ENTRY 32792 20210512 32003279200000001 SUBENT 32792001 20210512 32003279200100001 BIB 12 43 3279200100002 TITLE Fission product yields from 19.1 MeV neutron induced 3279200100003 fission of 238U 3279200100004 AUTHOR (Yang Yi, Liu Yonghui, Bao Jie, Feng Jing, Li Ze, 3279200100005 Cui Anzhi, Sun Hongqing, Zhang Shengdong, Guo Jingru) 3279200100006 INSTITUTE (3CPRAEP) 3279200100007 REFERENCE (P,INDC(CPR)-053,10,2001) 3279200100008 FACILITY (VDGT,3CPRAEP) 5SDH-2, 2x1.7 MV minim tandem 3279200100009 INC-SOURCE (D-T) The tritium-Ti target bombarded by the deuteron 3279200100010 beam was of the size 10 mm in diameter, thickness of 3279200100011 about 5.5 mg/cm2 and, the adsorption of tritium was 3279200100012 4.0 to 4.5 Ci for every target. The deuteron beam 3279200100013 energy was 3 MeV. 3279200100014 SAMPLE The samples used in the irradiation were 16 mm in 3279200100015 diameter disks made of natural uranium metal about 2 g.3279200100016 The uranium disk was sealed in a pure aluminum 3279200100017 foil of 0.2 mm thickness. The sample sandwiched 3279200100018 between two standardized thin samples to monitor the 3279200100019 fission rate absolutely was mounted in the double 3279200100020 fission chamber. The standardized thin samples were 3279200100021 made of the same uranium as the thick ones. The 3279200100022 double fission chamber was covered with Cd of 1 mm 3279200100023 thickness to shield the thermal neutrons in the 3279200100024 environment. 3279200100025 DETECTOR (HPGE) 3279200100026 METHOD (ACTIV) Four samples were irradiated for periods 3279200100027 about 30 h, every time 2 samples were irradiated, one 3279200100028 had a distance of about 5 cm from the neutron source 3279200100029 in the direction of zero degree, another one 5 mm 3279200100030 from the neutron source, 0 degree. 3279200100031 (GSPEC) The gamma-ray spectra were recorded 3279200100032 successively over a period of two months to encompass 3279200100033 the wide range of half-life involved and to eliminate 3279200100034 the cross interfering of the gamma-rays from the 3279200100035 product nuclides of almost the same energy that can 3279200100036 not be resolved by the HPGe detector. 3279200100037 CORRECTION Corrected for 3279200100038 - Gamma-ray self-absorption 3279200100039 - Cascade coincidence losses 3279200100040 - Background neutrons 3279200100041 - Independent yields and fission from 235U 3279200100042 STATUS (TABLE) Table 1 of INDC(CPR)-053,10,2001 3279200100043 HISTORY (20191002C) Compiled by XI TAO (CNDC) 3279200100044 (20210512U) On. FACILITY modified. 3279200100045 ENDBIB 43 0 3279200100046 COMMON 1 3 3279200100047 EN 3279200100048 MEV 3279200100049 19.1 3279200100050 ENDCOMMON 3 0 3279200100051 ENDSUBENT 50 0 3279200199999 SUBENT 32792002 20191002 31923279200200001 BIB 2 4 3279200200002 REACTION (92-U-235(N,F)MASS,CHN,FY) 3279200200003 ERR-ANALYS (DATA-ERR) Standard deviation by considering all known 3279200200004 sources of random errors according to the error 3279200200005 propagation law 3279200200006 ENDBIB 4 0 3279200200007 NOCOMMON 0 0 3279200200008 DATA 3 36 3279200200009 MASS DATA DATA-ERR 3279200200010 NO-DIM PC/FIS PC/FIS 3279200200011 85. 1.130 0.099 3279200200012 87. 1.871 0.070 3279200200013 88. 2.370 0.107 3279200200014 89. 3.024 0.173 3279200200015 91. 3.392 0.105 3279200200016 92. 3.815 0.165 3279200200017 93. 4.159 0.251 3279200200018 94. 3.730 0.170 3279200200019 95. 4.564 0.139 3279200200020 97. 5.498 0.165 3279200200021 99. 5.824 0.206 3279200200022 101. 4.822 0.211 3279200200023 103. 4.110 0.138 3279200200024 104. 3.823 0.175 3279200200025 105. 3.011 0.097 3279200200026 112. 1.570 0.065 3279200200027 115. 1.277 0.075 3279200200028 127. 1.818 0.073 3279200200029 128. 1.987 0.161 3279200200030 129. 2.066 0.086 3279200200031 130. 3.000 0.985 3279200200032 131. 3.969 0.141 3279200200033 132. 4.529 0.157 3279200200034 133. 5.704 0.181 3279200200035 134. 5.762 0.302 3279200200036 135. 5.503 0.326 3279200200037 138. 5.046 0.448 3279200200038 140. 4.178 0.136 3279200200039 141. 4.632 0.301 3279200200040 142. 3.663 0.145 3279200200041 143. 3.595 0.162 3279200200042 146. 2.212 0.121 3279200200043 147. 1.859 0.063 3279200200044 149. 1.296 0.089 3279200200045 151. 0.686 0.033 3279200200046 156. 0.169 0.072 3279200200047 ENDDATA 38 0 3279200200048 ENDSUBENT 47 0 3279200299999 ENDENTRY 2 0 3279299999999