ENTRY 32794 20190623 31953279400000001 SUBENT 32794001 20190623 31953279400100001 BIB 13 43 3279400100002 TITLE Chain yields from 19.1 MeV neutron-induced fission of 3279400100003 U-235 3279400100004 AUTHOR (Bao Jie, Yang Yi, Liu Yonghui, Feng Jing, Li Ze, 3279400100005 Cui Anzhi, Sun Hongqing, Zhang Shengdong, Guo Jingru) 3279400100006 INSTITUTE (3CPRAEP) 3279400100007 REFERENCE ((J,CNDP,26,8,2001)=(P,INDC(CPR)-56,8,2001)) 3279400100008 FACILITY (VDGT,3CPRAEP) The HI-13 Tandem 3279400100009 INC-SOURCE (D-T) The Tritium-Ti target, 10 mm diameter, and 5.2 3279400100010 mg/cm2 thickness. The deuteron beam energy was 3 MeV. 3279400100011 SAMPLE The uranium metal (about 2 g) disks with 16 mm diameter3279400100012 were sealed in a pure Al foil of 0.2 mm thickness. It 3279400100013 was sandwiched between two standardized thinner uranium3279400100014 samples. The standardized thin samples were made of the3279400100015 same uranium as the thick ones. The abundance of 3279400100016 Uranium isotopes: 3279400100017 U-235, 90.2% 3279400100018 U-234, 1.1% 3279400100019 U-236, 0.3 % 3279400100020 U-238, 8.4% 3279400100021 DETECTOR (HPGE) Gamma-spectrometers. 3279400100022 (FISCH) The sample was mounted in a double fission 3279400100023 chamber, covered with Cd of 1 mm thick in order to 3279400100024 shield it from the thermal neutrons from the 3279400100025 environment. 3279400100026 METHOD (ACTIV) Four samples were irradiated for 30 h at a 3279400100027 distance of about 5 cm from the neutron source in the 3279400100028 direction of zero degree. 3279400100029 (GSPEC) Fission product activities were measured by 3279400100030 HPGe gamma-ray spectrometry. The gamma ray spectra 3279400100031 were collected over a period varying from 30 seconds 3279400100032 up to two months, and the gamma ray spectra were 3279400100033 analyzed by the decay program SPAN. The fission 3279400100034 yields were obtained by FYAUTOLS. 3279400100035 MONITOR Absolute measurement of fission rate 3279400100036 CORRECTION Corrections were made for coincidence losses, pileup 3279400100037 losses in the counting system, influence of the 3279400100038 background neutrons, self absorption of gamma ray, 3279400100039 independent yields and influence from other uranium 3279400100040 isotopes. 3279400100041 COMMENT The sum of the yields directly measured was 61.1% for 3279400100042 the light mass groups, and 53.2% for the heavy mass 3279400100043 groups. 3279400100044 HISTORY (20190623C) Compiled by Liu Lile (CNDC) 3279400100045 ENDBIB 43 0 3279400100046 COMMON 1 3 3279400100047 EN 3279400100048 MEV 3279400100049 19.1 3279400100050 ENDCOMMON 3 0 3279400100051 ENDSUBENT 50 0 3279400199999 SUBENT 32794002 20190623 31953279400200001 BIB 3 3 3279400200002 REACTION (92-U-235(N,F)MASS,CHN,FY) 3279400200003 ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 3279400200004 STATUS (TABLE) Table 1 of P,INDC(CPR)-56,8,2001 3279400200005 ENDBIB 3 0 3279400200006 NOCOMMON 0 0 3279400200007 DATA 3 35 3279400200008 MASS DATA DATA-ERR 3279400200009 NO-DIM PC/FIS PC/FIS 3279400200010 84. 0.61 0.16 3279400200011 85. 1.49 0.07 3279400200012 87. 2.76 0.04 3279400200013 88. 3.21 0.04 3279400200014 89. 3.90 0.05 3279400200015 91. 3.87 0.04 3279400200016 92. 4.49 0.09 3279400200017 93. 4.22 0.07 3279400200018 94. 4.19 0.05 3279400200019 95. 4.54 0.04 3279400200020 97. 4.77 0.03 3279400200021 99. 5.6 0.03 3279400200022 101. 3.83 0.04 3279400200023 103. 3.06 0.03 3279400200024 104. 3.33 0.06 3279400200025 105. 2.92 0.06 3279400200026 112. 2.31 0.11 3279400200027 115. 2.02 0.06 3279400200028 117. 1.65 0.11 3279400200029 127. 2.29 0.07 3279400200030 128. 2.55 0.64 3279400200031 129. 2.79 0.09 3279400200032 131. 4.04 0.54 3279400200033 132. 3.82 0.03 3279400200034 133. 5.21 0.03 3279400200035 134. 6.25 0.47 3279400200036 135. 5.44 0.04 3279400200037 138. 4.38 0.12 3279400200038 140. 3.93 0.04 3279400200039 142. 2.97 0.05 3279400200040 143. 3.17 0.05 3279400200041 146. 1.54 0.12 3279400200042 147. 1.71 0.07 3279400200043 149. 0.85 0.05 3279400200044 151. 0.64 0.05 3279400200045 ENDDATA 37 0 3279400200046 ENDSUBENT 45 0 3279400299999 ENDENTRY 2 0 3279499999999