ENTRY 32687 20110816 31513268700000001 SUBENT 32687001 20110816 31513268700100001 BIB 15 52 3268700100002 TITLE 95Zr,140Ba, and 147Nd yields from 0.57, 1.0, and 1.5 3268700100003 MeV neutrons induced fission of 235U 3268700100004 AUTHOR (Feng Jing,Yang Yi,Liu Shilong,Bao Jie,Liu Yonghui, 3268700100005 Li Ze,Cui Anzhi,Sun Hongqing,Zhang Shengdong, 3268700100006 Guo Jingru) 3268700100007 INSTITUTE (3CPRAEP) 3268700100008 REFERENCE (J,HFH,32,(6),321,2010) 3268700100009 FACILITY (VDGT,3CPRAEP) 2 x 1.7 MV tandem Van de Graaff 3268700100010 accelerator 3268700100011 INC-SOURCE (P-LI7) 7Li(p, n)7Be reaction to obtain 0.57 MeV 3268700100012 neutron source, the thickness of LiF target is 1 3268700100013 mg/cm2. 3268700100014 (P-T) T(p, n)3He reaction to obtain 1.0 and 1.5 MeV 3268700100015 neutron source, the thickness of Ti-T target is 5 3268700100016 mg/cm2. 3268700100017 SAMPLE (92-U-235,ENR=0.902) Enriched metal U sample 3268700100018 including 234U(1.1%), 235U(90.2%), 236U(0.3%) and 3268700100019 238U(8.4%). The mass thickness of thick and thin 3268700100020 sample (as standard sample in fission chamber) is 0.6- 3268700100021 0.8 g/cm2 and 0.3-0.4 mg/cm2, and the diameter is 16 3268700100022 mm. The metal U samples were enveloped by Al foil, 3268700100023 and the sample backing Pt thickness is 0.10-0.15 mm. 3268700100024 METHOD (ABSFY,EXTB) Absolute measurements of fission 3268700100025 products 95Zr, 140Ba and 147Nd. The sample was 3268700100026 irradiation at 2 x 1.7 MV tandem Van de Graaff 3268700100027 accelerator. 3268700100028 DETECTOR (HPGE) 3268700100029 1)The volume of HPGe detector is 110 cm3. 3268700100030 2)For gamma energy 1332.5 keV from 60Co, the 3268700100031 gamma-energy resolution FWHM is 1.8 keV. 3268700100032 3)The uncertainty of efficiency is less than 2%. 3268700100033 ANALYSIS Decay gamma spectrum area were determined with SPAN 3268700100034 code. 3268700100035 CORRECTION 1) Correct gamma self-absorbtion for thick sample 3268700100036 2) To subtract the contamination from neutron which was3268700100037 from scattering and other production neutron reaction. 3268700100038 STATUS (TABLE) Data were taken from Table 4 at page 324 in 3268700100039 J,HFH,32,(6),321,2010. 3268700100040 ERR-ANALYS (DATA-ERR) absolute uncertainty of measurements. 3268700100041 (ERR-S,0.2,0.7) Statistical uncertainty of gamma peak 3268700100042 area for 95Zr, 140Ba and 147Nd is 0.2%, 0.2% and 0.7%, 3268700100043 respectively. 3268700100044 (ERR-1) Uncertainty of fission rate and the correction 3268700100045 for contamination of scattering neutron etc is 2.0%. 3268700100046 (ERR-2) Uncertainty of efficiency calibration is 2.0%. 3268700100047 (ERR-3,1.2,1.8) Uncertainty of the correction for 3268700100048 self-absorbtion. 3268700100049 DECAY-DATA (40-ZR-95,9.219E+04MIN,DG,756.7,0.5450) 3268700100050 (56-BA-140,1.835E+04MIN,DG,537.3,0.2439) 3268700100051 (60-ND-147,1.581E+04MIN,DG,531.,0.1310) 3268700100052 HISTORY (20110330C) Compiled by Guochang CHEN (CNDC) 3268700100053 (20110816A) On. ERR-ANALYS corrected. 3268700100054 ENDBIB 52 0 3268700100055 COMMON 2 3 3268700100056 ERR-1 ERR-2 3268700100057 PER-CENT PER-CENT 3268700100058 2.0 2.0 3268700100059 ENDCOMMON 3 0 3268700100060 ENDSUBENT 59 0 3268700199999 SUBENT 32687002 20110330 31503268700200001 BIB 1 3 3268700200002 REACTION 1(92-U-235(N,F)40-ZR-95,CUM,FY) 3268700200003 2(92-U-235(N,F)56-BA-140,CUM,FY) 3268700200004 3(92-U-235(N,F)60-ND-147,CUM,FY) 3268700200005 ENDBIB 3 0 3268700200006 NOCOMMON 0 0 3268700200007 DATA 7 3 3268700200008 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2DATA 33268700200009 DATA-ERR 3 3268700200010 MEV PC/FIS PC/FIS PC/FIS PC/FIS PC/FIS 3268700200011 PC/FIS 3268700200012 0.57 6.64 0.21 6.37 0.22 2.373268700200013 0.08 3268700200014 1.0 6.49 0.19 6.35 0.18 2.253268700200015 0.07 3268700200016 1.5 6.59 0.19 6.25 0.18 2.373268700200017 0.07 3268700200018 ENDDATA 10 0 3268700200019 ENDSUBENT 18 0 3268700299999 ENDENTRY 2 0 3268799999999