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23 changes: 13 additions & 10 deletions exforall/102/10262.x4
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ENTRY 10262 20011204 20020117
SUBENT 10262001 20011204 20020117
BIB 14 24
ENTRY 10262 20011204 20060111 1337
SUBENT 10262001 20011204 20060111 1337
BIB 14 28
INSTITUTE (1USAORL)
REFERENCE (J,PL/B,38,501,197204)
AUTHOR (H.Rosler,F.Plasil,H.W.Schmitt)
Expand All @@ -25,10 +25,14 @@ STATUS No reply to author proff.
HISTORY (19750812C)
(19830613A) Converted to REACTION formalism
(20011204A) Converted to new date formats, lower case.
ENDBIB 24
(20051018C) DR First value at 0.4916 MeV deleted
because of its possible wrong value (of
0.08421) compared to cross sections at
0.4921 MeV and higher energies
ENDBIB 28
NOCOMMON 0 0
ENDSUBENT 27
SUBENT 10262002 20011204 20020117
ENDSUBENT 31
SUBENT 10262002 20011204 20060111 1337
BIB 1 1
REACTION (92-U-236(N,F),,SIG)
ENDBIB 1
Expand All @@ -37,10 +41,9 @@ EN-RSL EN-NRM
KEV MEV
7. 2.
ENDCOMMON 3
DATA 2 1484
DATA 2 1483
EN DATA
MEV B
0.4916 0.08421
0.4921 0.02074
0.4926 0.02023
0.4931 0.01880
Expand Down Expand Up @@ -1524,6 +1527,6 @@ MEV B
9.4358 1.03126
9.4793 1.01599
9.5231 1.01947
ENDDATA 1486
ENDSUBENT 1496
ENDDATA 1485
ENDSUBENT 1495
ENDENTRY 2
36 changes: 19 additions & 17 deletions exforall/102/10266.x4
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ENTRY 10266 20011204 20020117
SUBENT 10266001 20011204 20020117
BIB 13 37
ENTRY 10266 20051017 20060111 1337
SUBENT 10266001 20051017 20060111 1337
BIB 13 39
INSTITUTE (1USALAS)
REFERENCE (J,NP/A,171,31,197108)
AUTHOR (G.F.Auchampaugh,J.A.Farrell,D.W.Bergen)
Expand Down Expand Up @@ -38,10 +38,12 @@ HISTORY (19720724C)
(19820311A) BIB correction.
(19830608A) MONITOR corrected
(20011204A) Converted to new date formats, lower case.
ENDBIB 37
(20051017A) DR ERR-1 corrected in subentries 2,4,5 and
6 from "barn" to "percent"
ENDBIB 39
NOCOMMON 0 0
ENDSUBENT 40
SUBENT 10266002 20011204 20020117
ENDSUBENT 42
SUBENT 10266002 20011204 20060111 1337
BIB 6 16
REACTION (94-PU-242(N,F),,SIG)
SAMPLE Pu oxide sample - 99.91% 242Pu. Sample thickness
Expand All @@ -62,8 +64,8 @@ HISTORY (19810814A) BIB corrections.
ENDBIB 16
COMMON 2 3
EN-RSL ERR-1
NSEC/M B
0.8 0.062
NSEC/M PER-CENT
0.8 6.2
ENDCOMMON 3
DATA 3 127
EN DATA ERR-S
Expand Down Expand Up @@ -333,7 +335,7 @@ EV B B
3.9859E+06 1.2459E+00 4.580E-02
ENDDATA 109
ENDSUBENT 134
SUBENT 10266004 20011204 20020117
SUBENT 10266004 20011204 20060111 1337
BIB 6 15
REACTION (94-PU-242(N,F),,SIG)
SAMPLE Pu oxide sample - 99.91% 242Pu. Sample thickness
Expand All @@ -353,8 +355,8 @@ HISTORY (19730507C)
ENDBIB 15
COMMON 1 3
ERR-1
B
0.062
PER-CENT
6.2
ENDCOMMON 3
DATA 3 6367
EN DATA ERR-S
Expand Down Expand Up @@ -6728,7 +6730,7 @@ EV B B
5.0143E+05 2.0531E-01 8.2200E-02
ENDDATA 6369
ENDSUBENT 6393
SUBENT 10266005 20011204 20020117
SUBENT 10266005 20011204 20060111 1337
BIB 5 13
REACTION (94-PU-244(N,F),,SIG)
SAMPLE Pu oxide sample - 99.06% 244Pu. Sample thickness
Expand All @@ -6746,8 +6748,8 @@ HISTORY (19810814A) BIB corrections.
