ENTRY 32873 20221018 3287300000001 SUBENT 32873001 20221018 20231011 3287300100001 BIB 14 46 3287300100002 TITLE Cross section of the 232Th(n,f) reaction in the MeV 3287300100003 neutron energy region 3287300100004 AUTHOR (Yu.M.Gledenov,Zengqi Cui,Jie Liu,Haoyu Jiang, 3287300100005 Yiwei Hu,Haofan Bai,Jinxiang Chen,Guohui Zhang, 3287300100006 E.Sansarbayar,G.Khuukhenkhuu,L.Krupa,I.Chuprakov, 3287300100007 Yinlu Han,Xichao Ruan,Hanxiong Huang,Jie Ren) 3287300100008 INSTITUTE (4ZZZDUB,3CPRBJG,3MGLNUM,3CZRCTI,4KASATN,4KASKAZ, 3287300100009 3CPRAEP) 3287300100010 REFERENCE (J,EPJ/A,58,86,2022) 3287300100011 #doi:10.1140/epja/s10050-022-00716-8 3287300100012 FACILITY (VDG,3CPRBJG) 4.5 MV Van de Graaff accelerator 3287300100013 4.20 - 5.50 MeV neutron energies 3287300100014 (VDGT,3CPRAEP) HI-13 tandem accelerator 3287300100015 8.50 - 11.50 MeV neutron energies 3287300100016 INC-SOURCE (D-D) The deuteron beam current was about 2.0 uA 3287300100017 during both measurements. 3287300100018 INC-SPECT (EN-RSL-HW) Standard deviation of the main neutron 3287300100019 peak from Gaussian fitting 3287300100020 DETECTOR (STANK) A EJ309 scintillator detector was used for the 3287300100021 detection of the neutron energy spectrum at the 3287300100022 sample position using unfolding method. 3287300100023 (IOCH) A twin grid ionization chamber (GIC) was used 3287300100024 as the charged particle detector. The distance from 3287300100025 the cathode to the grid was 6.1 cm. The working gas 3287300100026 of the GIC was Ar + CH4 (10%) with the pressure of 3287300100027 1.1 bar for both experiments. The high voltages 3287300100028 applied on the cathode and anodes were -1200 V and 3287300100029 +600 V and the grid electrodes were grounded for all 3287300100030 measurements. 3287300100031 SAMPLE A 232Th(OH)4 sample and a 238U3O8 sample were 3287300100032 prepared each on a tantalum foil 0.10 mm in thickness. 3287300100033 For 232Th(OH)4, isotopic enrichment was about 100%, 3287300100034 diameter was 44.0 mm, thickness was 601.9 ug/cm2, and 3287300100035 number of nuclei was 1.837E19. 3287300100036 For 238U3O8, isotopic enrichment was 99.999%, 3287300100037 diameter was 43.0 mm, thickness was 600.8 ug/cm2, and 3287300100038 number of nuclei was 1.872E19. 3287300100039 MONITOR (92-U-238(N,F),,SIG) 3287300100040 MONIT-REF (,,J,NDS,148,143,2018) 3287300100041 ERR-ANALYS (ERR-1) Number of 232Th nuclei 3287300100042 (ERR-2) Number of 238U nuclei 3287300100043 2(ERR-T) The total uncertainty 3287300100044 (MONIT-ERR) 238U(n,f) cross section 3287300100045 STATUS (TABLE) Data presented by author 3287300100046 HISTORY (20221018C) Jimin Wang (CNDC) 3287300100047 (20221107R) Data