ENTRY 22792 20180318 22702279200000001
SUBENT 22792001 20180318 22702279200100001
BIB 11 16 2279200100002
TITLE Th-232 fission yields determination by gamma-ray 2279200100003
spectroscopy on unseparated samples 2279200100004
AUTHOR (M.Brasca, A.Cessna, V.Sangiust, M.Terrani) 2279200100005
INSTITUTE (2ITYMIP) CESNEF, Politecnico di Milano 2279200100006
REFERENCE (J,EN,20,691,1973) Main ref., data tables are given 2279200100007
FACILITY (REAC,2ITYMIP) L54 reactor at CESNEF 2279200100008
METHOD (GSPEC) Gamma ray spectroscopy 2279200100009
DETECTOR (GELI) The 35 cm3 coaxial detector, resolution 2279200100010
2.5 keV at 1330 keV gamma energy 2279200100011
ANALYSIS (DECAY) Fission fragments were determined by energy 2279200100012
of gamma rays and half-lives of the fission products 2279200100013
CORRECTION .Correction was made for self-absorption of gammas 2279200100014
ERR-ANALYS (DATA-ERR) Standard uncertainty 2279200100015
HISTORY (20091126C) S.M. 2279200100016
(20180318A) SD: REACTION code corrected in Subents 2279200100017
002-004. Data were re-compiled in Subent 004. 2279200100018
ENDBIB 16 0 2279200100019
NOCOMMON 0 0 2279200100020
ENDSUBENT 19 0 2279200199999
SUBENT 22792002 20180318 22702279200200001
BIB 6 10 2279200200002
REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 2279200200003
INC-SOURCE (THCOL) Thermal column of the L54 reactor 2279200200004
INC-SPECT .Thermal Maxwellian 2279200200005
SAMPLE .Coin-shaped sample of Aluminum-Uranium alloy, 3% of 2279200200006
uranium, 15 mm diameter, thickness aprx. 31 mg/cm2 2279200200007
wrapped in a 5 mg/cm2 thick aluminum foil 2279200200008
(92-U-235,ENR=0.93) 2279200200009
STATUS (TABLE) Table 4 of Energ.Nucl.20(1973)691 2279200200010
HISTORY (20180318A) SD: SF5=SEC -> CUM in REACTION code 2279200200011
according to MEMO CP-D/929. 2279200200012
ENDBIB 10 0 2279200200013
COMMON 1 3 2279200200014
EN-DUMMY 2279200200015
EV 2279200200016
2.5 E-02 2279200200017
ENDCOMMON 3 0 2279200200018
DATA 5 12 2279200200019
ELEMENT MASS ISOMER DATA DATA-ERR 2279200200020
NO-DIM NO-DIM NO-DIM PC/FIS PER-CENT 2279200200021
36. 85. 1. 1.30 2.3 2279200200022
36. 88. 3.60 0.5 2279200200023
38. 91. 5.71 0.5 2279200200024
38. 92. 5.92 0.5 2279200200025
40. 97. 5.85 0.5 2279200200026
52. 132. 4.15 1.5 2279200200027
53. 131. 2.79 1.4 2279200200028
53. 133. 6.73 0.6 2279200200029
53. 135. 6.23 2.0 2279200200030
56. 140. 6.29 0.5 2279200200031
57. 142. 5.86 0.5 2279200200032
58. 143. 5.80 0.5 2279200200033
ENDDATA 14 0 2279200200034
ENDSUBENT 33 0 2279200299999
SUBENT 22792003 20180318 22702279200300001
BIB 8 17 2279200300002
REACTION ((90-TH-232(N,F)ELEM/MASS,CUM,FY,,FST)/ 2279200300003
(92-U-235(N,F)56-BA-140,CUM,FY,,FST)) 2279200300004
METHOD (FNB) Neutron beam filtered by 800 mg/cm2 cadmium 2279200300005
and 600 mg/cm2 natural boron filters in order to 2279200300006
minimize 233Th and 233Pa activities arising from 2279200300007
232Th neutron capture 2279200300008
INC-SOURCE (REAC) Reactor core spectrum of L54 reactor 2279200300009
INC-SPECT .Neutron spectrum similar to that of fission 2279200300010
SAMPLE .Thorium oxide pellet 300 mg/cm2 thick, 15 mm diameter 2279200300011
wrapped in a 5 mg/cm2 thick aluminum foil 2279200300012
FLAG (1.) Obtained from 39-Y-91-m, gamma ray energy 2279200300013