ENDBIB 13
COMMON 1 3
ERR-1
B
0.056
PER-CENT
5.6
ENDCOMMON 3
DATA 3 6037
EN DATA ERR-S
Expand Down Expand Up @@ -12791,7 +12793,7 @@ EV B B
9.6529E+06 1.2735E+00 5.640E-02
ENDDATA 6039
ENDSUBENT 6061
SUBENT 10266006 20011204 20020117
SUBENT 10266006 20011204 20060111 1337
BIB 5 13
REACTION (94-PU-244(N,F),,SIG)
SAMPLE Pu oxide sample - 99.06% 244Pu. Sample thickness
Expand All @@ -12809,8 +12811,8 @@ HISTORY (19810814A) BIB corrections.
ENDBIB 13
COMMON 1 3
ERR-1
B
0.056
PER-CENT
5.6
ENDCOMMON 3
DATA 3 1966
EN DATA ERR-S
Expand Down
191 changes: 97 additions & 94 deletions exforall/106/10654.x4
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Original file line number Diff line number Diff line change
@@ -1,79 +1,81 @@
ENTRY 10654 840306
SUBENT 10654001 840306
BIB 12 51
ENTRY 10654 20051010 20060111 1337
SUBENT 10654001 20051010 20060111 1337
BIB 12 53
INSTITUTE (1USAANL)
REFERENCE (J,NSE,65,171,7801)
(R,ANL-NDM-83,8310) REVISED DATA.
(C,76ANL,73,760628)
AUTHOR (J.W.MEADOWS)
TITLE THE FISSION CROSS SECTIONS OF URANIUM-234 AND
URANIUM-236 ISOTOPES RELATIVE TO U-235.
FACILITY (DYNAM) FAST NEUTRON GENERATOR
INC-SOURCE (P-LI7) PROTONS ON LITHIUM METAL FOR NEUTRON ENERGIES
TO 5 MEV.
(D-D) DEUTERONS ON DEUTERIUM GAS FOR NEUTRON ENERGIES
ABOVE 5 MEV.
SAMPLE SAMPLES WERE DEPOSITED ON 0.25 MM STAINLESS STEEL OR
0.13 MM MOLYBDINUM PLATES BY ELECTRO DEPOSITION OR
VACCUUM EVAPORATION IF UF(4).
SHAPE MEASUREMENTS WERE MADE WITH HIGH PURITY SAMPLES.
METHOD PULSED BEAM AND FAST TIMING USED TO REDUCE AND MEASURE
TIME INDEPENDENT BACKGROUND. ABSOLUTE MEASUREMENTS MADE
BETWEEN 2 AND 3 MEV. SHAPE MEASUREMENT NORMALIZED IN
THIS REGION
FOR ABSOLUTE RATIO MEASUREMENTS, MASS RATIOS WERE
OBTAINED BY COMPARING THERMAL FISSION RATIO OF U-235
SAMPLES WITH U-234 AND U-236 SAMPLES CONTAINING 10
PERCENT U-235.
FOR 234-U/235-U RATIOS MASS RATIOS WERE ALSO OBTAINED
BY COMPARING ALPHA DECAY RATES OF 234-U SAMPLES AND
235-U SAMPLES CONTAINING 1 PERCENT 234-U FOR 236-U/
235-U RATIOS.
SAMPLE MASS RATIOS WERE ALSO OBTAINED BY LOW GEOMETRY
ALPHA COUNTING AND SPECIFIC ACTIVITIES CALCULATED
USING ISOTOPIC ANALYSIS AND REPORTED ALPHA HALF-
LIVES.
