ENTRY 21624 20220203 23092162400000001 SUBENT 21624001 20220203 23092162400100001 BIB 14 38 2162400100002 TITLE Fission product yields in U-235 fission by fast 2162400100003 and thermal neutrons 2162400100004 AUTHOR (K.Debertin) 2162400100005 INSTITUTE (2GERPTB) 2162400100006 REFERENCE (S,INDC(NDS)-87,211,1978) Proceedings of 2162400100007 the 2nd IAEA Advisory Group Meeting on Fission 2162400100008 Product Nuclear Data, held at Petten, the 2162400100009 Netherlands, 5-9 September 1977, containing 2162400100010 the contributed papers to the review papers. 2162400100011 (S,IAEA-208,(2),261,1978) Less data given. 2162400100012 (P,INDC(GER)-19,82,1977) - Short descript. of experim. 2162400100013 FACILITY (REAC,2GERPTB) The FMRB reactor at Braunschweig,Germany2162400100014 INC-SOURCE (REAC) Reactor thermal neutrons. 2162400100015 (CF252) Californium-252 fission neutron source. 2162400100016 INC-SPECT 1. Thermal neutrons from a reactor. 2162400100017 2. Californium-252 fission neutron source. 2162400100018 SAMPLE Discs of 10 mm diameter and 0.2 mm thickness, 2162400100019 enriched to 93% of U-235. 2162400100020 METHOD (GSPEC) Six irradiations from 2 hr to 12 days - at Cf 2162400100021 spectrum; 3 sample irradiations at thermal spectrum; 2162400100022 cooling times between 1/2 hr and 100 days 2162400100023 DETECTOR (GELI ) Ge(Li) detector, volume 70 cc, resolution 2162400100024 2.2 keV at 1.33 MeV. 2162400100025 STATUS (TABLE) Tbl.I from INDC(NDS)-87,211 2162400100026 CORRECTION For dead time. 2162400100027 For pile-up. 2162400100028 For contributions from U-238 fission to the 2162400100029 fast fission yields. 2162400100030 All corrections due to gamma-ray self absorption, 2162400100031 efficiency calibration, gamma-ray emission 2162400100032 probabilities and to real summing cancel when 2162400100033 forming the yield ratios. 2162400100034 ERR-ANALYS (DATA-ERR) The uncertainties quoted are mainly 2162400100035 statistical and relate to a confidence level of 68%. 2162400100036 HISTORY (19800801C) CN. 2162400100037 (20151212U) SD:Updated to new date formats,lower case. 2162400100038 BIB update; type or refs was changed (R -> S). 2162400100039 (20220203U) SD: Ref. INDC(GER)-19,82 added. 2162400100040 ENDBIB 38 0 2162400100041 COMMON 2 3 2162400100042 EN-NRM EN-DUMMY 2162400100043 EV MEV 2162400100044 2.5300E-02 1.5 2162400100045 ENDCOMMON 3 0 2162400100046 ENDSUBENT 45 0 2162400199999 SUBENT 21624002 20151212 22462162400200001 BIB 6 17 2162400200002 REACTION ((92-U-235(N,F)ELEM/MASS,CUM,FY,,FIS)/ 2162400200003 (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW)) 2162400200004 MONITOR ((92-U-235(N,F)40-ZR-95,CUM,FY,,FIS)/ 2162400200005 (92-U-235(N,F)40-ZR-95,CUM,FY)) 2162400200006 COMMENT The ratios of the observed relative cumulative 2162400200007 fission yields for Cf-252 and thermal neutrons 2162400200008 were normalized to the evaluated chain yield 2162400200009 ratio for zirconium-95 given by Meek and Rider 2162400200010 using reactor spectrum and thermal neutrons. 2162400200011 FLAG (1.) Normalization point to the Meek and Rider file. 2162400200012 (2.) Data point also includes contribution from 2162400200013 the nucleus with element/mass = A/(Z+1). 2162400200014 (3.) data point also includes contribution from 2162400200015 the metastable state of the nucleus with 2162400200016 element/mass = A/(Z+1). 2162400200017 MONIT-REF (,M.E.Meek+,R,NEDO-12154-1,1974) 2162400200018 HISTORY (20151212A) SD: MONITOR was added. 2162400200019 ENDBIB 17 0 2162400200020 COMMON 4 3 2162400200021 ELEM-NRM MASS-NRM MONIT MONIT-ERR 2162400200022 NO-DIM NO-DIM NO-DIM NO-DIM 2162400200023 40. 95. 0.990 0.012 2162400200024 ENDCOMMON 3 0 2162400200025 DATA 5 23 2162400200026 ELEMENT MASS DATA DATA-ERR FLAG 2162400200027 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 2162400200028 36. 87. 0.94 0.04 2162400200029 36. 88. 1.010 0.015 2. 2162400200030 38. 91. 0.922 0.01 3. 2162400200031 38. 92. 0.966 0.01 2. 2162400200032 39. 93. 0.95 0.018 2162400200033 40. 95. 0.990 0.010 1. 2162400200034 40. 97. 1.016 0.007 2. 2162400200035 42. 99. 1.013 0.016 2162400200036 44. 103. 1.099 0.007 2162400200037 45. 105. 1.264 0.021 2162400200038 51. 127. 2.95 0.09 2162400200039 51. 129. 1.54 0.10 2162400200040 52. 132. 1.136 0.008 2. 2162400200041 52. 134. 0.93 0.04 2162400200042 53. 131. 1.258 0.019 2162400200043 53. 133. 1.000 0.008 2162400200044 53. 135. 1.013 0.008 2. 2162400200045 55. 138. 0.94 0.03 2162400200046 56. 140. 0.960 0.009 2. 2162400200047 57. 142. 0.95 0.04 2162400200048 58. 143. 0.892 0.008 2162400200049 60. 147. 0.97 0.05 2162400200050 61. 151. 1.26 0.07 2162400200051 ENDDATA 25 0 2162400200052 ENDSUBENT 51 0 2162400299999 ENDENTRY 2 0 2162499999999