ENTRY 23812 20210625 23012381200000001 SUBENT 23812001 20210625 23012381200100001 BIB 6 8 2381200100002 TITLE The determination of the capture to fission ratio and 2381200100003 the fission product yields of fissile materials 2381200100004 irradiated in the Dounreay fast reactor 2381200100005 AUTHOR (E.A.C.Crouch) 2381200100006 REFERENCE (C,71CANT,,147,1971) 2381200100007 INSTITUTE (2UK HAR) 2381200100008 FACILITY (REAC,2UK DOU) Dounreay fast reactor DFR. 2381200100009 HISTORY (20210625C) M.M. 2381200100010 ENDBIB 8 0 2381200100011 COMMON 1 3 2381200100012 EN-DUMMY 2381200100013 MEV 2381200100014 1.5 2381200100015 ENDCOMMON 3 0 2381200100016 ENDSUBENT 15 0 2381200199999 SUBENT 23812002 20210625 23012381200200001 BIB 6 20 2381200200002 REACTION (94-PU-239(N,ABS),,ALF,,SPA) 2381200200003 SAMPLE Pu-239 electromagnetically separated, Pu-240 content 2381200200004 less than 0.025 % or Pu241 < 0.00025%. 2381200200005 10 ug samples were spaced radially out from DFR core. 2381200200006 METHOD Irradiation time 18 days. Pu-240 content in samples 2381200200007 nearest the core was only .09% after irradiation. 2381200200008 FLAG (1.) Position 1 2381200200009 (2.) Position 2 2381200200010 (3.) Position 3 2381200200011 (4.) Position 4. 2381200200012 (5.) Position 5. 2381200200013 (6.) Run 1 2381200200014 (7.) Run 2 2381200200015 (8.) Run 3 2381200200016 (9.) Run 4 2381200200017 . There is no detailed explanation of position of 2381200200018 sample, distances are not given. 2381200200019 ERR-ANALYS (DATA-ERR,12.) Absolute accuracy was not better than 2381200200020 +-12.%. 2381200200021 STATUS (TABLE) Table 1 of Conf.Proc.71CANT,p.147,1971 2381200200022 ENDBIB 20 0 2381200200023 NOCOMMON 0 0 2381200200024 DATA 3 15 2381200200025 DATA FLAG FLAG 2381200200026 NO-DIM NO-DIM NO-DIM 2381200200027 0.11 1. 6. 2381200200028 0.11 1. 7. 2381200200029 0.12 1. 8. 2381200200030 0.23 2. 6. 2381200200031 0.19 2. 7. 2381200200032 0.23 2. 8. 2381200200033 0.21 2. 9. 2381200200034 0.45 3. 6. 2381200200035 0.45 3. 7. 2381200200036 0.46 3. 8. 2381200200037 0.50 4. 7. 2381200200038 0.51 4. 8. 2381200200039 0.73 5. 6. 2381200200040 0.72 5. 7. 2381200200041 0.71 5. 8. 2381200200042 ENDDATA 17 0 2381200200043 ENDSUBENT 42 0 2381200299999 SUBENT 23812003 20210625 23012381200300001 BIB 5 8 2381200300002 REACTION (92-U-235(N,ABS),,ALF,,SPA) 2381200300003 SAMPLE Two samples of ~30 mg 235UO(2). 2381200300004 238U content ~7.%. 2381200300005 Some ug of 239Pu were produced during irradiations. 2381200300006 METHOD Irradiation time 3 months. 2381200300007 FLAG (1.) Sample 1. 2381200300008 (2.) Sample 2. 2381200300009 STATUS (TABLE) Table 2 of Conf.Proc.71CANT,p.147,1971 2381200300010 ENDBIB 8 0 2381200300011 NOCOMMON 0 0 2381200300012 DATA 2 2 2381200300013 DATA FLAG 2381200300014 NO-DIM NO-DIM 2381200300015 0.18 1. 2381200300016 0.34 2. 2381200300017 ENDDATA 4 0 2381200300018 ENDSUBENT 17 0 2381200399999 SUBENT 23812004 20210625 23012381200400001 BIB 5 7 2381200400002 REACTION (92-U-238(N,ABS),,ALF,,SPA) 2381200400003 SAMPLE Two samples of ~30 mg 235UO(2). 