ENTRY 30566 20020322 00003056600000001 SUBENT 30566001 20020322 00003056600100001 BIB 14 66 3056600100002 TITLE Fission yields induced by reactor neutrons. 3056600100003 REFERENCE (J,NSF,17,107,198006) experimental details and U-235 3056600100004 data 3056600100005 AUTHOR (V.K-C.Cheng,J-H.Jean,M-H.Yang) last author only for 3056600100006 U-235 yields 3056600100007 INSTITUTE (3CHFTHU) 3056600100008 FACILITY (REAC,3CHFTHU). THOR, open pool type. 3056600100009 INC-SPECT Reactor neutron spectrum, neutron flux = 3x10**12 3056600100010 n/cm2/sec. 3056600100011 - Comment: for Th-232 (fission threshold 1 MeV) the 3056600100012 fission neutron part of the spectrum is relevant. 3056600100013 Comment by compiler: The neutron energy is not given 3056600100014 explicitely but the reactor type and the neutrons being3056600100015 referred to as 'reactor neutrons' indicate that the 3056600100016 spectrum is that of a thermal reactor. However, (see 3056600100017 subentry 3) the U-235 yields are normalized to the 3056600100018 Ce-140 fast fission yield of Lisman et al, and in the 3056600100019 publication, all yields are compared to fast fission 3056600100020 yields by other authors. At least the normalization and3056600100021 the neutron energy should be checked before using 3056600100022 absolute values of these yields. 3056600100023 METHOD (FPGAM) 3056600100024 DETECTOR (GELI) 3056600100025 CORRECTION no information 3056600100026 ERR-ANALYS Only random error given as one standard deviation for 3056600100027 the average of individual determintions. 3056600100028 DECAY-DATA No half lives given. 3056600100029 ((1.)36-KR-85-M,,DG,151.2,0.746) 3056600100030 ((2.)36-KR-88,,DG,196.3,0.263) 3056600100031 ((3.)38-SR-91,,DG,749.7,0.244) 3056600100032 ((3.)39-Y-91-M,,DG,555.6,0.560) 3056600100033 ((4.)38-SR-92,,DG,1383.9,0.900) 3056600100034 ((5.)39-Y-93,,DG,266.9,0.0695) 3056600100035 ((6.)40-ZR-95,,DG,724.3,0.444) 3056600100036 ((6.)41-NB-95-G,,DG,766.2,1.0) 3056600100037 ((7.)40-ZR-97,,DG,743.3,0.946) 3056600100038 ((7.)41-NB-97-G,,DG,658.1,1.0) 3056600100039 ((8.)42-MO-99,,DG,181.9,0.060) 3056600100040 ((8.)43-TC-99-M,,DG,140.5,0.8896) 3056600100041 ((9.)44-RU-103,,DG,497.1,0.8935) 3056600100042 ((10.)44-RU-105,,DG,724.2,0.4728) 3056600100043 ((11.)53-I-131,,DG,364.5,0.824) 3056600100044 ((12.)52-TE-132,,DG,228.2,0.880) 3056600100045 ((12.)53-I-132,,DG,772.7,0.762) 3056600100046 ((13.)53-I-133-G,,DG,529.9,0.873) 3056600100047 ((13.)54-XE-133-G,,DG,81.0,0.3714) 3056600100048 ((14.)53-I-134-G,,DG,884.1,0.6525) 3056600100049 ((15.)53-I-135,,DG,1260.5,0.3028) 3056600100050 ((16.)55-CS-137,,DG,661.6,0.851) 3056600100051 ((17.)56-BA-139,,DG,165.9,0.188) 3056600100052 ((18.)58-CE-141,,DG,145.4,0.481) 3056600100053 ((19.)57-LA-142,,DG,641.2,0.490) 3056600100054 ((20.)58-CE-143,,DG,293.3,0.413) 3056600100055 ((21.)58-CE-144,,DG,133.5,0.111) 3056600100056 ((22.)60-ND-147,,DG,91.0,0.272) 3056600100057 ((23.)60-ND-149,,DG,211.3,0.273) 3056600100058 DECAY-MON No half lives given 3056600100059 (56-BA-140,,DG,537.3,0.240) 3056600100060 (57-LA-140,,DG,487.0,0.453) 3056600100061 COMMENT by compiler: In cases where parent and daughter 3056600100062 products are used in the data analyses and are given in3056600100063 the tables of the respective publications, it is 3056600100064 assumed that the yield is given for the parent product,3056600100065 which is therefore also identified by MASS and ELEMENT 3056600100066 in the DATA sections of subentries 2 and 3. 