   20090928   20100128   20100126       3142
 BIB                  2          2
 REACTION   (5-B-0(N,ABS),,SIG,,MXW)

diff --git a/exforall/318/31801.x4 b/exforall/318/31801.x4
@@ -1,6 +1,6 @@
-ENTRY            31801   20200710   20210003   20201203       3197
-SUBENT        31801001   20200710   20210003   20201203       3197
-BIB                 11         23
+ENTRY            31801   20241211   20250304   20250304       3216
+SUBENT        31801001   20241211   20250304   20250304       3216
+BIB                 11         24
 TITLE      Improved 242Pu(n,g) thermal cross section combining
             activation and prompt gamma analysis
 AUTHOR     (J.Lerendegui-Marco, C.Guerrero, T.Belgya, B.Maroti,
@@ -24,15 +24,16 @@ ADD-RES    The weighted average of the cross sections from the
             average thermal capture cross secton=18.9+/-0.9 b.
 STATUS     (APRVD) Approved by Jorge Lerendegui-Marco (2020-07-16)
 HISTORY    (20200710C) On
-ENDBIB              23
+           (20241211A) On. Major alteration in 004.
+ENDBIB              24
 COMMON               1          3
 EN
 EV
  0.0253
 ENDCOMMON            3
-ENDSUBENT           30
-SUBENT        31801002   20200710   20210003   20201203       3197
-BIB                 11         45
+ENDSUBENT           31
+SUBENT        31801002   20241211   20250304   20250304       3216
+BIB                 12         47
 REACTION   (94-PU-242(N,G)94-PU-243,,SIG)
 DECAY-DATA The 67 keV line was also measured but excluded
             due to large uncertainty in decay intensity (50%).
@@ -77,8 +78,10 @@ ERR-ANALYS (ERR-T) Total uncertainty propagated from
            (ERR-10)    Counting statistics/Pu
            (ERR-11)    Decay gamma intensity/P
            (ERR-12)    Detection efficiency/Pu
-STATUS     (TABLE) Table 6 of Eur.Phys.J.A,55(2019)63
-ENDBIB              45
+STATUS     (TABLE,,J.Lerendegui-Marco+,J,EPJ/A,55,63,2019)
+            Table 6
+HISTORY    (20241211U) On. STATUS format updated.
+ENDBIB              47
 COMMON               9          6
 ERR-1      ERR-2      ERR-3      ERR-4      ERR-5      ERR-6
 ERR-7      ERR-8      ERR-9
@@ -95,9 +98,9 @@ B          B          PER-CENT   PER-CENT   PER-CENT   NO-DIM
  21.        3.         2.9        11.        1.4        3.
  19.5       1.7        2.0         6.6       1.3        4.
 ENDDATA              6
-ENDSUBENT           63
-SUBENT        31801003   20200710   20210003   20201203       3197
-BIB                  4         22
+ENDSUBENT           65
+SUBENT        31801003   20241211   20250304   20250304       3216
+BIB                  5         24
 REACTION   (94-PU-242(N,G)94-PU-243,,SIG,,AV)
 ANALYSIS   Weighted average of cross sections obtained from the
             counts of four gamma lines
@@ -116,11 +119,13 @@ ERR-ANALYS (ERR-T) Total uncertainty propagated from
                     - decay gamma intensity/Pu
                     - detection efficiency/Pu
                     (0.9 b in the weighted average)
-STATUS     (TABLE) Table 6 + text (p.8) of Eur.Phys.J.A,55(2019)63
+STATUS     (TABLE,,J.Lerendegui-Marco+,J,EPJ/A,55,63,2019)
+            Table 6 + text (p.8)
            (DEP,31801002) Cross section for each gamma line
            (COREL,31801006) Result from PGAA single line method
            (COREL,31801007) Result from PGAA unfolding method
-ENDBIB              22
+HISTORY    (20241211U) On. STATUS format updated.