2381200400004 238U content ~7.%. 2381200400005 Some ug of 239Pu were produced during irradiations. 2381200400006 METHOD Irradiation time 3 months. 2381200400007 FLAG (2.) Sample 2. 2381200400008 STATUS (TABLE) Table 2 of Conf.Proc.71CANT,p.147,1971 2381200400009 ENDBIB 7 0 2381200400010 NOCOMMON 0 0 2381200400011 DATA 2 1 2381200400012 DATA FLAG 2381200400013 NO-DIM NO-DIM 2381200400014 34.13 2. 2381200400015 ENDDATA 3 0 2381200400016 ENDSUBENT 15 0 2381200499999 SUBENT 23812005 20210625 23012381200500001 BIB 5 7 2381200500002 REACTION (94-PU-239(N,ABS),,ALF,,SPA) 2381200500003 SAMPLE Two samples of ~30 mg 235UO(2). 2381200500004 238U content ~7.%. 2381200500005 Some ug of 239Pu were produced during irradiations. 2381200500006 METHOD Irradiation time 3 months. 2381200500007 FLAG (2.) Sample 2. 2381200500008 STATUS (TABLE) Table 2 of Conf.Proc.71CANT,p.147,1971 2381200500009 ENDBIB 7 0 2381200500010 NOCOMMON 0 0 2381200500011 DATA 2 1 2381200500012 DATA FLAG 2381200500013 NO-DIM NO-DIM 2381200500014 0.597 2. 2381200500015 ENDDATA 3 0 2381200500016 ENDSUBENT 15 0 2381200599999 SUBENT 23812006 20210625 23012381200600001 BIB 7 16 2381200600002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 2381200600003 INC-SPECT The energy of neutrons was different in the two 2381200600004 irradiations, certainly not "fission spectrum" - 2381200600005 comment of authors in the article. 2381200600006 MONITOR (92-U-235(N,F)60-ND-143,CUM,FY,,SPA) 2381200600007 Nd-143 yield was assumed arbitrarily. 2381200600008 SAMPLE Two samples of ~30 mg 235UO(2). 2381200600009 238U content ~7.%. 2381200600010 Some ug of 239Pu were produced during irradiations. 2381200600011 METHOD Irradiation time 3 months. 2381200600012 (CHSEP) 2381200600013 FLAG (1.) Sample 1. 2381200600014 (2.) Sample 2. 2381200600015 (3.) Cs-134 is a capture product, its yield chould be 2381200600016 added to that of Cs-133 from which it is formed. 2381200600017 STATUS (TABLE) Table 3 of Conf.Proc.71CANT,p.147,1971 2381200600018 ENDBIB 16 0 2381200600019 COMMON 1 3 2381200600020 MONIT 2381200600021 PC/FIS 2381200600022 5.90 2381200600023 ENDCOMMON 3 0 2381200600024 DATA 5 22 2381200600025 ELEMENT MASS DATA FLAG FLAG 2381200600026 NO-DIM NO-DIM PC/FIS NO-DIM NO-DIM 2381200600027 37. 85. 1.36 1. 2381200600028 37. 85. 1.32 2. 2381200600029 37. 87. 2.45 1. 2381200600030 37. 87. 2.42 2. 2381200600031 55. 133. 6.50 1. 2381200600032 55. 133. 6.23 2. 2381200600033 55. 134. 0.035 1. 3. 2381200600034 55. 134. 0.264 2. 3. 2381200600035 55. 135. 6.17 1. 2381200600036 55. 135. 5.80 2. 2381200600037 55. 137. 5.76 1. 2381200600038 55. 137. 5.46 2. 2381200600039 60. 144. 6.03 1. 2381200600040 60. 144. 5.56 2. 2381200600041 60. 145. 3.84 1. 2381200600042 60. 145. 3.82 2. 2381200600043 60. 146. 2.95 1. 2381200600044 60. 146. 2.94 2. 2381200600045 60. 148. 1.69 1. 2381200600046 60. 148. 1.62 2. 2381200600047 60. 150. 0.71 1. 2381200600048 60. 150. 0.63 2. 2381200600049 ENDDATA 24 0 2381200600050 ENDSUBENT 49 0 2381200699999 ENDENTRY 6 0 2381299999999