ENTRY 33008 20210924 32033300800000001 SUBENT 33008001 20210924 32033300800100001 BIB 15 57 3300800100002 TITLE Fission Yields And Recoil Ranges Determined By A Ge(Li)3300800100003 detector 3300800100004 REFERENCE (C,69VIENNA,,741,1969) 3300800100005 (R,BARC/I-62,1970) the same data 3300800100006 AUTHOR (S.P.Dange,H.C.Jain,S.B.Manohar,K.Satyprakash, 3300800100007 M.V.Ramaniah,A.Ramaswami,K.Rengan) 3300800100008 INSTITUTE (3INDTRM) 3300800100009 FACILITY (REAC,3INDTRM) Apsara reactor and CIRUS reactor 3300800100010 INC-SOURCE (REAC) CIRUS neutron flux ~ 10.**13 n/cm**2/s. 3300800100011 Apsara neutron flux ~ 10.**12 n/cm**2/s. 3300800100012 SAMPLE (94-PU-239,ENR=0.95) 3300800100013 Plutonium containing about 95% 239Pu, enriched 3300800100014 uranium containing about 90% 235U and uranium-233 3300800100015 were purified chemically and used for target 3300800100016 preparation. The targets were prepared by 3300800100017 electroplating. The amount of fissionable material 3300800100018 on a target varied from 10 to 50 mu-g depending on the 3300800100019 length of irradiation and nuclides of interest. 3300800100020 DETECTOR (GELI) A 2 cm3-(4 cm2 area x 5 mm depl.) Ge(Li) 3300800100021 ANALYSIS The yields of nuclides in the thermal-neutron-induced 3300800100022 fission of 239Pu were determined relative to that of 3300800100023 235U. The nuclides determined in the work were not 3300800100024 sufficient for plotting mass-yield curve for 3300800100025 normalization. The ratio of 99Mo yields in 239Pu to 3300800100026 235U fission was used. 3300800100027 (DECAY) 3300800100028 METHOD (RINGR,GSPEC) 3300800100029 MONITOR (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) Data taken from 3300800100030 Meek et al., APED-5398-A(1968). 3300800100031 ((MONIT)94-PU-239(N,F)42-MO-99,CUM,FY,,MXW) 3300800100032 MONIT-REF (,M.E.Meek+,R,APED-5398,1968) 3300800100033 DECAY-DATA (36-KR-85-M,4.4HR,DG,151.2) 3300800100034 (38-SR-91,9.7HR,DG,555.6) 3300800100035 (40-ZR-95,65.D,DG,724.1) 3300800100036 (42-MO-99,66.HR,DG,140.7) 3300800100037 (44-RU-103,39.5D,DG,496.9) 3300800100038 (53-I-131,8.05D,DG,364.5) 3300800100039 (52-TE-132,77.7HR,DG,228.3) 3300800100040 (53-I-133-G,20.3HR,DG,529.8) 3300800100041 (54-XE-133-G,5.27D,DG,81.0) 3300800100042 (54-XE-135-G,9.2HR,DG,249.6) 3300800100043 (56-BA-139,82.9MIN,DG,165.8) 3300800100044 (56-BA-140,12.8D,DG,162.8,,DG,328.8,,DG,815.8) 3300800100045 (58-CE-141,32.5D,DG,145.4) 3300800100046 (57-LA-142,92.5MIN,DG,641.1) 3300800100047 (58-CE-143,33.HR,DG,292.9) 3300800100048 (58-CE-144,284.D,DG,133.6) 3300800100049 (60-ND-147,11.06D,DG,91.1) 3300800100050 STATUS (TABLE) Data from the tables of this paper 3300800100051 HISTORY (20060906C) Bhushan Patil 3300800100052 (20080826A) SD. Energy changed on 0.0253 from 0.025 eV 3300800100053 SAMPLE, MONITOR, decay-data were added to BIB section 3300800100054 and in Subent 002 added SPA in reaction code. 3300800100055 (20090914A) SD: ref. on BARC/I-62 was added. 3300800100056 (20100210A) SD: Year of publ. in BARC was corrected. 3300800100057 (20210924A) VS. Reference corrected cf. Memo CP-D/0979 3300800100058 Flag->MONIT1 values in 002. 3300800100059 ENDBIB 57 0 3300800100060 COMMON 1 3 3300800100061 EN-DUMMY 3300800100062 EV 3300800100063 0.0253 3300800100064 ENDCOMMON 3 0 3300800100065 ENDSUBENT 64 0 3300800199999 SUBENT 33008002 20210924 32033300800200001 BIB 3 5 3300800200002 REACTION (94-PU-239(N,F)ELEM/MASS,CUM,FY,,MXW) 3300800200003 ERR-ANALYS (DATA-ERR) The standard deviations calculated from the 3300800200004 experimental data. They do not include any 3300800200005 systematic errors. 3300800200006 HISTORY (20210924A) VS. Flag deleted. MONIT1 values added 3300800200007 ENDBIB 5 0 3300800200008 NOCOMMON 0 0 3300800200009 DATA 6 34 3300800200010 ELEMENT MASS ISOMER DATA DATA-ERR MONIT 3300800200011 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS PC/FIS 3300800200012 36. 85. 1. 0.60 0.02 5.61 3300800200013 36. 85. 1. 0.64 0.02 6.02 3300800200014 38. 91. 1.89 0.06 5.61 3300800200015 38. 91. 2.03 0.06 6.02 3300800200016 40. 95. 4.40 0.15 5.61 3300800200017 40. 95. 4.74 0.16 6.02 3300800200018 42. 99. 5.61 5.61 3300800200019 42. 99. 6.02 6.02 3300800200020 44. 103. 6.19 0.43 5.61 3300800200021 44. 103. 6.65 0.46 6.02 3300800200022 52. 132. 4.62 0.09 5.61 3300800200023 52. 132. 4.97 0.10 6.02 3300800200024 53. 131. 3.68 0.11 5.61 3300800200025 53. 131. 3.96 0.12 6.02 3300800200026 53. 133. 6.23 0.15 5.61 3300800200027 53. 133. 6.69 0.16 6.02 3300800200028 54. 133. 6.44 0.11 5.61 3300800200029 54. 133. 6.92 0.12 6.02 3300800200030 54. 135. 6.08 0.16 5.61 3300800200031 54. 135. 6.53 0.17 6.02 3300800200032 56. 139. 5.09 0.08 5.61 3300800200033 56. 139. 5.47 0.09 6.02 3300800200034 56. 140. 4.89 0.13 5.61 3300800200035 56. 140. 5.25 0.14 6.02 3300800200036 57. 142. 4.82 0.18 5.61 3300800200037 57. 142. 5.19 0.19 6.02 3300800200038 58. 141. 4.90 0.08 5.61 3300800200039 58. 141. 5.27 0.09 6.02 3300800200040 58. 143. 3.71 0.29 5.61 3300800200041 58. 143. 3.99 0.31 6.02 3300800200042 58. 144. 3.36 0.07 5.61 3300800200043 58. 144. 3.61 0.07 6.02 3300800200044 60. 147. 1.78 0.07 5.61 3300800200045 60. 147. 1.92 0.07 6.02 3300800200046 ENDDATA 36 0 3300800200047 ENDSUBENT 46 0 3300800299999 ENDENTRY 2 0 3300899999999