+ENDBIB              24
 COMMON               9          6
 ERR-1      ERR-2      ERR-3      ERR-4      ERR-5      ERR-6
 ERR-7      ERR-8      ERR-9
@@ -134,9 +139,9 @@ DATA       ERR-T      ERR-10
 B          B          B
  18.7       1.4        0.9
 ENDDATA              3
-ENDSUBENT           37
-SUBENT        31801004   20200710   20210003   20201203       3197
-BIB                  9         29
+ENDSUBENT           39
+SUBENT        31801004   20241211   20250304   20250304       3216
+BIB                 10         31
 REACTION   (94-PU-242(N,G)94-PU-243,PAR,SIG)
 MONITOR    (14-SI-28(N,G)14-SI-29,PAR,SIG)
 SAMPLE     242Pu #1 0.458(13) E+19 at/cm2, 14x14 mm2
@@ -165,40 +170,42 @@ ERR-ANALYS (ERR-T) Total uncertainty propagated from
            (ERR-6) Counting statistics/Si
            (ERR-7) Detection efficiency/Si
            (MONIT-ERR) gamma production cross section/Si
-STATUS     (TABLE) Table 11 of Eur.Phys.J.A,55(2019)63
-ENDBIB              29
+STATUS     (TABLE,,J.Lerendegui-Marco+,J,EPJ/A,55,63,2019)
+            Table 11
+HISTORY    (20241211A) On. Units of MONIT and MONIT-ERR corrected.
+ENDBIB              31
 COMMON               6          3
 E          ERR-1      ERR-2      ERR-3      ERR-4      ERR-5
 KEV        PER-CENT   PER-CENT   PER-CENT   PER-CENT   PER-CENT
  287.       0.27       1.3        1.28       4.0        3.0
 ENDCOMMON            3
 DATA                 8          9
-DATA       ERR-T      ERR-6      ERR-7      MONIT      MONIT-ERR
-E-NRM      FLAG
-B          B          PER-CENT   PER-CENT   PER-CENT   B
-KEV        NO-DIM
- 7.5        0.6        0.72       1.27       0.029     1.9
- 1273.      1.
- 6.9        0.5        0.72       1.27       0.029     1.9
- 1273.      2.
- 7.7        0.6        0.72       1.27       0.029     1.9
- 1273.      3.
- 7.1        0.5        0.54       1.39       0.119     1.7
- 3538.      1.
- 6.5        0.5        0.54       1.39       0.119     1.7
- 3538.      2.
- 7.3        0.5        0.54       1.39       0.119     1.7
- 3538.      3.
- 7.2        0.5        0.67       1.39       0.112     2.0
- 4333.      1.
- 6.8        0.5        0.67       1.39       0.112     2.0
- 4333.      2.
- 7.4        0.6        0.67       1.39       0.112     2.0
- 4333.      3.
+DATA       ERR-T      ERR-6      ERR-7      E-NRM      MONIT
+MONIT-ERR  FLAG
+B          B          PER-CENT   PER-CENT   KEV        B
+PER-CENT   NO-DIM
+ 7.5        0.6        0.72       1.27       1273.      0.029
+ 1.9        1.
+ 6.9        0.5        0.72       1.27       1273.      0.029
+ 1.9        2.
+ 7.7        0.6        0.72       1.27       1273.      0.029
+ 1.9        3.
+ 7.1        0.5        0.54       1.39       3538.      0.119
+ 1.7        1.
+ 6.5        0.5        0.54       1.39       3538.      0.119
+ 1.7        2.
+ 7.3        0.5        0.54       1.39       3538.      0.119
+ 1.7        3.
+ 7.2        0.5        0.67       1.39       4333.      0.112
+ 2.0        1.
+ 6.8        0.5        0.67       1.39       4333.      0.112
+ 2.0        2.
+ 7.4        0.6        0.67       1.39       4333.      0.112
+ 2.0        3.
 ENDDATA             22
-ENDSUBENT           60
-SUBENT        31801005   20200710   20210003   20201203       3197
-BIB                  4         12
+ENDSUBENT           62
+SUBENT        31801005   20241211   20250304   20250304       3216
+BIB                  5         14
 REACTION   (94-PU-242(N,G)94-PU-243,PAR,SIG,,AV)
 ANALYSIS   Weighted average of cross sections obtained from
             three irradiation and three Si gamma lines
@@ -208,10 +215,12 @@ ERR-ANALYS (ERR-T) Total uncertainty
            (ERR-3) Detection efficiency/Al               (1.28%)
            (ERR-4) Sample inhomogenity/Pu                (4.0%)
            (ERR-5) Mass/Pu                               (3.0%)
-STATUS     (TABLE) Text (p.11) of Eur.Phys.J.A,55(2019)63
+STATUS     (TABLE,,J.Lerendegui-Marco+,J,EPJ/A,55,63,2019)
+            Text (p.11)
            (DEP,31801004) Cross sections from three irradiation
             and three Si gamma lines
-ENDBIB              12
+HISTORY    (20241211U) On. STATUS format updated.
