ENTRY 12771 20200713 14711277100000001
SUBENT 12771001 20200713 14711277100100001
BIB 10 46 1277100100002
TITLE The yield of short-lived gamma-ray emitting nuclides 1277100100003
from fast- and thermal-neutron fission 1277100100004
AUTHOR (R.P.Larsen,N.D.Dudey,R.R.Heinrich,R.D.Oldham, 1277100100005
R.J.Armani,R.J.Popek,R.Gold) 1277100100006
INSTITUTE (1USAANL) 1277100100007
REFERENCE (J,NSE,54,263,1974) 1277100100008
#doi:10.13182/NSE74-A23417 1277100100009
#NSR: 1974LA17 1277100100010
(J,ANS,15,483,1972) 235U, 238U, and 239Pu fast fission 1277100100011
yields of short-lived gamma-active nuclides 1277100100012
#NSR: 1972LAZL 1277100100013
(P,ANL-7887,32,1971) Data for 235U, 238U, and 239Pu are1277100100014
the same as in the main reference. The 237Np fission 1277100100015
yield of 140Ba included in 13271002. 1277100100016
(P,ANL-7979,7,1973) Data for 235U, and 239Pu are almost1277100100017
the same as in the main reference. 1277100100018
(J,ANS,14,370,1971) 235U, and 239Pu thermal fission 1277100100019
yields of 95Zr, 103Ru, 131I, presented as relative to 1277100100020
140Ba, are very similar to relative data, calculated 1277100100021
using the main ref. 1277100100022
METHOD (CHSEP,GSPEC) 1277100100023
DETECTOR (GELI) 1277100100024
SAMPLE The fissionable materials were all of very high 1277100100025
isotopic (99.999+%); the amounts ranged from 10 to 1277100100026
50 ng for 235U and 239Pu and from 0.2 to 2 mu-g for 1277100100027
238U. 1277100100028
DECAY-DATA ((1.)40-ZR-95,65.0D,DG,724.,0.445,DG,757.,0.55) 1277100100029
((1.)41-NB-95-G,35.0D,DG,766.,0.98) 1277100100030
((2.)40-ZR-97,0.701D,DG,745.,0.94) 1277100100031
((2.)41-NB-97-G,0.050D,DG,658.,0.99) 1277100100032
((3.)42-MO-99,2.78D,B-) 1277100100033
((4.)44-RU-103,40.0D,DG,497.,0.88) 1277100100034
((5.)53-I-131,8.05D,DG,364.,0.82) 1277100100035
((6.)56-BA-140,12.80D) 1277100100036
((6.)57-LA-140,1.67D,DG,1597.,0.96) 1277100100037
STATUS (APRVD) R.R.Heinrich, 85/10/14. 1277100100038
HISTORY (19850808C) 1277100100039
(19891106A) Bib, reaction update. 1277100100040
(20181130U) OS. ERR-ANALYS upgraded, minor BIB 1277100100041
correction, converted to lower and upper case 1277100100042
(20190418U) OG. REF. (J,ANS,15,483,1972) was added 1277100100043
#NSR were added 1277100100044
(20200713U) OG. #doi, SAMPLE added. 1277100100045
3-rd REF (P,ANL-7887,32,1971) added. 1277100100046
4-th REF (P,ANL-7979,7,1973) added. 1277100100047
5-th REF (J,ANS,14,370,1971) added. 1277100100048
ENDBIB 46 0 1277100100049
NOCOMMON 0 0 1277100100050
ENDSUBENT 49 0 1277100199999
SUBENT 12771002 20181203 14451277100200001
BIB 6 17 1277100200002
REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,FST) 1277100200003
FACILITY (REAC,1USAANL) ZPR-3 1277100200004
INC-SPECT Fast reactor spectrum. 1277100200005
Average of samples at 3 locations with average 1277100200006
fission energies of 446, 442, 293 keV. 1277100200007
MONITOR (92-U-235(N,F)55-CS-137,CUM,FY,,FST) 1277100200008
ERR-ANALYS (DATA-ERR) The following sources of errors are 1277100200009
