ENTRY 32787 20191012 31923278700000001 SUBENT 32787001 20191012 31923278700100001 BIB 16 67 3278700100002 TITLE Fission cross-section measurement for 238U(n,f)Z-X- 3278700100003 134 reactions induced by D-T neutrons 3278700100004 AUTHOR (Niu Deqing,Zhang Zuoyi,Zhou Yong,Yang Chao,Liu Yang, 3278700100005 Fang Kaihong) 3278700100006 INSTITUTE (3CPRTSI) 3278700100007 (3CPRCPR) Southwest Automation Research Institute, 3278700100008 Mianyang, Sichuan, China 3278700100009 (3CPRCPR) Southwest University of Science and 3278700100010 Technology, Mianyang, Sichuan, China 3278700100011 REFERENCE (J,RPC,158,175,2019) 3278700100012 #doi:10.1016/j.radphyschem.2018.12.028 3278700100013 FACILITY (NGEN,3CPRNPC) K-400 Intense Neutron Generator 3278700100014 INC-SOURCE (D-T) Neutron with a yiels of about 2E11 n/s was 3278700100015 produced. 3278700100016 SAMPLE The natural abundance uranium sesquioxide (U2O3, 98% 3278700100017 purity) powder for uranium target was pressed into 3278700100018 circular disk with a diameter of 12.0 mm and a 3278700100019 thickness of about 1.0 mm. Each sample disk was 3278700100020 covered by a polyethylene film, and then sandwiched 3278700100021 between two thin pure aluminum foils (99.99% purity). 3278700100022 Three U2O3 samples (with mass around 1 g), which were 3278700100023 placed at 0 deg, 45 deg and 90 deg angles related to 3278700100024 the deuteron beam direction and centered about the 3278700100025 T-Ti target at a distance of 4.0 cm. 3278700100026 DETECTOR (HPGE) High-Purity Germanium (HPGe,ORTEC) gamma-ray 3278700100027 spectrometer with 68% relative efficiency and 1.7 keV 3278700100028 energy resolution at 1332.5 keV. 3278700100029 METHOD (ACTIV) Two sets of measurement schemes were arranged 3278700100030 to distinguish the short half-life and long half-life 3278700100031 fragments. Firstly, the samples after irradiating and 3278700100032 cooling (4.5 min) were measured by the HPGe detector 3278700100033 about 90.0 min for the gamma-spectrum accumulation 3278700100034 from short half-life nuclides. Meanwhile, the 3278700100035 gamma-spectrum was recorded every minute during this 3278700100036 measurement (about 90.0 min) , so as to investigate 3278700100037 the nuclide with much shorter half-life. Secondly, 3278700100038 after a long cooling time (24 h) the samples were 3278700100039 measured for every 12 h, and more than twenty gamma 3278700100040 spectra were recorded. 3278700100041 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 3278700100042 Fang Kaihong (2019-10-24): 3278700100043 The values are 121.1 mb at 14.1 MeV, 116.0 mb at 3278700100044 14.5 MeV and 113.4 mb at 14.7 MeV. 3278700100045 DECAY-MON (11-NA-24,14.997HR,DG,1368.626,0.999936) 3278700100046 MONIT-REF (,,J,NDS,112,2887,2011) ENDF/B-VII.1 3278700100047 CORRECTION Correction factor F=Fg*Fs*Fc includes three parts: 3278700100048 The geometry correction factor (Fg) which originates 3278700100049 from volume effect of samples. The self-absorption 3278700100050 correction factor (Fs) caused by the gamma-ray 3278700100051 absorption as penetrating the