ENTRY 32719 20180528 31863271900000001 SUBENT 32719001 20180528 31863271900100001 BIB 15 50 3271900100002 TITLE Fission product yields measurement of 232Th induced 3271900100003 by 14.8 MeV neutron 3271900100004 AUTHOR (Liu Shilong,Yang Yi,Feng Jing,Zhang Chunli, 3271900100005 Chen Hongtao) 3271900100006 INSTITUTE (3CPRAEP) 3271900100007 REFERENCE (J,CST,47,901,2013) 3271900100008 #doi:10.7538/yzk.2013.47.06.0901 3271900100009 FACILITY (CCW,3CPRAEP) 3271900100010 SAMPLE The target was a 232Th metallic foil with 20 mm in 3271900100011 diameter and bout 1. gram in mass, and wraped by 3271900100012 aluminium foil with 20 um thickness to restraint the 3271900100013 escaping of fission fragments. 3271900100014 INC-SOURCE (D-T) 3271900100015 METHOD (RELFY,FPGAM) The relative cumulative yields of 62 3271900100016 fission products were determined using direct 3271900100017 gamma-ray spectrum method. 3271900100018 The obtained relative chain yields were normalized 3271900100019 so that their summation becomes 200%. 3271900100020 DETECTOR (HPGE) The volume of HPGe detector is 230 cm3, and 3271900100021 the relative efficiency is 90%. 3271900100022 (SIBAR) The Au-Si surface barrier detector is used to 3271900100023 measure the accompanying alpha particle from 3271900100024 T(d,n)4He reaction as neutron flux monitor. 3271900100025 ANALYSIS Gamma spectrum area were determined with SPAN code. 3271900100026 The relative cumulative yields were calculated by 3271900100027 FYAUTOLS and FYNorm code. 62 fission products were 3271900100028 measured, 47 mass cumulative yields data were 3271900100029 directly obtained from measurement, and other 15 mass 3271900100030 cumulative yields were obtained by interpolation and 3271900100031 extrapolation method. 3271900100032 CORRECTION The main correction includes the gamma-ray 3271900100033 self-absorption in sample and cascade gamma-ray 3271900100034 emission. 3271900100035 ERR-ANALYS (ERR-T) The total uncertainty (<10.2%) 3271900100036 (ERR-S,,8.) The uncertainty of gamma counting 3271900100037 statistics (<8%) 3271900100038 (ERR-1,,1.5) The uncertainty of gamma-ray cascade 3271900100039 correction (<1.5%) 3271900100040 (ERR-2) The uncertainty of efficiency calibration(1.5%)3271900100041 (ERR-3,,1.2) The uncertainty of gamma-ray 3271900100042 self-absorption (<1.2%) 3271900100043 (ERR-4,,2.) The uncertainty of cumulative yields 3271900100044 normalization (<2%) 3271900100045 REL-REF (R,,R.B.Firestone,B,FIRESTONE,,,1996) 3271900100046 Decay data given 3271900100047 STATUS (TABLE) The fission yield and total uncertainty data 3271900100048 are taken from Table 1, and the detailed uncertainties 3271900100049 are taken from Table 2 at page 905 in 3271900100050 J,CST,47,901,2013. 3271900100051 HISTORY (20180528C) Compiled by WANG Jimin (CNDC) 3271900100052 ENDBIB 50 0 3271900100053 COMMON 2 3 3271900100054 EN ERR-2 3271900100055 MEV PER-CENT 3271900100056 14.8 1.5 3271900100057 ENDCOMMON 3 0 3271900100058 ENDSUBENT 57 0 3271900199999 SUBENT 32719002 20180528 31863271900200001 BIB 1 1 3271900200002 REACTION (90-TH-232(N,F)MASS,CHN,FY) 3271900200003 ENDBIB 1 0 3271900200004 NOCOMMON 0 0 3271900200005 DATA 3 47 3271900200006 MASS DATA ERR-T 3271900200007 NO-DIM PC/FIS PC/FIS 3271900200008 84. 4.47 0.05 3271900200009 85. 4.51 0.11 3271900200010 87. 5.43 0.14 3271900200011 88. 5.50 0.13 3271900200012 89. 5.82 0.16 3271900200013 90. 5.48 0.51 3271900200014 91. 5.63 0.05 3271900200015 92. 5.29 0.05 3271900200016 93. 5.21 0.23 3271900200017 94. 4.16 0.05 3271900200018 95. 3.83 0.21 3271900200019 97. 3.35 0.05 3271900200020 99. 2.31 0.12 3271900200021 101. 1.47 0.15 3271900200022 102. 1.59 0.24 3271900200023 103. 1.05 0.05 3271900200024 104. 1.15 0.13 3271900200025 105. 1.07 0.05 3271900200026 111. 1.52 0.33 3271900200027 112. 1.68 0.05 3271900200028 113. 1.47 0.15 3271900200029 115. 1.34 0.21 3271900200030 116. 1.35 0.12 3271900200031 119. 1.45 0.21 3271900200032 123. 0.92 0.13 3271900200033 127. 1.05 0.10 3271900200034 128. 1.05 0.14 3271900200035 129. 1.18 0.11 3271900200036 130. 1.62 0.12 3271900200037 131. 2.72 0.05 3271900200038 132. 3.28 0.13 3271900200039 133. 4.71 0.09 3271900200040 134. 4.97 0.13 3271900200041 135. 5.35 0.09 3271900200042 138. 5.37 0.12 3271900200043 139. 5.71 0.10 3271900200044 140. 5.61 0.14 3271900200045 141. 5.82 0.15 3271900200046 142. 4.77 0.22 3271900200047 143. 4.97 0.11 3271900200048 145. 3.17 0.23 3271900200049 146. 2.16 0.19 3271900200050 147. 1.11 0.10 3271900200051 148. 1.20 0.21 3271900200052 149. 0.55 0.13 3271900200053 151. 0.38 0.05 3271900200054 152. 0.24 0.05 3271900200055 ENDDATA 49 0 3271900200056 ENDSUBENT 55 0 3271900299999 ENDENTRY 2 0 3271999999999