received from Zengqi Cui 3287300100048 ENDBIB 46 0 3287300100049 COMMON 2 3 3287300100050 ERR-1 ERR-2 3287300100051 PER-CENT PER-CENT 3287300100052 2.09 0.96 3287300100053 ENDCOMMON 3 0 3287300100054 ENDSUBENT 53 0 3287300199999 SUBENT 32873002 20221018 20231011 3287300200001 BIB 4 9 3287300200002 REACTION 1((90-TH-232(N,F),,SIG)/(92-U-238(N,F),,SIG)) 3287300200003 2(90-TH-232(N,F),,SIG) 3287300200004 METHOD Detection of forward fission events 3287300200005 ERR-ANALYS (ERR-3) Net counts for 232Th(n,f) 3287300200006 (ERR-4) Net counts for 238U(n,f) 3287300200007 (ERR-5) Fission fragment detection efficiency 3287300200008 (ERR-6) Low energy neutron background 3287300200009 (ERR-7) The ratio of the average neutron flux 3287300200010 STATUS (COREL,32873003) Data from backward fission events 3287300200011 ENDBIB 9 0 3287300200012 NOCOMMON 0 0 3287300200013 DATA 11 12 3287300200014 EN EN-RSL-HW DATA 1DATA 2ERR-T 2ERR-3 3287300200015 ERR-4 ERR-5 ERR-6 ERR-7 MONIT-ERR 2 3287300200016 MEV PER-CENT NO-DIM B PER-CENT PER-CENT 3287300200017 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3287300200018 4.20 3.41 0.252 0.141 3.73 0.93 3287300200019 0.44 2.31 0.42 0.30 1.4 3287300200020 4.50 2.63 0.258 0.145 4.14 0.97 3287300200021 0.47 2.81 0.85 0.33 1.0 3287300200022 4.75 2.14 0.258 0.145 4.03 0.92 3287300200023 0.44 2.66 0.88 0.34 1.0 3287300200024 5.00 1.41 0.262 0.144 4.27 1.03 3287300200025 0.49 2.93 0.97 0.42 1.0 3287300200026 5.25 1.23 0.259 0.143 4.15 1.03 3287300200027 0.49 2.73 1.02 0.38 1.0 3287300200028 5.50 0.92 0.259 0.142 4.32 0.75 3287300200029 0.35 3.07 1.05 0.43 1.0 3287300200030 8.50 0.75 0.353 0.358 4.93 0.62 3287300200031 0.36 3.20 2.47 0.49 1.40 3287300200032 9.50 0.58 0.318 0.323 5.42 0.61 3287300200033 0.32 3.30 3.22 0.48 1.45 3287300200034 10.00 1.12 0.315 0.318 5.30 0.52 3287300200035 0.24 3.27 3.01 0.68 1.50 3287300200036 10.50 0.79 0.313 0.316 5.72 0.63 3287300200037 0.35 3.54 3.44 0.57 1.50 3287300200038 11.00 0.59 0.307 0.310 5.66 0.46 3287300200039 0.30 3.67 3.21 0.68 1.50 3287300200040 11.50 0.46 0.306 0.308 5.56 0.51 3287300200041 0.33 3.63 3.06 0.68 1.50 3287300200042 ENDDATA 28 0 3287300200043 ENDSUBENT 42 0 3287300299999 SUBENT 32873003 20221018 20231011 3287300300001 BIB 4 9 3287300300002 REACTION 1((90-TH-232(N,F),,SIG)/(92-U-238(N,F),,SIG)) 3287300300003 2(90-TH-232(N,F),,SIG) 3287300300004 METHOD Detection of backward fission events 3287300300005 ERR-ANALYS (ERR-3) Net counts for 232Th(n,f) 3287300300006 (ERR-4) Net counts for 238U(n,f) 3287300300007 (ERR-5) Fission fragment detection efficiency 3287300300008 (ERR-6) Low energy neutron background 3287300300009 (ERR-7) The ratio of the average