+ENDBIB              14
 COMMON               5          3
 ERR-1      ERR-2      ERR-3      ERR-4      ERR-5
 PER-CENT   PER-CENT   PER-CENT   PER-CENT   PER-CENT
@@ -222,30 +231,32 @@ E          DATA       ERR-T
 KEV        B          B
  287.       7.1        0.4
 ENDDATA              3
-ENDSUBENT           24
-SUBENT        31801006   20200710   20210003   20201203       3197
-BIB                  5         11
+ENDSUBENT           26
+SUBENT        31801006   20241211   20250304   20250304       3216
+BIB                  6         13
 REACTION   (94-PU-242(N,G)94-PU-243,,SIG,,,DERIV)
 REL-REF    (R,,C.D.Nesaraja+,J,NDS,121,695,2014)
             287 keV prompt gamma emission probability 0.41+/-0.07
 ANALYSIS   287 keV gamma production cross section divided by
             its emission probability
 ERR-ANALYS (ERR-T) Total uncertainty
            (ERR-1) gamma emission probability (17%)
-STATUS     (TABLE) Table 14 of Eur.Phys.J.A,55(2019)63
+STATUS     (TABLE,,J.Lerendegui-Marco+,J,EPJ/A,55,63,2019)
+            Table 14
            (DEP,31801005) 287 keV gamma production cross section
            (COREL,31801003) Result from activation method
            (COREL,31801007) Result from PGAA unfolding method
-ENDBIB              11
+HISTORY    (20241211U) On. STATUS format updated.
+ENDBIB              13
 NOCOMMON             0          0
 DATA                 3          1
 DATA       ERR-T      ERR-1
 B          B          PER-CENT
  17.        3.         17.
 ENDDATA              3
-ENDSUBENT           19
-SUBENT        31801007   20200710   20210003   20201203       3197
-BIB                  8         24
+ENDSUBENT           21
+SUBENT        31801007   20241211   20250304   20250304       3216
+BIB                  9         26
 REACTION   (94-PU-242(N,G)94-PU-243,,SIG)
 MONITOR    (94-PU-242(N,G)94-PU-243,PAR,SIG)
 DETECTOR   (BGO,HPGE) BGO guarded Canberra GR2720/S (27% relative
@@ -266,11 +277,13 @@ ERR-ANALYS (ERR-T) The overall uncertainty (6.5%) from
            (ERR-2) Statistics in background-subtracted spectrum
             propagated to the weighted sum                  (3.7%)
            (MONIT-ERR) 287 keV gamma prod. cross section    (5.2%)
-STATUS     (TABLE) Table 14 of Eur.Phys.J.A,55(2019)63
+STATUS     (TABLE,,J.Lerendegui-Marco+,J,EPJ/A,55,63,2019)
+            Table 14
            (DEP,31801005) 287 keV production cross section
            (COREL,31801003) Result from activation method
            (COREL,31801006) Result from PGAA single line method
-ENDBIB              24
+HISTORY    (20241211U) On. STATUS format updated.
+ENDBIB              26
 COMMON               2          3
 ERR-1      ERR-2
 PER-CENT   PER-CENT
@@ -281,5 +294,5 @@ DATA       ERR-T      E-NRM      MONIT      MONIT-ERR
 B          B          MEV        B          B
  19.2       1.3        287.       7.1        0.4
 ENDDATA              3
-ENDSUBENT           36
+ENDSUBENT           38
 ENDENTRY             7
diff --git a/exforall/331/33166.x4 b/exforall/331/33166.x4
@@ -1,6 +1,6 @@
-ENTRY            33166   20220831   20230120   20230119       3208
-SUBENT        33166001   20220831   20230120   20230119       3208
-BIB                 11         43
+ENTRY            33166   20241220   20250304   20250304       3216
+SUBENT        33166001   20241220   20250304   20250304       3216
+BIB                 11         44
 TITLE      Post-neutron mass yield distribution in the
            epi-cadmium neutron induced fission of 99.9997 atom %
            238U
@@ -44,13 +44,14 @@ ERR-ANALYS (ERR-S,1.,10.) counting statistics (1-10%)
 STATUS     (TABLE) Table I of Rad.Phys.Chem.189(2021)109755
 HISTORY    (20220105C) VT
            (20220830A) VT. E-MIN-> E-MEAN replaced
-ENDBIB              43
+           (20241220A) On. EN-MEAN=1.9 MeV -> EN-MIN=0.5 eV.
