ENTRY 32902 20250826 3290200000001 SUBENT 32902001 20250826 20260228 3290200100001 BIB 15 56 3290200100002 TITLE Fission cross-section measurement for 135mXe and 3290200100003 135gXe in 238U reaction induced by 14MeV D-T neutrons 3290200100004 AUTHOR (Quanxiao Wang, Yunyu Wang, Zhonglin Li, Shutong Niu, 3290200100005 Shuyao Si, Qiang Wang, Shuo Zhan) 3290200100006 INSTITUTE (3CPRLNZ) 3290200100007 (3CPRCPR) Institute of Science and Technology of the 3290200100008 404 Company Limited, China National Nuclear 3290200100009 Corporation, Jiayuguan 3290200100010 REFERENCE (J,ARI,198,110852,2023) 3290200100011 #doi:10.1016/j.apradiso.2023.110852 3290200100012 FACILITY (NGEN,3CPRNPC) K-400 high-current neutron generator 3290200100013 INC-SOURCE (D-T) The density of the T-Ti target used was 2.18 3290200100014 mg/cm2, the average energy and the intensity of the 3290200100015 incident deuterium beam were 134 keV and about 230 uA, 3290200100016 the neutron yield was about 2.0E11 n/s. 3290200100017 SAMPLE A certain mass of high-purity uranium nitrate 3290200100018 (UO2(NO3)2) powder was pressed into the mold. The 3290200100019 diameter of the mold was 12 mm, and the thickness was 3290200100020 about 1 mm. Three sample targets were placed at 3290200100021 different angles (0, 45, 90 deg relative to the 3290200100022 incident direction of the deuterium beam). 3290200100023 DETECTOR (HPGE) A high sensitivity HPGe detector with a low 3290200100024 background lead chamber. The HPGe detector was 3290200100025 connected to a general-purpose spectrometer 3290200100026 amplifier (572A from ORTEC) with a shaping time of 1 3290200100027 us. The energy and efficiency calibration of 3290200100028 HPGe-gamma spectrometers had been carried out 3290200100029 carefully using 60Co, 137Cs, 152Eu and 241Am standard 3290200100030 sources. The detector had an absolute efficiency of 3290200100031 0.504% at 1.173 MeV. 3290200100032 METHOD (ACTIV) The irradiation time is about 7000 s, the 3290200100033 cooling time is about 300 s, and a about 5000 s 3290200100034 period was arranged for the measurement. 3290200100035 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 3290200100036 To eliminate the influence of the D-T reaction 3290200100037 competitions on the neutron fluence. 3290200100038 MONIT-REF (,,3,ENDF/B-VII.1,,2011) 3290200100039 CORRECTION The correction coefficient F = Fs * Fc * Fg, 3290200100040 Fs is the self-absorption correction coefficient, 3290200100041 Fc is the cascade coincidence correction coefficient, 3290200100042 Fg is the geometric correction coefficient. 3290200100043 ERR-ANALYS (ERR-T) The uncertainty of the cross-section 3290200100044 mainly comes from the following. Other uncertain 3290200100045 factors such as the geometry of the sample, the mass 3290200100046 of the sample, the measurement time, the energy of 3290200100047 the incident neutron, fluctuation of neutron flux, 3290200100048 and the cascade coincidence effect of the gamma rays 3290200100049 are all considered during the data analysis. 3290200100050 (ERR-S,0.9,10.3) The statistical fluctuations of the 3290200100051 characteristic peaks of gamma rays 3290200100052 (ERR-1) The effect of the reference foil 3290200100053 (ERR-2,2.0,2.5) The detection efficiency 3290200100054 (ERR-3) The neutron correction factor 3290200100055 (ERR-4) The self-absorption correction factor 3290200100056 STATUS (TABLE,,Quanxiao Wang+,J,ARI,198,110852,2023) Table 2 3290200100057 HISTORY (20250826C) Wang Jimin 3290200100058 ENDBIB 56 0 3290200100059 COMMON 4 3 3290200100060 EN-RSL-HW ERR-1 ERR-3 ERR-4 3290200100061 MEV PER-CENT PER-CENT PER-CENT 3290200100062 0.3 2. 0. 0.5 3290200100063 ENDCOMMON 3 0 3290200100064 ENDSUBENT 63 0 3290200199999 SUBENT 32902002 20250826 20260228 3290200200001 BIB 2 2 3290200200002 REACTION (92-U-238(N,F)54-XE-135-G,,SIG) 3290200200003 DECAY-DATA (54-XE-135-G,9.14HR,DG,249.794,0.90) 3290200200004 ENDBIB 2 0 3290200200005 NOCOMMON 0 0 3290200200006 DATA 3 3 3290200200007 EN DATA ERR-T 3290200200008 MEV MB MB 3290200200009 14.1 2.54 0.14 3290200200010 14.5 3.05 0.19 3290200200011 14.7 2.94 0.19 3290200200012 ENDDATA 5 0 3290200200013 ENDSUBENT 12 0 3290200299999 SUBENT 32902003 20250826 20260228 3290200300001 BIB 2 2 3290200300002 REACTION (92-U-238(N,F)54-XE-135-M,,SIG) 3290200300003 DECAY-DATA (54-XE-135-M,15.29MIN,DG,526.561,0.804) 3290200300004 ENDBIB 2 0 3290200300005 NOCOMMON 0 0 3290200300006 DATA 3 3 3290200300007 EN DATA ERR-T 3290200300008 MEV MB MB 3290200300009 14.1 2.11 0.16 3290200300010 14.5 2.47 0.18 3290200300011 14.7 2.34 0.21 3290200300012 ENDDATA 5 0 3290200300013 ENDSUBENT 12 0 3290200399999 ENDENTRY 3 0 3290299999999