555.57 keV 2279200300014
(2.) Obtained with the help of gamma energy 1131.6 keV 2279200300015
(3.) Obtained with the help of gamma energy 1260.45 keV2279200300016
STATUS (TABLE) Table 4 of Energ.Nucl.20(1973)691 2279200300017
HISTORY (20180318A) SD: SF5=SEC -> CUM in REACTION code 2279200300018
according to MEMO CP-D/929. 2279200300019
ENDBIB 17 0 2279200300020
COMMON 1 3 2279200300021
EN-DUMMY 2279200300022
MEV 2279200300023
1. 2279200300024
ENDCOMMON 3 0 2279200300025
DATA 6 14 2279200300026
ELEMENT MASS ISOMER DATA DATA-ERR FLAG 2279200300027
NO-DIM NO-DIM NO-DIM NO-DIM PER-CENT NO-DIM 2279200300028
36. 85. 1. 1.92 5.5 2279200300029
36. 88. 1.11 3.2 2279200300030
38. 91. 0.723 6.4 2279200300031
38. 91. 0.714 2.7 1. 2279200300032
38. 92. 0.673 4.1 2279200300033
40. 97. 0.446 3.6 2279200300034
52. 132. 0.360 7.8 2279200300035
53. 131. 0.400 5.0 2279200300036
53. 133. 0.331 7.0 2279200300037
53. 135. 0.553 4.0 2. 2279200300038
53. 135. 0.577 3.2 3. 2279200300039
56. 140. 0.718 5.0 2279200300040
57. 142. 0.666 4.5 2279200300041
58. 143. 0.696 6.6 2279200300042
ENDDATA 16 0 2279200300043
ENDSUBENT 42 0 2279200399999
SUBENT 22792004 20180318 22702279200400001
BIB 10 21 2279200400002
REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY,,FST) 2279200400003
METHOD (FNB) Neutron beam filtered by 800 mg/cm2 cadmium 2279200400004
and 600 mg/cm2 natural boron filters in order to 2279200400005
minimize 233Th and 233Pa activities arising from 2279200400006
232Th neutron capture 2279200400007
INC-SOURCE (REAC) Reactor core spectrum of L54 reactor 2279200400008
INC-SPECT .Neutron spectrum similar to that of fission 2279200400009
MONITOR (90-TH-232(N,F)56-BA-140,SEC,FY,,FST) 2279200400010
MONIT-REF (,M.E.Meek+,R,NEDO-12154,1972) 2279200400011
SAMPLE .Thorium oxide pellet 300 mg/cm2 thick, 15 mm diam. 2279200400012
wrapped in a 5 mg/cm2 thick aluminum foil 2279200400013
FLAG (1.) Obtained from 39-Y-91-m, gamma ray energy 2279200400014
555.57 keV 2279200400015
(2.) Obtained with the help of gamma energy 1131.6 keV 2279200400016
(3.) Obtained with the help of gamma energy 1260.45 keV2279200400017
STATUS (TABLE) Table 4 of Energ.Nucl.20(1973)691 2279200400018
(DEP,22792003) 2279200400019
HISTORY (20180318A) SD: SF5=SEC -> CUM in REACTION code 2279200400020
according to MEMO CP-D/929. Data were re-compiled 2279200400021
from Tbl. 5 (instead of Tb.4. In Tbl.4 relative yields 2279200400022
presented; in Tbl.5 - absolute yields presented). 2279200400023
ENDBIB 21 0 2279200400024
COMMON 2 3 2279200400025
EN-DUMMY MONIT 2279200400026
MEV PC/FIS 2279200400027
1. 7.807 2279200400028
ENDCOMMON 3 0 2279200400029
DATA 6 13 2279200400030
ELEMENT MASS ISOMER DATA DATA-ERR FLAG 2279200400031
NO-DIM NO-DIM NO-DIM PC/FIS PER-CENT NO-DIM 2279200400032
36. 85. 1. 4.32 8.4 2279200400033
36. 88. 6.91 6.7 2279200400034
38. 91. 7.13 8.7 2279200400035
38. 91. 7.05 6.4 1. 2279200400036
38. 92. 6.87 7.1 2279200400037
40. 97. 4.51 6.9 2279200400038
52. 132. 2.57 10. 2279200400039
53. 131. 1.93 7.8 2279200400040
53. 133. 3.86 9.1 2279200400041
53. 135. 5.96 7.4 2. 2279200400042
53. 135. 6.20 7.0 3. 2279200400043
57. 142. 6.74 7.4 2279200400044
58. 143. 6.82 8.8 2279200400045
ENDDATA 15 0 2279200400046
ENDSUBENT 45 0 2279200499999
ENDENTRY 4 0 2279299999999