DETECTOR (IOCH) SAMPLES BACK-TO-BACK IN LOW MASS DOUBLE
IONIZATION CHAMBER USING METHANE AS COUNTER GAS PLACED
5 CM FROM NEUTRON SOURCE
CORRECTION CORRECTED FOR SECOND LI-7(P,N) GROUP, LI-7 AND D
BREAK-UP NEUTRONS, SCATTERING IN DETECTOR AND NEUTRON
SOURCE ASSEMBLY, PULSE-HEIGHT DISTRIBUTION BELOW BIAS
LEVEL. SAMPLE GEOMETRY DIFFERENCES ELIMINATED BY
MEASUREMENTS IN BOTH DETECTOR ORIENTATIONS. MOMENTUM
EFFECTS REDUCED USING SAME PROCEDURE. CORRECTIONS MADE
FOR REMAINING MOMENTUM EFFECTS, DEPOSIT THICKNESS AND
FRAGMENT ANGULAR DISTRIBUTIONS. BACKGROUND FROM (D,N)
REACTIONS WITH GAS TARGET ASSEMBLY MEASURED WITH EMPTY
GAS CELL.
STATUS DATA TAKEN FROM ANL-NDM-83.
(APRVD) J.W.MEADOWS, 84/3/2.
HISTORY (770330C)
(780405U) REFERENCE UPDATE
(831109U) DATA HEADING UPDATE.
(840206A) UPDATED AS PER ANL-NDM-83.
ENDBIB 51
REFERENCE (J,NSE,65,171,1978)
(R,ANL-NDM-83,1983) revised data.
(C,76ANL,73,1976)
AUTHOR (J.W.Meadows)
TITLE The fission cross sections of uranium-234 and
uranium-236 isotopes relative to u-235.
FACILITY (DYNAM) Fast neutron generator
INC-SOURCE (P-LI7) Protons on lithium metal for neutron energies
to 5 MeV.
(D-D) Deuterons on deuterium gas for neutron energies
above 5 MeV.
SAMPLE Samples were deposited on 0.25 mm stainless steel or
0.13 mm molybdinum plates by electro deposition or
vaccuum evaporation of UF(4).
Shape measurements were made with high purity samples.
METHOD Pulsed beam and fast timing used to reduce and measure
time independent background. absolute measurements made
between 2 and 3 MeV. shape measurement normalized in
this region
for absolute ratio measurements, mass ratios were
obtained by comparing thermal fission ratio of U-235
samples with U-234 and U-236 samples containing 10
percent U-235.
For 234-U/235-U ratios mass ratios were also obtained
by comparing alpha decay rates of 234-U samples and
235-U samples containing 1 percent 234-U for 236-U/
235-U ratios.
Sample mass ratios were also obtained by low geometry
alpha counting and specific activities calculated
using isotopic analysis and reported alpha half-
lives.
DETECTOR (IOCH) samples back-to-back in low mass double
ionization chamber using methane as counter gas placed
5 cm from neutron source
CORRECTION Corrected for second Li-7(p,n) group, Li-7 and D
break-up neutrons, scattering in detector and neutron
source assembly, pulse-height distribution below bias
level. sample geometry differences eliminated by
measurements in both detector orientations. momentum
effects reduced using same procedure. corrections made
for remaining momentum effects, deposit thickness and
fragment angular distributions. background from (d,n)
reactions with gas target assembly measured with empty
gas cell.
STATUS Data taken from ANL-NDM-83.
(APRVD) J.W.Meadows, 1984/3/2.
HISTORY (19770330C)
(19780405U) Reference update
(19831109U) Data heading update.
(19840206A) Updated as per ANL-NDM-83.
(20051010C) DR Line "10654002 36" corrected and
format updated
ENDBIB 53
NOCOMMON 0 0
ENDSUBENT 54
SUBENT 10654002 840306
ENDSUBENT 56
SUBENT 10654002 19840306 20060111 1337
BIB 3 17
REACTION 1((92-U-236(N,F),,SIG)/(92-U-235(N,F),,SIG))
2(92-U-236(N,F),,SIG)
MONITOR RATIO NORMALIZED BETWEEN 2.2 AND 3.0 MEV.
2(92-U-235(N,F),,SIG) FROM ENDF/B-V.
ERR-ANALYS1(ERR-S) STATISTICAL UNCERTAINTY
(ERR-T) TOTAL UNCERTAINTY INCLUDES STATISTICAL
ERROR PLUS ERRORS (IN PERCENT) DUE TO -
233-U HALF-LIFE (0.03)
ISOTOPIC ANALYSIS (0.29)
ALPHA-COUNTING SYSTEM (0.15)
THICKNESS CORRECTION (0.10)
EXTRAPOLATION (0.10)
DEAD-TIME CORRECTION (0.25)
SCATTERING CORRECTION (0.60)
SECONDARY SOURCE REACTIONS (20 PERCENT OF CORRECTION)
ERROR IN NEUTRON ENERGY (ABOUT 20 PERCENT OF ENERGY
RESOLUTION)
MONITOR Ratio normalized between 2.2 and 3.0 MeV.