3056600100067 HISTORY (20010706C) ML. 3056600100068 ENDBIB 66 0 3056600100069 NOCOMMON 0 0 3056600100070 ENDSUBENT 69 0 3056600199999 SUBENT 30566002 20020322 00003056600200001 BIB 8 17 3056600200002 TITLE Fission yield of thorium-232 induced by reactor 3056600200003 neutrons. 3056600200004 REFERENCE (J,NSF,17,96,198006) Th-232 data 3056600200005 REACTION (90-TH-232(N,F)ELEM/MASS,CUM,FY,,SPA) 3056600200006 MONITOR (90-TH-232(N,F)56-BA-140,CUM,FY,,SPA) analysis of 3056600200007 Ba-140 + La-140 for yield derivation; result is the 3056600200008 average of 7 determinations. 3056600200009 MONIT-REF (,K.BRESESTI+,J,JIN,29,1189,196709) The value used 3056600200010 is not their measurement result (first column) but 3056600200011 the "preferred value" in the last column of Table 4. 3056600200012 FLAG (1.) total Kr-85 yield 3056600200013 (2.) analysis of Zr-95 + Nb-95g for yield derivation 3056600200014 (3.) analysis of Zr-97 + Nb-97g for yield derivation 3056600200015 (4.) analysis of Mo-99 + Tc-99m for yield derivation 3056600200016 (5.) analysis of Te-132 + I-132m+g for yield derivation3056600200017 MISC-COL Number of determinations 3056600200018 STATUS Data taken from Table 1 of Nucl.Sci.J.17(1980)96. 3056600200019 ENDBIB 17 0 3056600200020 COMMON 2 3 3056600200021 EN-DUMMY MONIT 3056600200022 MEV PC/FIS 3056600200023 1. 7.64 3056600200024 ENDCOMMON 3 0 3056600200025 DATA 8 20 3056600200026 MASS ELEMENT ISOMER DATA DATA-ERR FLAG 3056600200027 DECAY-FLAG MISC 3056600200028 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3056600200029 NO-DIM NO-DIM 3056600200030 85. 36. 3.72 0.10 1. 3056600200031 1. 4. 3056600200032 88. 36. 6.57 0.11 3056600200033 2. 4. 3056600200034 91. 38. 7.52 0.09 3056600200035 3. 7. 3056600200036 92. 38. 6.85 0.15 3056600200037 4. 4. 3056600200038 93. 39. 7.66 0.15 3056600200039 5. 4. 3056600200040 95. 40. 6.09 0.09 2. 3056600200041 6. 7. 3056600200042 97. 40. 4.99 0.09 3. 3056600200043 7. 6. 3056600200044 99. 42. 2.68 0.08 4. 3056600200045 8. 5. 3056600200046 103. 44. 0.150 0.008 3056600200047 9. 4. 3056600200048 131. 53. 1.89 0.08 3056600200049 11. 5. 3056600200050 132. 52. 2.96 0.06 5. 3056600200051 12. 7. 3056600200052 133. 53. 0. 3.30 0.18 3056600200053 13. 3. 3056600200054 134. 53. 0. 5.26 0.17 3056600200055 14. 2. 3056600200056 135. 53. 4.58 0.09 3056600200057 15. 4. 3056600200058 137. 55. 6.39 0.05 3056600200059 16. 4. 3056600200060 139. 56. 6.14 0.10 3056600200061 17. 4. 3056600200062 141. 58. 6.86 0.15 3056600200063 18. 5. 3056600200064 142. 57. 7.69 0.16 3056600200065 19. 4. 3056600200066 143. 58. 6.56 0.14 3056600200067 20. 6. 3056600200068 149. 60. 1.32 0.12 3056600200069 23. 2. 3056600200070 ENDDATA 44 0 3056600200071 ENDSUBENT 70 0 3056600299999 SUBENT 30566003 20020322 00003056600300001 BIB 8 25 3056600300002 TITLE Fission yield of uranium-235 induced by reactor 3056600300003 neutrons. 