ENTRY 33056 20150119 31713305600000001 SUBENT 33056001 20150119 31713305600100001 BIB 15 47 3305600100002 TITLE Measurement of the neutron capture cross-section of 3305600100003 238U at neutron energies of 5.9 +- 0.5 and 15.5 +- 0.7 3305600100004 MeV by using the neutron activation technique 3305600100005 AUTHOR (V.K.Mulik, S.V.Surayanarayana, H.Naik,Sadhana Mukerji,3305600100006 B.S.Shivashankar, P.M.Prajapati, S.D.Dhole, 3305600100007 V.N.Bhoraskar, S.Ganesan, A.Goswami) 3305600100008 INSTITUTE (3INDPOO,3INDTRM,3INDMNP,3INDBDA) 3305600100009 REFERENCE (J,ANE,63,233,2014) 3305600100010 #doi:10.1016/j.anucene.2013.07.042 3305600100011 FACILITY (VDGT,3INDTRM) 14UD BARC TIFR Pelletron accelerator 3305600100012 SAMPLE (92-U-238,NAT=0.99284) Natural U metal foil, wrapped 3305600100013 with 0.025 mm thick super pure aluminum foil of 3305600100014 purity 99.99%. 3305600100015 DETECTOR (HPGE) Precalibrated 80 c.c HPGe detector 3305600100016 ERR-ANALYS (ERR-T) Total uncertainty propagated from: 3305600100017 (ERR-S,4.,8.) Statistical error 3305600100018 (ERR-SYS,7.7,9.5) The total systematic errors are due 3305600100019 to : 3305600100020 (ERR-1,5.2,7.6) Neutron flux estimation 3305600100021 (ERR-2) Neutron energies weight of U target (~ 0.28%) 3305600100022 (ERR-3) Fission cross-section (~ 4.2%) 3305600100023 (ERR-4) Irradiation time (~ 0.55%) 3305600100024 (ERR-5) Energy calibration and efficiency of detector 3305600100025 around (~ 3%) 3305600100026 (ERR-6) Self-absorption of the gamma-rays in the 3305600100027 sample (~ 1%) 3305600100028 (ERR-7) nuclear decay data (~ 2%) 3305600100029 INC-SOURCE (P-LI7) The neutron flux was produced from the 3305600100030 7Li(p,n) reaction at the incident proton energies of 3305600100031 7.8 MeV and 18.0 MeV. 3305600100032 MONITOR 1(92-U-238(N,F)40-ZR-97,CUM,FY) 3305600100033 2(92-U-238(N,F)53-I-135,CUM,FY) 3305600100034 3(92-U-238(N,F),,SIG) 3305600100035 DECAY-MON 1(40-ZR-97,16.74HR,DG,743.36,0.931) 3305600100036 2(53-I-135,6.57HR,DG,1260.4,0.287) 3305600100037 MONIT-REF (10798001,S.Nagy+,J,PR/C,17,163,1978) 3305600100038 (10828003,T.C.Chapman+,J,PR/C,17,1089,1978) 3305600100039 3(20796003,J.Blons+,J,PRL,35,1749,1975) 3305600100040 METHOD (ACTIV,GSPEC) The irradiation time was 15 h for the 3305600100041 neutron beam corresponding to the proton beam energy 3305600100042 of 7.8 MeV and the irradiation time was 5 h for the 3305600100043 neutron beam corresponding to the proton beam energy 3305600100044 of 18 MeV. After irradiation, the samples were cooled 3305600100045 for 1 to 2 h. 3305600100046 CORRECTION Corrected for captures by low energy backgroud (tail) 3305600100047 neutrons 3305600100048 HISTORY (20150119C) Compiled by Rebecca Lalnuntluangi 3305600100049 ENDBIB 47 0 3305600100050 COMMON 6 3 3305600100051 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 ERR-7 3305600100052 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3305600100053 0.28 4.2 0.55 3. 1. 2.3305600100054 ENDCOMMON 3 0 3305600100055 ENDSUBENT 54 0 3305600199999 SUBENT 33056002 20150119 31713305600200001 BIB 3 6 3305600200002 REACTION (92-U-238(N,G)92-U-239,,SIG) 3305600200003 DECAY-DATA (93-NP-239,2.35D,DG,103.4,0.222, 3305600200004 DG,106.1,0.263, 3305600200005 DG,228.2,0.1114, 3305600200006 DG,277.6,0.1444) 3305600200007 STATUS (TABLE) Table 2 of Ann.Nucl.Energ.63(2014)233 3305600200008 ENDBIB 6 0 3305600200009 NOCOMMON 0 0 3305600200010 DATA 4 2 3305600200011 EN EN-ERR DATA ERR-T 3305600200012 MEV MEV MB MB 3305600200013 5.9 0.5 1.16 0.13 3305600200014 15.5 0.7 0.62 0.08 3305600200015 ENDDATA 4 0 3305600200016 ENDSUBENT 15 0 3305600299999 SUBENT 33056003 20150121 31713305600300001 BIB 3 4 3305600300002 REACTION (92-U-238(N,2N)92-U-237,,SIG) 3305600300003 DECAY-DATA (92-U-237,6.75D,DG,101.1,0.245, 3305600300004 DG,208.0,0.212) 3305600300005 STATUS (TABLE) Table 2 of Ann.Nucl.Energ.63(2014)233 3305600300006 ENDBIB 4 0 3305600300007 NOCOMMON 0 0 3305600300008 DATA 4 1 3305600300009 EN EN-ERR DATA ERR-T 3305600300010 MEV MEV MB MB 3305600300011 15.5 0.7 534. 76. 3305600300012 ENDDATA 3 0 3305600300013 ENDSUBENT 12 0 3305600399999 ENDENTRY 3 0 3305699999999