2(92-U-235(N,F),,SIG) from ENDF/B-V.
ERR-ANALYS1(ERR-S) Statistical uncertainty
(ERR-T) Total uncertainty includes statistical
Error plus errors (in percent) due to -
233-U Half-life (0.03)
Isotopic analysis (0.29)
Alpha-counting system (0.15)
Thickness correction (0.10)
Extrapolation (0.10)
Dead-time correction (0.25)
Scattering correction (0.60)
Secondary source reactions (20 percent of correction)
Error in neutron energy (about 20 percent of energy
resolution)
ENDBIB 17
NOCOMMON 0 0
DATA 6 57
Expand All @@ -90,7 +92,7 @@ MEV MEV NO-DIM PER-CENT PER-CENT B
0.899 0.031 0.2117 1.38 4.16 0.2472
0.948 0.030 0.2862 1.24 1.58 0.3434
0.998 0.030 0.2940 1.25 1.59 0.3586
1.047 0.029 0.2940 2.36 1.68 0.3573
1.047 0.029 0.2940 1.36 1.68 0.3573
1.094 0.035 0.345 1.22 5.03 0.419
1.097 0.029 0.361 1.40 4.41 0.438
1.146 0.072 0.428 1.16 4.70 0.521
Expand Down Expand Up @@ -138,29 +140,30 @@ MEV MEV NO-DIM PER-CENT PER-CENT B
9.905 0.122 0.867 1.03 1.78 1.519
ENDDATA 59
ENDSUBENT 81
SUBENT 10654003 860825
BIB 4 20
SUBENT 10654003 19860825 20060111 1337
BIB 4 21
REACTION 1((92-U-234(N,F),,SIG)/(92-U-235(N,F),,SIG))
2(92-U-234(N,F),,SIG)
MONITOR RATIO NORMALIZED BETWEEN 1.9 AND 2.8 MEV.
2(92-U-235(N,F),,SIG) FROM ENDF/B-V.
ERR-ANALYS1(ERR-S) STATISTICAL UNCERTAINTY
(ERR-T) TOTAL UNCERTAINTY INCLUDES STATISTICAL
ERROR PLUS ERRORS (IN PERCENT) DUE TO -
233-U HALF-LIFE (0.03)
234-U HALF-LIFE (0.06)
236-U HALF-LIFE (0.08)
ISOTOPIC ANALYSIS (0.31)
ALPHA-COUNTING SYSTEM (0.15)
THICKNESS CORRECTION (0.18)
EXTRAPOLATION (0.10)
DEAD-TIME CORRECTION (0.25)
SCATTERING CORRECTION (0.45)
SECONDARY SOURCE REACTIONS (20 PERCENT OF CORRECTION)
ERROR IN NEUTRON ENERGY (ABOUT 20 PERCENT OF ENERGY
RESOLUTION)
HISTORY (860825A) REACTION CORRECTED.
ENDBIB 20
MONITOR Ratio normalized between 1.9 and 2.8 MeV.
2(92-U-235(N,F),,SIG) from ENDF/B-V.
ERR-ANALYS1(ERR-S) Statistical uncertainty
(ERR-T) Total uncertainty includes statistical
Error plus errors (in percent) due to -
233-U half-life (0.03)
234-U half-life (0.06)
236-U half-life (0.08)
isotopic analysis (0.31)
alpha-counting system (0.15)
thickness correction (0.18)
extrapolation (0.10)
dead-time correction (0.25)
scattering correction (0.45)
Secondary source reactions (20 percent of correction)
error in neutron energy (about 20 percent of energy
resolution)
HISTORY (19860825A) Reaction corrected.
(20051010C) DR Format updated
ENDBIB 21
NOCOMMON 0 0
DATA 6 56
EN EN-RSL-FW DATA 1ERR-S 1ERR-T 1DATA 2
Expand Down Expand Up @@ -222,5 +225,5 @@ MEV MEV NO-DIM PER-CENT PER-CENT B
9.673 0.121 1.180 1.15 1.42 2.073
9.905 0.122 1.179 1.11 1.38 2.064
ENDDATA 58
ENDSUBENT 83
ENDSUBENT 84
ENDENTRY 3
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