included: 1277100200010
. the precision of the mean of the gamma counts per 1277100200011
gram of fissionable mateial 1277100200012
. the detector calibration 1277100200013
. the nuclear constants of the fission products 1277100200014
(photon-to disintegration ratios and half-lives) 1277100200015
. the mass absorptions of the gamma rays by the foils 1277100200016
. the weights of the fissionable materials in the 1277100200017
foils 1277100200018
STATUS (TABLE) Data from Nucl.Sci.Eng.54,263(1974), Table II 1277100200019
ENDBIB 17 0 1277100200020
COMMON 1 3 1277100200021
EN-DUMMY 1277100200022
MEV 1277100200023
0.4 1277100200024
ENDCOMMON 3 0 1277100200025
DATA 5 6 1277100200026
ELEMENT MASS DATA DATA-ERR DECAY-FLAG 1277100200027
NO-DIM NO-DIM PC/FIS PER-CENT NO-DIM 1277100200028
40. 95. 6.41 3.5 1. 1277100200029
40. 97. 5.53 3.0 2. 1277100200030
42. 99. 5.70 3.0 3. 1277100200031
44. 103. 3.29 3.1 4. 1277100200032
53. 131. 3.25 3.1 5. 1277100200033
56. 140. 5.67 2.9 6. 1277100200034
ENDDATA 8 0 1277100200035
ENDSUBENT 34 0 1277100299999
SUBENT 12771003 20181203 14451277100300001
BIB 6 17 1277100300002
REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY,,FST) 1277100300003
FACILITY (REAC,1USAANL) ZPR-3 1277100300004
INC-SPECT Fast reactor spectrum. 1277100300005
Average of samples at 2 locations with average 1277100300006
fission energies of 446, 442 keV. 1277100300007
MONITOR (92-U-238(N,F)55-CS-137,CUM,FY,,FST) 1277100300008
ERR-ANALYS (DATA-ERR) The following sources of errors are 1277100300009
included: 1277100300010
. the precision of the mean of the gamma counts per 1277100300011
gram of fissionable mateial 1277100300012
. the detector calibration 1277100300013
. the nuclear constants of the fission products 1277100300014
(photon-to disintegration ratios and half-lives) 1277100300015
. the mass absorptions of the gamma rays by the foils 1277100300016
. the weights of the fissionable materials in the 1277100300017
foils 1277100300018
STATUS (TABLE) Data from Nucl.Sci.Eng.54,263(1974), Table IV 1277100300019
ENDBIB 17 0 1277100300020
COMMON 1 3 1277100300021
EN-DUMMY 1277100300022
MEV 1277100300023
0.4 1277100300024
ENDCOMMON 3 0 1277100300025
DATA 5 6 1277100300026
ELEMENT MASS DATA DATA-ERR DECAY-FLAG 1277100300027
NO-DIM NO-DIM PC/FIS PER-CENT NO-DIM 1277100300028
40. 95. 5.44 3.0 1. 1277100300029
40. 97. 5.32 3.0 2. 1277100300030
42. 99. 6.03 2.0 3. 1277100300031
44. 103. 6.29 3.5 4. 1277100300032
53. 131. 3.05 4.0 5. 1277100300033
56. 140. 5.92 3.0 6. 1277100300034
ENDDATA 8 0 1277100300035
ENDSUBENT 34 0 1277100399999
SUBENT 12771004 20181203 14451277100400001
BIB 7 20 1277100400002
REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,FST) 1277100400003
FACILITY (REAC,1USAANL) ZPR-3 1277100400004
INC-SPECT Fast reactor spectrum. 1277100400005
Average of samples at 2 locations with average 1277100400006
fission energies of 446, 442, 293 keV. 1277100400007
MONITOR (94-PU-239(N,F)55-CS-137,CUM,FY,,FST) 1277100400008