+ENDBIB              44
 COMMON               3          3
-EN-MEAN    ERR-2      ERR-3
-MEV        PER-CENT   PER-CENT
-        1.9         3.         1.
+EN-MIN     ERR-2      ERR-3
+EV         PER-CENT   PER-CENT
+        0.5         3.         1.
 ENDCOMMON            3
-ENDSUBENT           50
+ENDSUBENT           51
 SUBENT        33166002   20220105   20220303   20220303       3206
 BIB                  5        139
 REACTION   (92-U-238(N,F)ELEM/MASS,CUM,FY,,EPI)

diff --git a/exforall/331/33169.x4 b/exforall/331/33169.x4
@@ -1,8 +1,8 @@
-ENTRY            33169   20220304   20220530   20220530       3207
-SUBENT        33169001   20220304   20220530   20220530       3207
-BIB                 10         42
-TITLE      Post-neutron mass yield distribution in the epi-
-           cadmium neutron-induced fission of 237Np
+ENTRY            33169   20241220   20250304   20250304       3216
+SUBENT        33169001   20241220   20250304   20250304       3216
+BIB                 10         43
+TITLE      Post-neutron mass yield distribution in the
+           epi-cadmium neutron-induced fission of 237Np
 AUTHOR     (H.Naik, S.P.Dange, W.Jang, R.J.Singh)
 INSTITUTE  (3INDTRM,3KORKNU)
 REFERENCE  (J,NSE,196,16,2022)
@@ -43,13 +43,14 @@ ERR-ANALYS (ERR-S,1.,10.) counting statistics (1-10%)
            (ERR-4) half-life of the fission products (~1%)
            (ERR-5,2.,5.) gamma-ray intensity (2-5%)
 HISTORY    (20220304C) VT
-ENDBIB              42
+           (20241220A) On. EN-DUMMY -> EN-MIN.
+ENDBIB              43
 COMMON               4          3
-EN-DUMMY   ERR-2      ERR-3      ERR-4
+EN-MIN     ERR-2      ERR-3      ERR-4
 EV         PER-CENT   PER-CENT   PER-CENT
       0.5           2.         3.         1.
 ENDCOMMON            3
-ENDSUBENT           49
+ENDSUBENT           50
 SUBENT        33169002   20220304   20220530   20220530       3207
 BIB                  5        129
 REACTION   (93-NP-237(N,F)ELEM/MASS,CUM,FY,,EPI)

diff --git a/exforall/331/33174.x4 b/exforall/331/33174.x4
@@ -1,8 +1,8 @@
-ENTRY            33174   20220511   20230120   20230119       3208
-SUBENT        33174001   20220511   20230120   20230119       3208
-BIB                 13         45
-TITLE      Post-neutron mass yield distribution in the epi-
-           cadmium neutron-induced fission of 243Am
+ENTRY            33174   20241220   20250304   20250304       3216
+SUBENT        33174001   20241220   20250304   20250304       3216
+BIB                 13         46
+TITLE      Post-neutron mass yield distribution in the
+           epi-cadmium neutron-induced fission of 243Am
 AUTHOR     (H.Naik, R.J.Singh, S.P.Dange, W.Jang)
 INSTITUTE  (3INDTRM,3KORKNU)
 REFERENCE  (J,NSE,196,694,2022)
@@ -46,13 +46,14 @@ ERR-ANALYS (ERR-S,1.,10.) counting statistics (1-10%)
            (ERR-3) half-life of the fission products (~1%)
            (ERR-4,2.,5.) gamma-ray intensity (2-5%)
 HISTORY    (20220511C) VT
-ENDBIB              45
+           (20241220A) On. EN-MIN: 1.9 MeV -> 0.5 eV
+ENDBIB              46
 COMMON               3          3
 EN-MIN     ERR-2      ERR-3
-MEV        PER-CENT   PER-CENT
-      1.9         3.         1.
+EV         PER-CENT   PER-CENT
+      0.5         3.         1.
 ENDCOMMON            3
-ENDSUBENT           52
+ENDSUBENT           53
 SUBENT        33174002   20220511   20230120   20230119       3208
 BIB                  4        133
 REACTION   (95-AM-243(N,F)ELEM/MASS,CUM,FY,,EPI)