ENTRY 32718 20221116 3271800000001 SUBENT 32718001 20221116 20231011 3271800100001 BIB 14 53 3271800100002 TITLE Absolute measurement of 99Mo fission yields of 235U 3271800100003 induced by 0.57, 1.0 and 1.5 MeV neutrons 3271800100004 AUTHOR (Feng Jing,Bao Jie,Yang Yi,Liu Shi-long,Zhang Chun-li, 3271800100005 Yang Yang,Liu Yong-hui) 3271800100006 INSTITUTE (3CPRAEP) 3271800100007 REFERENCE (J,CST,47,1473,2013) 3271800100008 #doi:10.7538/yzk.2013.47.09.1473 3271800100009 FACILITY (VDGT,3CPRAEP) 2 x 1.7 MV Tandem Accelerator 3271800100010 SAMPLE (92-U-235,ENR=0.902)Isotopic composition of the sample 3271800100011 are 234U(1.1%), 235U(90.2%), 236U(0.3%) and 3271800100012 238U(8.4%). The thick uranium target with 16 mm in 3271800100013 diameter and 0.6-0.8 g/cm2 in mass thickness, was 3271800100014 wrapped by pure aluminium foil with 5 mg/cm2 in mass 3271800100015 thickness. The thin uranium target with 16 mm in 3271800100016 diameter and 0.3-0.4 mg/cm2 in mass thickness, was 3271800100017 electrodeposited on the platinum foil with 0.10-0.15 3271800100018 mm thickness. 3271800100019 INC-SOURCE (P-LI7) The 0.57 MeV neutrons were obtained by 3271800100020 7Li(p,n)7Be. LiF target thickness is 1 mg/cm2. The 3271800100021 incident energies of proton is 2.36 MeV. 3271800100022 (P-T) The 1.0 and 1.5 MeV neutrons were obtained by 3271800100023 T(p,n)3He. T-Ti target thickness is 5 mg/cm2. The 3271800100024 incident energies of proton are 2.05 and 2.50 MeV. 3271800100025 METHOD (ABSFY,GSPEC) Absolute measurements of the cumulative 3271800100026 yields of fission product 99Mo were determined for 3271800100027 the fission of 235U induced by 0.57, 1.0 and 1.5 MeV 3271800100028 neutrons. Fission product activities were measured by 3271800100029 HPGe gamma ray spectrometry. Absolute fission rate 3271800100030 was monitored with a double-fission chamber. 3271800100031 DETECTOR (HPGE) The volume of HPGe detector is 110 cm3. The 3271800100032 energy resolution is 1.8 keV for 60Co at 1332.5 keV 3271800100033 gamma ray. 3271800100034 (FISCH) Double-fission chamber were used to measure 3271800100035 the absolute fission rate, and monitor the changing 3271800100036 of fission rate with time. 3271800100037 ANALYSIS Decay gamma spectrum area were determined with SPAN 3271800100038 code, and fission cumulative yields were calculated by 3271800100039 FYAUTOLS code. 3271800100040 CORRECTION The main correction is the gamma-ray self-absorption 3271800100041 in the target. The effects of all kinds of secondary 3271800100042 neutrons on fission yield data were discussed. 3271800100043 ERR-ANALYS (ERR-T) The total uncertainty. 3271800100044 (ERR-S) The uncertainty of gamma counting statistics. 3271800100045 (ERR-1) The uncertainty of fission rate is 2.0%. 3271800100046 (ERR-2) The uncertainty of efficiency calibration is 3271800100047 2.0%. 3271800100048 (ERR-3) The uncertainty of self-absorption is 0.18%. 3271800100049 STATUS (TABLE) The fission yield and total uncertainty data 3271800100050 were taken from Table 2, and the detailed 3271800100051 uncertainties were taken from Table 3 at page 1477 in 3271800100052 J,CST,47,1473,2013. 3271800100053 HISTORY (20140529C) Compiled by WANG Jimin (CNDC). 3271800100054 (20221116A) Jimin Wang: major revisions in 002 3271800100055 ENDBIB 53 0 3271800100056 COMMON 3 3 3271800100057 ERR-1 ERR-2 ERR-3 3271800100058 PER-CENT PER-CENT PER-CENT 3271800100059 2.0 2.0 0.18 3271800100060 ENDCOMMON 3 0 3271800100061 ENDSUBENT 60 0 3271800199999 SUBENT 32718002 20221116 20231011 3271800200001 BIB 3 4 3271800200002 REACTION (92-U-235(N,F)42-MO-99,CUM,FY) 3271800200003 DECAY-DATA (42-MO-99,65.94HR,DG,739.5,0.121) 3271800200004 HISTORY (20221116A) Jimin Wang: PC/FIS --> PER-CENT 3271800200005 under ERR-T and ERR-S 3271800200006 ENDBIB 4 0 3271800200007 NOCOMMON 0 0 3271800200008 DATA 4 3 3271800200009 EN DATA ERR-T ERR-S 3271800200010 MEV PC/FIS PER-CENT PER-CENT 3271800200011 0.57 6.61 3.2 1.4 3271800200012 1.0 6.62 3.1 1.3 3271800200013 1.5 6.28 2.8 0.2 3271800200014 ENDDATA 5 0 3271800200015 ENDSUBENT 14 0 3271800299999 ENDENTRY 2 0 3271899999999