ENTRY 32658 20060619 31213265800000001 SUBENT 32658001 20060619 31213265800100001 BIB 15 34 3265800100002 TITLE Fission product yield from 11.3MeV neutron-induced 3265800100003 Fission of U-238 3265800100004 AUTHOR (Ze Li, Xiuzhi Wang, Kexin Jing, Anzhi Cui,Daming Liu, 3265800100005 Daming Li,Yonghui Liu, Xueliang Li,Conggui Liu, 3265800100006 Shuxing Su,Peijia Tang,Tahai Chih,Shulang Zhang, 3265800100007 Shengdong Zhang,Jinru Guo) 3265800100008 INSTITUTE (3CPRAEP) 3265800100009 REFERENCE (J,RCA,64,95,1994) 3265800100010 SAMPLE Natural metallic uranium about 2g, disk shaped foils 3265800100011 of 16 mm diameter, sealed in 0.2mm aluminium foil. 3265800100012 MONITOR Absolute fission rate was monitored with a double 3265800100013 fission chamber 3265800100014 DETECTOR (FISCH) 3265800100015 (GELI) 3265800100016 (HPGE) 3265800100017 FACILITY (VDGT,3CPRAEP) 3265800100018 INC-SOURCE (D-D) 3265800100019 METHOD (FISCT) 3265800100020 (TOF)Measured the neutron spectrum 3265800100021 COMMENT By author. 59.4% of the yields in the light mass group 3265800100022 and 76.4% of the yields in the heavy mass group have 3265800100023 been measured. Together with interpolated and 3265800100024 extrapolated chain yoelds, the sums fo yield in the 3265800100025 light and heavy mass group are 100.8 and 99.5% 3265800100026 CORRECTION The following correction were made: 3265800100027 .Gamma-ray self-absorption correction. 3265800100028 .Cascade coincident losses. 3265800100029 .The pile-up losees in the counting system 3265800100030 .The influence of the background neutrons. 3265800100031 ERR-ANALYS (DATA-ERR) Uncertaintied were obtained by considertion 3265800100032 of all known sources of random error with the usual 3265800100033 rules of error propagation. 3265800100034 STATUS (TABLE) Data from the table 1 of this paper 3265800100035 HISTORY (20060619C) Compiled by Yu Hongwei 3265800100036 ENDBIB 34 0 3265800100037 COMMON 1 3 3265800100038 EN 3265800100039 MEV 3265800100040 11.3 3265800100041 ENDCOMMON 3 0 3265800100042 ENDSUBENT 41 0 3265800199999 SUBENT 32658002 20060619 31213265800200001 BIB 2 2 3265800200002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 3265800200003 METHOD (FPGAM)Direct gamma-ray spectroscopy. 3265800200004 ENDBIB 2 0 3265800200005 NOCOMMON 0 0 3265800200006 DATA 4 31 3265800200007 ELEMENT MASS DATA DATA-ERR 3265800200008 NO-DIM NO-DIM PC/FIS PC/FIS 3265800200009 36. 87. 1.77 0.13 3265800200010 37. 88. 2.48 0.13 3265800200011 37. 89. 2.83 0.12 3265800200012 38. 91. 3.93 0.15 3265800200013 38. 92. 4.18 0.14 3265800200014 39. 94. 4.48 0.16 3265800200015 40. 95. 5.22 0.18 3265800200016 41. 97. 5.28 0.20 3265800200017 42. 99. 5.74 0.24 3265800200018 43. 101. 5.61 0.24 3265800200019 43. 104. 3.78 0.15 3265800200020 44. 103. 5.20 0.20 3265800200021 44. 105. 3.64 0.18 3265800200022 45. 107. 2.06 0.11 3265800200023 47. 112. 0.53 0.03 3265800200024 50. 128. 0.927 0.07 3265800200025 51. 127. 0.870 0.06 3265800200026 51. 129. 1.5 0.094 3265800200027 52. 132. 5.36 0.21 3265800200028 53. 131. 3.23 0.14 3265800200029 53. 133. 6.66 0.26 3265800200030 53. 134. 6.28 0.27 3265800200031 54. 135. 5.91 0.24 3265800200032 55. 138. 5.85 0.29 3265800200033 56. 139. 5.10 0.30 3265800200034 56. 140. 5.00 0.19 3265800200035 56. 141. 4.96 0.34 3265800200036 58. 143. 4.28 0.16 3265800200037 59. 146. 2.59 0.13 3265800200038 60. 147. 2.39 0.10 3265800200039 60. 149. 1.39 0.10 3265800200040 ENDDATA 33 0 3265800200041 ENDSUBENT 40 0 3265800299999 SUBENT 32658003 20060619 31213265800300001 BIB 2 2 3265800300002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 3265800300003 METHOD (RCHEM)RADIOCHEMISTRY METHOD 3265800300004 ENDBIB 2 0 3265800300005 NOCOMMON 0 0 3265800300006 DATA 4 14 3265800300007 ELEMENT MASS DATA DATA-ERR 3265800300008 NO-DIM NO-DIM PC/FIS PC/FIS 3265800300009 42. 99. 5.80 0.17 3265800300010 46. 109. 1.10 0.09 3265800300011 47. 111. 0.57 0.06 3265800300012 47. 113. 0.49 0.03 3265800300013 48. 115. 0.43 0.05 3265800300014 50. 121. 0.35 0.10 3265800300015 51. 127. 0.94 0.04 3265800300016 56. 140. 5.72 0.23 3265800300017 56. 141. 4.81 0.14 3265800300018 58. 144. 4.20 0.20 3265800300019 60. 147. 2.53 0.08 3265800300020 62. 153. 0.415 0.25 3265800300021 63. 156. 0.0954 0.0054 3265800300022 65. 161. 0.0094 0.0009 3265800300023 ENDDATA 16 0 3265800300024 ENDSUBENT 23 0 3265800399999 ENDENTRY 3 0 3265899999999