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