3056600300004 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 3056600300005 MONITOR (92-U-235(N,F)56-BA-140,CUM,FY,,SPA) analysis of 3056600300006 Ba-140 + La-140 for yield derivation; result is the 3056600300007 average of 8 determinations. 3056600300008 MONIT-REF (13270017,F.L.LISMAN+,J,NSE,42,191,197011) note: the 3056600300009 fast fission yield of Ce-140 given in table XIII of 3056600300010 this publication is used for normalization of the, 3056600300011 presumably thermal, yields given in the DATA section. 3056600300012 FLAG (1.) analysis of Zr-95 + Nb-95g for yield derivation 3056600300013 (2.) analysis of Zr-97 + Nb-97g for yield derivation 3056600300014 (3.) analysis of Mo-99 + Tc-99m for yield derivation 3056600300015 (4.) analysis of Te-132 + I-132m+g for yield derivation3056600300016 (5.) analysis of I-133 + Xe-133g for yield derivation 3056600300017 (6.) analysis of I-135 + Xe-135g for yield derivation 3056600300018 MISC-COL Number of determinations 3056600300019 COMMENT by compiler: as noted above (subentry 1, INC-SPEC, and 3056600300020 this subentry, MONIT-REF), the authors have used fast 3056600300021 neutron induced U-235 fission yields for normalizing 3056600300022 their relative yields and for comparing their 3056600300023 measurement results, although their measurements have 3056600300024 presumably be made in a thermal reactor. This should be3056600300025 taken into consideration when using these data. 3056600300026 STATUS Data taken from Table 2 of Nucl.Sci.J.17(1980)107. 3056600300027 ENDBIB 25 0 3056600300028 COMMON 3 3 3056600300029 EN-DUMMY MONIT MONIT-ERR 3056600300030 EV PC/FIS PC/FIS 3056600300031 0.0253 6.21 0.11 3056600300032 ENDCOMMON 3 0 3056600300033 DATA 8 23 3056600300034 MASS ELEMENT ISOMER DATA DATA-ERR FLAG 3056600300035 DECAY-FLAG MISC 3056600300036 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3056600300037 NO-DIM NO-DIM 3056600300038 85. 36. 1. 1.435 0.008 3056600300039 1. 6. 3056600300040 88. 36. 3.350 0.026 3056600300041 2. 3. 3056600300042 91. 38. 6.07 0.046 3056600300043 3. 6. 3056600300044 92. 38. 6.11 0.026 3056600300045 4. 5. 3056600300046 93. 39. 5.71 0.085 3056600300047 5. 5. 3056600300048 95. 40. 6.47 0.09 1. 3056600300049 6. 4. 3056600300050 97. 40. 6.49 0.27 2. 3056600300051 7. 2. 3056600300052 99. 42. 6.10 0.03 3. 3056600300053 8. 6. 3056600300054 103. 44. 3.34 0.03 3056600300055 9. 6. 3056600300056 105. 44. 1.56 0.06 3056600300057 10. 5. 3056600300058 131. 53. 3.24 0.09 3056600300059 11. 5. 3056600300060 132. 52. 4.70 0.05 4. 3056600300061 12. 5. 3056600300062 133. 53. 0. 6.18 0.09 5. 3056600300063 13. 5. 3056600300064 134. 53. 0. 7.58 0.15 3056600300065 14. 5. 3056600300066 135. 53. 6.91 0.04 6. 3056600300067 15. 8. 3056600300068 137. 55. 6.32 0.05 3056600300069 16. 4. 3056600300070 139. 56. 6.55 0.08 3056600300071 17. 3. 3056600300072 141. 58. 6.49 0.04 3056600300073 18. 7. 3056600300074 142. 57. 5.93 0.06 3056600300075 19. 6. 3056600300076 143. 58. 5.83 0.05 3056600300077 20. 6. 3056600300078 144. 58. 5.60 0.16 3056600300079 21. 5. 3056600300080 147. 60. 2.39 0.07 3056600300081 22. 8. 3056600300082 149. 60. 0.99 0.04 3056600300083 23. 2. 3056600300084 ENDDATA 50 0 3056600300085 ENDSUBENT 84 0 3056600399999 ENDENTRY 3 0 3056699999999