ENTRY 32720 20140611 31673272000000001 SUBENT 32720001 20140611 31673272000100001 BIB 13 33 3272000100002 TITLE Study on coincidence measurement for 56Fe(n,xng) 3272000100003 reaction cross section 3272000100004 AUTHOR (Wang Zhaohui,Su Xiaobin,Zhang Xiaopeng,Hou Long, 3272000100005 Yu Guoliang,Li Xia,Wang Qi) 3272000100006 REFERENCE (J,CST,47,2177,2013) 3272000100007 #doi:10.7538/yzk.2013.47.12.2177 3272000100008 INSTITUTE (3CPRAEP) 3272000100009 FACILITY (CCW,3CPRAEP) 600 kV Cockcroff-Walton accelerator 3272000100010 SAMPLE A natural iron sample with 3x3 cm in diameter and 3272000100011 thickness were used. 3272000100012 INC-SOURCE (D-T) T-Ti target were used to produce incident 3272000100013 neutron. 3272000100014 METHOD (COINC) Apply the coincidence method to measure the 3272000100015 prompt gamma from residual nuclei with 846.8 and 3272000100016 1238.3 keV energy. 3272000100017 (GSPEC,ASSOP) 3272000100018 DETECTOR (HPGE) 2 clover detectors are consist of 8 co-axis N- 3272000100019 type HPGe with 60x60 mm in diameter and thickness, 3272000100020 which was calibrated using Eu-152 gamma source. 3272000100021 (SIBAR) The associated alpha particle are detect by 3272000100022 Au-Si surface detector as neutron flux monitor. 3272000100023 ERR-ANALYS Total uncertainty of measurement mainly due to 3272000100024 gamma full-energy peak counting statistics, distance 3272000100025 between sample and detector, weight of sample and 3272000100026 correction factor calculation etc. 3272000100027 CORRECTION Corrections were made for gamma-ray self-absorption 3272000100028 in the sample, fluctuation of the neutron flux during 3272000100029 the irradiation, multi-scattering, dead-time, cascade 3272000100030 gamma rays coincidence, and sample geometry. 3272000100031 STATUS (TABLE) Data taken from Table 1 in page 2180 of 3272000100032 J,CST,Vol.47,p.2177,201312. 3272000100033 HISTORY (20140409C) Compiled by ZHUANG Youxiang and 3272000100034 CHEN Guochang (CNDC). 3272000100035 ENDBIB 33 0 3272000100036 COMMON 1 3 3272000100037 EN 3272000100038 MEV 3272000100039 14.8 3272000100040 ENDCOMMON 3 0 3272000100041 ENDSUBENT 40 0 3272000199999 SUBENT 32720002 20140611 31673272000200001 BIB 1 1 3272000200002 REACTION (26-FE-56(N,2N)26-FE-55,PAR,SIG,G) 3272000200003 ENDBIB 1 0 3272000200004 NOCOMMON 0 0 3272000200005 DATA 2 8 3272000200006 E DATA 3272000200007 KEV MB 3272000200008 385.26 5.4963 3272000200009 411.93 30.868 3272000200010 477.21 37.935 3272000200011 803.4 16.458 3272000200012 895.3 18.539 3272000200013 931.28 122.03 3272000200014 1316.4 56.534 3272000200015 1408.4 43.586 3272000200016 ENDDATA 10 0 3272000200017 ENDSUBENT 16 0 3272000299999 SUBENT 32720003 20140611 31673272000300001 BIB 1 1 3272000300002 REACTION (26-FE-56(N,INL)26-FE-56,PAR,SIG,G) 3272000300003 ENDBIB 1 0 3272000300004 NOCOMMON 0 0 3272000300005 DATA 2 4 3272000300006 E DATA 3272000300007 KEV MB 3272000300008 846.8 611.55 3272000300009 1037.8 73.921 3272000300010 1238.3 283.85 3272000300011 1303.3 62.761 3272000300012 ENDDATA 6 0 3272000300013 ENDSUBENT 12 0 3272000399999 ENDENTRY 3 0 3272099999999