ERR-ANALYS (DATA-ERR) The following sources of errors are 1277100400009
included: 1277100400010
. the precision of the mean of the gamma counts per 1277100400011
gram of fissionable mateial 1277100400012
. the detector calibration 1277100400013
. the nuclear constants of the fission products 1277100400014
(photon-to disintegration ratios and half-lives) 1277100400015
. the mass absorptions of the gamma rays by the foils 1277100400016
. the weights of the fissionable materials in the 1277100400017
foils 1277100400018
FLAG (1.) Calculated from 95Zr yield and measured 97Zr/95Zr 1277100400019
thermal-neutron fission-yield ratio. The 97Zr gamma 1277100400020
was subject of interference from a 239Pu gamma 1277100400021
STATUS (TABLE) Data from Nucl.Sci.Eng.54,263(1974), Table III 1277100400022
ENDBIB 20 0 1277100400023
COMMON 1 3 1277100400024
EN-DUMMY 1277100400025
MEV 1277100400026
0.4 1277100400027
ENDCOMMON 3 0 1277100400028
DATA 6 5 1277100400029
ELEMENT MASS DATA DATA-ERR DECAY-FLAG FLAG 1277100400030
NO-DIM NO-DIM PC/FIS PER-CENT NO-DIM NO-DIM 1277100400031
40. 95. 4.77 3.5 1. 1277100400032
40. 97. 4.86 3.0 1. 1277100400033
44. 103. 7.05 3.1 4. 1277100400034
53. 131. 4.08 3.1 5. 1277100400035
56. 140. 5.25 2.9 6. 1277100400036
ENDDATA 7 0 1277100400037
ENDSUBENT 36 0 1277100499999
SUBENT 12771005 20181203 14451277100500001
BIB 5 5 1277100500002
REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 1277100500003
FACILITY (REAC,1USAANL) Argonne thermal source reactor. 1277100500004
INC-SPECT Thermal reactor spectrum 1277100500005
MONITOR (92-U-235(N,F)55-CS-137,CUM,FY,,SPA) 1277100500006
STATUS (TABLE) Data from Nucl.Sci.Eng.54,263(1974), Table V 1277100500007
ENDBIB 5 0 1277100500008
COMMON 1 3 1277100500009
EN-DUMMY 1277100500010
EV 1277100500011
0.0253 1277100500012
ENDCOMMON 3 0 1277100500013
DATA 4 5 1277100500014
ELEMENT MASS DATA DECAY-FLAG 1277100500015
NO-DIM NO-DIM PC/FIS NO-DIM 1277100500016
40. 95. 6.53 1. 1277100500017
40. 97. 5.28 2. 1277100500018
44. 103. 2.95 4. 1277100500019
53. 131. 2.66 5. 1277100500020
56. 140. 5.81 6. 1277100500021
ENDDATA 7 0 1277100500022
ENDSUBENT 21 0 1277100599999
SUBENT 12771006 20181203 14451277100600001
BIB 5 5 1277100600002
REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,SPA) 1277100600003
FACILITY (REAC,1USAANL) Argonne thermal source reactor. 1277100600004
INC-SPECT Thermal reactor spectrum 1277100600005
MONITOR (94-PU-239(N,F)55-CS-137,CUM,FY,,SPA) 1277100600006
STATUS (TABLE) Data from Nucl.Sci.Eng.54,263(1974), Table V 1277100600007
ENDBIB 5 0 1277100600008
COMMON 1 3 1277100600009
EN-DUMMY 1277100600010
EV 1277100600011
0.0253 1277100600012
ENDCOMMON 3 0 1277100600013
DATA 4 5 1277100600014
ELEMENT MASS DATA DECAY-FLAG 1277100600015
NO-DIM NO-DIM PC/FIS NO-DIM 1277100600016
40. 95. 4.83 1. 1277100600017
40. 97. 4.98 2. 1277100600018
44. 103. 7.04 4. 1277100600019
53. 131. 3.95 5. 1277100600020
56. 140. 5.24 6. 1277100600021
ENDDATA 7 0 1277100600022
ENDSUBENT 21 0 1277100699999
ENDENTRY 6 0 1277199999999