neutron flux 3287300300010 STATUS (COREL,32873002) Data from forward fission events 3287300300011 ENDBIB 9 0 3287300300012 NOCOMMON 0 0 3287300300013 DATA 11 12 3287300300014 EN EN-RSL-HW DATA 1DATA 2ERR-T 2ERR-3 3287300300015 ERR-4 ERR-5 ERR-6 ERR-7 MONIT-ERR 2 3287300300016 MEV PER-CENT NO-DIM B PER-CENT PER-CENT 3287300300017 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3287300300018 4.20 3.41 0.254 0.142 3.75 0.89 3287300300019 0.42 2.35 0.43 0.32 1.4 3287300300020 4.50 2.63 0.259 0.146 4.19 0.98 3287300300021 0.47 2.88 0.84 0.38 1.0 3287300300022 4.75 2.14 0.259 0.145 4.01 0.87 3287300300023 0.41 2.67 0.81 0.31 1.0 3287300300024 5.00 1.41 0.264 0.145 4.27 1.01 3287300300025 0.48 2.95 0.98 0.32 1.0 3287300300026 5.25 1.23 0.260 0.143 1.45 0.98 3287300300027 0.47 2.77 0.99 0.34 1.0 3287300300028 5.50 0.92 0.259 0.142 4.24 0.80 3287300300029 0.37 2.93 1.09 0.40 1.0 3287300300030 8.50 0.75 0.347 0.353 4.98 0.60 3287300300031 0.34 3.21 2.51 0.69 1.40 3287300300032 9.50 0.58 0.315 0.319 5.46 0.70 3287300300033 0.38 3.21 3.30 0.74 1.45 3287300300034 10.00 1.12 0.310 0.313 5.30 0.53 3287300300035 0.27 3.70 2.42 0.80 1.50 3287300300036 10.50 0.79 0.307 0.310 5.89 0.57 3287300300037 0.30 3.44 3.79 0.70 1.50 3287300300038 11.00 0.59 0.302 0.304 5.53 0.62 3287300300039 0.27 3.40 3.21 0.80 1.50 3287300300040 11.50 0.46 0.300 0.302 5.56 0.55 3287300300041 0.28 3.60 3.06 0.80 1.50 3287300300042 ENDDATA 28 0 3287300300043 ENDSUBENT 42 0 3287300399999 SUBENT 32873004 20221018 20231011 3287300400001 BIB 3 5 3287300400002 REACTION 1((90-TH-232(N,F),,SIG,,AV)/(92-U-238(N,F),,SIG,,AV)) 3287300400003 2(90-TH-232(N,F),,SIG,,AV) 3287300400004 ANALYSIS The average of forward and backward fission events 3287300400005 STATUS (DEP,32837002) Data from forward fission events 3287300400006 (DEP,32837003) Data from backward fission events 3287300400007 ENDBIB 5 0 3287300400008 NOCOMMON 0 0 3287300400009 DATA 6 12 3287300400010 EN EN-RSL-HW DATA 1DATA 2ERR-T 2MONIT-ERR 23287300400011 MEV PER-CENT NO-DIM B PER-CENT PER-CENT 3287300400012 4.20 3.41 0.253 0.142 3.74 1.4 3287300400013 4.50 2.63 0.259 0.146 4.17 1.0 3287300400014 4.75 2.14 0.259 0.145 4.02 1.0 3287300400015 5.00 1.41 0.263 0.145 4.27 1.0 3287300400016 5.25 1.23 0.259 0.143 4.15 1.0 3287300400017 5.50 0.92 0.259 0.142 4.28 1.0 3287300400018 8.50 0.75 0.350 0.356 4.93 1.40 3287300400019 9.50 0.58 0.317 0.321 5.41 1.45 3287300400020 10.00 1.12 0.312 0.316 5.27 1.50 3287300400021 10.50 0.79 0.310 0.313 5.78 1.50 3287300400022 11.00 0.59 0.305 0.307 5.58 1.50 3287300400023 11.50 0.46 0.303 0.305 5.54 1.50 3287300400024 ENDDATA 14 0 3287300400025 ENDSUBENT 24 0 3287300499999 ENDENTRY 4 0 3287399999999