ENTRY 22665 20121228 22342266500000001 SUBENT 22665001 20121228 22342266500100001 BIB 13 32 2266500100002 TITLE .Determination of cumulative yields of fission 2266500100003 products from 238U by 5.0 MeV neutrons 2266500100004 AUTHOR (I.Celenk) 2266500100005 INSTITUTE (2TUKANR) 2266500100006 REFERENCE (J,RCA,89,481,2001) Main Reference, data are given 2266500100007 REL-REF (I,22785001,I.Celenk+,J,RCA,85,85,1999) Experim.details2266500100008 METHOD (GSPEC) Gamma spectroscopy of fission fragments 2266500100009 radiation 2266500100010 MONITOR (49-IN-115(N,INL)49-IN-115-M,,SIG) 2266500100011 INC-SOURCE (AM-BE) Americium-241-Berillium neutron source 2266500100012 DETECTOR (GE-IN) Reverse-electrode germanium detector. 2266500100013 Active volume 100 cm3, FWHM=1.80 keV at 1332.5 keV 2266500100014 Co-60 photopeak, efficiency 22.6% relative to 2266500100015 7.62*7.62 cm Na-I(Tl) crystal 2266500100016 SAMPLE .U-O2 oxide of 99.55% purity placed into cylindrical 2266500100017 polyethilene tube 27.4 mm long, 7.65 mm inner diam, 2266500100018 wall thickness 1 mm 2266500100019 .In2-O3 oxide in polyethilene tube of the same 2266500100020 dimensions 2266500100021 INC-SPECT .Uranium and indium samples were covered with cadmium 2266500100022 0.7 mm thickness 2266500100023 ERR-ANALYS (ERR-T) Uncertainty includes: 2266500100024 (ERR-1) The largest source of error is the uncertainty 2266500100025 of the cross section of the monitor reaction. 2266500100026 (ERR-S) The uncertainty of the counting is about 3%. 2266500100027 (ERR-2,0.01,2.) The other uncertainties vary between 2266500100028 2% and 0.01%. 2266500100029 HISTORY (20020326C) Compiled by S.M. 2266500100030 (20020328U) Last checking has been done. 2266500100031 (20121228U) SD: INC-SOURCE was corrected. ERR-ANALYS 2266500100032 was added. DATA-ERR-> ERR-T. SF6=SPC -> SIG in 2266500100033 MONITOR reaction. 2266500100034 ENDBIB 32 0 2266500100035 COMMON 4 3 2266500100036 EN E-NRM ERR-1 ERR-S 2266500100037 MEV KEV PER-CENT PER-CENT 2266500100038 5. 336.2 12.0 3.0 2266500100039 ENDCOMMON 3 0 2266500100040 ENDSUBENT 39 0 2266500199999 SUBENT 22665002 20121228 22342266500200001 BIB 3 4 2266500200002 REACTION (92-U-238(N,F)ELEM/MASS,CUM,FY) 2266500200003 MISC-COL (MISC) Energy of gamma-line used for determination 2266500200004 of fission yield 2266500200005 HISTORY (20121228U) SD: DATA-ERR-> ERR-T. 2266500200006 ENDBIB 4 0 2266500200007 NOCOMMON 0 0 2266500200008 DATA 7 34 2266500200009 ELEMENT MASS ISOMER DATA ERR-T MISC 2266500200010 MISC-ERR 2266500200011 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS KEV 2266500200012 KEV 2266500200013 36. 87. 1.767 .245 402.582266500200014 .496 2266500200015 36. 88. 2.269 .297 196.3 2266500200016 .26 2266500200017 37. 89. 2.816 .425 1031.922266500200018 .58 2266500200019 38. 90. 3.892 .571 1024.3 2266500200020 .334 2266500200021 38. 91. 4.088 .595 1383.932266500200022 .9 2266500200023 38. 92. 5.4 .758 590.242266500200024 .73 2266500200025 39. 91. 1. 4.42 .573 555.612266500200026 .561 2266500200027 39. 92. 4.422 .71 934.472266500200028 .139 2266500200029 40. 95. 5.231 .701 756.732266500200030 .545 2266500200031 41. 97. 5.768 .744 658.082266500200032 .984 2266500200033 42. 99. 6.096 .792 739.5 2266500200034 .1213 2266500200035 43. 99. 1. 6.102 .787 140.512266500200036 .8906 2266500200037 43. 101. 6.219 1.03 306.832266500200038 .88 2266500200039 43. 104. 4.508 .614 358. 2266500200040 8.9 2266500200041 44. 103. 6.244 .832 497.082266500200042 .895 2266500200043 44. 105. 4.209 .56 469.372266500200044 .176 2266500200045 45. 105. 4.32 .576 316.9 2266500200046 1.91 2266500200047 51. 131. 3.37 .683 943.4 2266500200048 4.5 2266500200049 52. 131. 3.619 .474 149.722266500200050 .688 2266500200051 52. 133. 6.932 .952 312.072266500200052 .24 2266500200053 52. 134. 7.112 1.006 565.992266500200054 .183 2266500200055 53. 131. 3.724 .482 364.482266500200056 .812 2266500200057 53. 132. 4.611 .599 667.692266500200058 .987 2266500200059 53. 133. 7.091 .93 529.872266500200060 .873 2266500200061 53. 134. 7.328 .961 847.022266500200062 .954 2266500200063 53. 135. 6.569 .85 1260.412266500200064 .286 2266500200065 55. 138. 6.106 .804 462.8 2266500200066 .3075 2266500200067 56. 139. 5.893 .811 165.862266500200068 .22 2266500200069 56. 140. 5.87 .759 537.312266500200070 .244 2266500200071 57. 140. 5.984 .778 487.032266500200072 .455 2266500200073 57. 142. 4.353 .566 641.282266500200074 .474 2266500200075 58. 141. 5.18 .669 145.492266500200076 .484 2266500200077 58. 143. 4.698 .609 293.262266500200078 .42 2266500200079 59. 146. 3.332 .449 453.882266500200080 .48 2266500200081 ENDDATA 72 0 2266500200082 ENDSUBENT 81 0 2266500299999 ENDENTRY 2 0 2266599999999