ENTRY 32903 20241220 32173290300000001 SUBENT 32903001 20241220 32173290300100001 BIB 7 18 3290300100002 TITLE 63Cu(n,a)60Co cross sections in the MeV region 3290300100003 AUTHOR (Jie Liu,Zengqi Cui,Yiwei Hu,Haofan Bai,Yi Yang, 3290300100004 Xichao Ruan,Cong Xia,Jinxiang Chen,Guohui Zhang, 3290300100005 Yu.M.Gledenov,E.Sansarbayar,G.Khuukhenkhuu,L.Krupa, 3290300100006 I.Chuprakov,Hanxiong Huang,Jie Ren,Qiwen Fan,Yuan Gao, 3290300100007 Xiangjun Yang) 3290300100008 INSTITUTE (3CPRBJG,3CPRCNI,3CPRAEP,4ZZZDUB,3MGLNUM,3CZRCTI, 3290300100009 4KASATN,4KASKAZ) 3290300100010 REFERENCE (J,JP/G,50,045106,2023) 3290300100011 #doi:10.1088/1361-6471/acb960 3290300100012 FACILITY (VDG,3CPRBJG) The 4.5 MV Van de Graaff accelerator 3290300100013 (VDGT,3CPRAEP) The HI-13 tandem accelerator 3290300100014 INC-SOURCE (D-D) 4.50, 5.00 and 5.50 MeV quasi mono-energetic 3290300100015 neutrons were produced at the 4.5 MV Van de Graaff 3290300100016 accelerator. 8.50, 9.50 and 10.50 MeV quasi 3290300100017 mono-energetic neutrons were produced at the HI-13 3290300100018 tandem accelerator. 3290300100019 HISTORY (20241220C) Yang Su and Jimin Wang 3290300100020 ENDBIB 18 0 3290300100021 NOCOMMON 0 0 3290300100022 ENDSUBENT 21 0 3290300199999 SUBENT 32903002 20241220 32173290300200001 BIB 8 44 3290300200002 REACTION (29-CU-63(N,A)27-CO-60,,SIG) 3290300200003 SAMPLE (29-CU-63,ENR=0.998) Mass thickness of 1334.9 ug/cm2 3290300200004 and diameter of 4.3 cm. 3290300200005 DETECTOR (IOCH) Two gridded ionization chamber (GIC) for 3290300200006 charged particle detection. 3290300200007 (SCIN) The EJ-309 liquid scintillator for the 3290300200008 measurement of the neutron energy spectra. 3290300200009 METHOD Direct measurement method. The total (n,a) cross 3290300200010 sections are obtained by adding up the forward and 3290300200011 backward cross sections while the forward/backward 3290300200012 ratios in the laboratory reference system are 3290300200013 obtained by dividing them. 3290300200014 MONITOR (92-U-238(N,F),,SIG) 3290300200015 MONIT-REF (,A.D.Carlson+,J,NDS,148,143,2018) 3290300200016 ERR-ANALYS (ERR-T) Total uncertainty 3290300200017 (ERR-1) The numbers of the 238U nuclei in sample for 3290300200018 forward and backward cross sections. 3290300200019 (ERR-2) The numbers of the 63Cu nuclei in sample for 3290300200020 forward and backward cross sections. 3290300200021 (ERR-3,0.82,6.3) The counts of the alpha events for 3290300200022 forward cross sections. 3290300200023 (ERR-4,0.80,6.8) The counts of the alpha events for 3290300200024 backward cross sections. 3290300200025 (ERR-5,3.3,7.3) The detection efficiency of the alpha 3290300200026 events for forward cross sections. 3290300200027 (ERR-6,3.4,7.5) The detection efficiency of the alpha 3290300200028 events for backward cross sections. 3290300200029 (ERR-7,0.44,1.7) The counts of the fission events for 3290300200030 forward and backward cross sections. 3290300200031 (ERR-8,1.9,3.4) The detection efficiency of the 3290300200032 fission events for forward and backward cross sections.3290300200033 (ERR-9,0.63,2.8) The ratio of the fission events 3290300200034 induced by the main-energy neutrons to those induced by3290300200035 all neutrons for forward and backward cross sections. 3290300200036 (ERR-10,0.28,0.86) The ratio of the fission counts 3290300200037 for the normalization of the neutron fluence for 3290300200038 forward and backward cross sections. 3290300200039 (ERR-11) The neutron flux fluctuation factor for 3290300200040 forward and backward cross sections. 3290300200041 (MONIT-ERR,1.3,1.5) The standard cross section of the 3290300200042 238U(n,f) reaction for forward and backward cross 3290300200043 sections. 