sample itself, which 3278700100052 becomes more negligible with the increase of 3278700100053 gamma-ray energy. The correction (Fc) is due to the 3278700100054 coincidence sum effect of cascade gamma-rays. 3278700100055 ERR-ANALYS (ERR-T) The uncertainties mainly come from the 3278700100056 counting statistics of the characteristic peak, 3278700100057 detection effciency and the self-absorption. Other 3278700100058 uncertainties, caused by the weight of samples, 3278700100059 sample geometry, coincidence sum effect of cascade 3278700100060 gamma-rays, neutron energy and fluence, the time 3278700100061 schedule and the cross-section of monitor reaction, 3278700100062 were also considered. 3278700100063 (ERR-S) Counting statistics of the characteristic 3278700100064 peak, about 2.5% 3278700100065 (ERR-1) Detection effciency, about 2% 3278700100066 (ERR-2) The self-absorption about 1% 3278700100067 STATUS (TABLE) Table 2 of Radiat.Phys.Chem.158,175,2019. 3278700100068 HISTORY (20191012C) Compiled by Liu Lile (CNDC) 3278700100069 ENDBIB 67 0 3278700100070 COMMON 3 3 3278700100071 ERR-S ERR-1 ERR-2 3278700100072 PER-CENT PER-CENT PER-CENT 3278700100073 2.5 2. 1. 3278700100074 ENDCOMMON 3 0 3278700100075 ENDSUBENT 74 0 3278700199999 SUBENT 32787002 20191012 31923278700200001 BIB 3 8 3278700200002 REACTION (92-U-238(N,F)52-TE-134,(CUM),SIG) 3278700200003 DECAY-DATA ((1.)52-TE-134,41.8MIN,DG,201.235,0.089) 3278700200004 ((2.)52-TE-134,41.8MIN,DG,210.465,0.227) 3278700200005 ((3.)52-TE-134,41.8MIN,DG,435.06,0.189) 3278700200006 ((4.)52-TE-134,41.8MIN,DG,565.992,0.186) 3278700200007 COMMENT By the authors: 3278700200008 The measurement shows that the 134I yield is 3278700200009 negligible in comparison with the 134Te yield. 3278700200010 ENDBIB 8 0 3278700200011 NOCOMMON 0 0 3278700200012 DATA 6 12 3278700200013 EN EN-ERR DATA ERR-T DECAY-FLAG MONIT 3278700200014 MEV MEV MB MB NO-DIM MB 3278700200015 14.1 0.3 46.8 3.1 1. 121.1 3278700200016 14.1 0.3 46.9 3.1 2. 121.1 3278700200017 14.1 0.3 51.3 3.3 3. 121.1 3278700200018 14.1 0.3 54.0 3.4 4. 121.1 3278700200019 14.5 0.3 50.7 3.3 1. 116.0 3278700200020 14.5 0.3 48.8 3.2 2. 116.0 3278700200021 14.5 0.3 53.0 3.4 3. 116.0 3278700200022 14.5 0.3 58.0 3.6 4. 116.0 3278700200023 14.7 0.3 53.5 3.5 1. 113.4 3278700200024 14.7 0.3 54.6 3.5 2. 113.4 3278700200025 14.7 0.3 50.8 3.4 3. 113.4 3278700200026 14.7 0.3 58.2 3.7 4. 113.4 3278700200027 ENDDATA 14 0 3278700200028 ENDSUBENT 27 0 3278700299999 SUBENT 32787003 20191012 31923278700300001 BIB 3 4 3278700300002 REACTION (92-U-238(N,F)52-TE-134,(CUM),SIG,,AV) 3278700300003 ANALYSIS Simple average of four cross sections 3278700300004 STATUS (DEP,32787002) Cross sections obtained from four gamma 3278700300005 lines 3278700300006 ENDBIB 4 0 3278700300007 NOCOMMON 0 0 3278700300008 DATA 5 3 3278700300009 EN EN-ERR DATA ERR-T MONIT 3278700300010 MEV MEV MB MB MB 3278700300011 14.1 0.3 50.0 3.2 121.1 3278700300012 14.5 0.3 52.6 3.4 116.0 3278700300013 14.7 0.3 54.3 3.5 113.4 3278700300014 ENDDATA 5 0 3278700300015 ENDSUBENT 14 0 3278700399999 ENDENTRY 3 0 3278799999999