3290300200044 STATUS (TABLE,,Jie Liu+,J,JP/G,50,045106,2023) Table 3 3290300200045 (COREL,32903003) Data from activation measurement 3290300200046 ENDBIB 44 0 3290300200047 COMMON 3 3 3290300200048 ERR-1 ERR-2 ERR-11 3290300200049 PER-CENT PER-CENT PER-CENT 3290300200050 1.0 1.0 1.0 3290300200051 ENDCOMMON 3 0 3290300200052 DATA 4 6 3290300200053 EN EN-RSL-HW DATA ERR-T 3290300200054 MEV MEV MB MB 3290300200055 4.50 0.14 0.98 0.10 3290300200056 5.00 0.09 1.46 0.12 3290300200057 5.50 0.09 3.17 0.22 3290300200058 8.50 0.12 20.17 1.28 3290300200059 9.50 0.11 26.66 1.58 3290300200060 10.50 0.11 32.25 2.20 3290300200061 ENDDATA 8 0 3290300200062 ENDSUBENT 61 0 3290300299999 SUBENT 32903003 20241220 32173290300300001 BIB 8 48 3290300300002 REACTION (29-CU-63(N,A)27-CO-60,,SIG) 3290300300003 SAMPLE The samples included two copper samples and three 3290300300004 aluminum samples with a sandwich structure, which 3290300300005 were wrapped in cadmium foil to absorb thermal 3290300300006 neutrons. The copper and aluminum samples are all 3290300300007 natural ones >99.999% in purity. The thicknesses of 3290300300008 each copper sample and each aluminum sample are 0.20 3290300300009 and 0.02 cm, respectively. The diameter of all the 3290300300010 samples is 2.00 cm. 3290300300011 DETECTOR (HPGE) A low-background high-purity germanium (HPGe) 3290300300012 detector (ORTEC, 46-TP41590A, diameter 82 mm, length 3290300300013 55.4 mm). The HPGe detector was pre-calibrated for 3290300300014 energy and detection efficiency using standard gamma 3290300300015 sources of 60Co and 137Cs. 3290300300016 METHOD (ACTIV) For each neutron energy, the samples were 3290300300017 irradiated for about 10h. The three aluminum samples 3290300300018 were measured separately with each measurement 3290300300019 duration of about 10 min after the cooling of about 3290300300020 60 min. The two copper samples were measured 3290300300021 simultaneously (one on top of another) using the HPGe 3290300300022 detector after the cooling of about 30 days, and they 3290300300023 were measured twice (with their positions exchanged) 3290300300024 in two runs with both measurement durations of about 3290300300025 48 h. 3290300300026 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 3290300300027 MONIT-REF (,D.A.Brown+,J,NDS,148,1,2018) ENDF/B-VIII.0 library 3290300300028 ERR-ANALYS (ERR-T) Total uncertainty 3290300300029 (ERR-1) The number of the 27Al nucleus in each 3290300300030 aluminum sample. 3290300300031 (ERR-2) The total numbers of the 63Cu nucleus in the 3290300300032 two copper samples. 3290300300033 (ERR-3,1.3,1.6) The count of the full-energy peak of 3290300300034 1.368 MeV gamma-ray from 24Na. 3290300300035 (ERR-4,2.4,2.8) The count of the full-energy peak 3290300300036 with an energy of 1.322 MeV. 3290300300037 (ERR-5) The ratio of the full-energy peak 3290300300038 efficiencies of the HPGe detector for the 3290300300039 characteristic gamma rays. 3290300300040 (ERR-6) The ratio of the neutron flux fluctuation 3290300300041 factor. 3290300300042 (ERR-7) The ratio of activity correction factor for 3290300300043 the self-absorption of the sample and the 3290300300044 experimental geometry of the HPGe detector with 3290300300045 respect to the sample. 3290300300046 (MONIT-ERR,1.4,2.1) The cross section of the 3290300300047 27Al(n,a)24Na reaction. 3290300300048 STATUS (TABLE,,Jie Liu+,J,JP/G,50,045106,2023) Table 5 3290300300049 (COREL,32903002) Data from outgoing alpha detection 3290300300050 ENDBIB 48 0 3290300300051 COMMON 5 3 3290300300052 ERR-1 ERR-2 ERR-5 ERR-6 ERR-7 3290300300053 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3290300300054 1.0 1.0 1.0 1.0 5.4 3290300300055 ENDCOMMON 3 0 3290300300056 DATA 4 2 3290300300057 EN EN-RSL-HW DATA ERR-T 3290300300058 MEV MEV MB MB 3290300300059 8.50 0.15 22.48 1.51 3290300300060 10.50 0.17 33.51 2.21 3290300300061 ENDDATA 4 0 3290300300062 ENDSUBENT 61 0 3290300399999 ENDENTRY 3 0 3290399999999