ENTRY 32880 20251202 3288000000001 SUBENT 32880001 20251202 20260228 3288000100001 BIB 13 71 3288000100002 TITLE Cross sections of the 144Sm(n,a)141Nd reaction at 3288000100003 5.5 and 6.5 MeV 3288000100004 AUTHOR (Yu.M.Gledenov, M.V.Sedysheva, L.Krupa, E.Sansarbayar, 3288000100005 G.Khuukhenkhuu, Haoyu Jiang, Huaiyong Bai, Yi Lu, 3288000100006 Zengqi Cui, Jinxiang Chen, Guohui Zhang) 3288000100007 INSTITUTE (4ZZZDUB,3CZRCTI,3MGLNUM,3CPRBJG) 3288000100008 REFERENCE (S,ISINN-26,63,2019) 3288000100009 FACILITY (VDG,3CPRBJG) 4.5 MV Van de Graaff Accelerator 3288000100010 INC-SOURCE (D-D) The mono-energetic neutrons were generated 3288000100011 using energetic deuteron beam from the accelerator to 3288000100012 bombard a deuterium gas target. For neutron energies 3288000100013 of 5.5 and 6.5 MeV, the corresponding neutron energy 3288000100014 spreads (1 sigma) were 0.14 and 0.10 MeV, 3288000100015 respectively. The beam current was about 2.0 uA 3288000100016 throughout the measurement. 3288000100017 SAMPLE (62-SM-144,NAT=0.950) 3288000100018 +-----------------------------------------------------+3288000100019 Samples Material Isotopic Thickness Diameter 3288000100020 enrichment(%) (ug/cm2) (mm) 3288000100021 -------------------------------------------------------3288000100022 144Sm 144Sm2O3 95.0 4084 (Forward) 44.0 3288000100023 3177 (Backward) 44.0 3288000100024 238U 238U3O8 99.999 604.84 45.0 3288000100025 +-----------------------------------------------------+3288000100026 DETECTOR (BF3) The relative neutron flux was monitored using a 3288000100027 BF3 long counter. 3288000100028 (IOCH) The alpha-particle detector is a twin gridded 3288000100029 ionization chamber (GIC). Working gas of the GIC was 3288000100030 Kr + 2.83% CO2, and the pressure is 2.02 atm for the 3288000100031 alpha-particles to be stopped before reaching the 3288000100032 grids. 3288000100033 MONITOR (92-U-238(N,F),,SIG) 3288000100034 The 238U(n,f) reaction taken from IAEA Neutron Cross- 3288000100035 section References (2015). Pronyaev V., Simakov S., 3288000100036 Marcinkevicius B., University of Leeds, 158, 80, 2015 3288000100037 COMMENT The uncertainties in the forward/backward cross 3288000100038 section Sig(forward/backward) due to statistics, 3288000100039 valid-event-area of alpha-source events, alpha 3288000100040 particle detection efficiency, background reduction 3288000100041 for the forward/backward events Err(forward/backward) 3288000100042 is propagated to the corresponding uncertainty 3288000100043 Err(total) in the total cross section Sig(tot) by 3288000100044 Err(total)=sqrt((Sig(forward)*Err(forward))**2+ 3288000100045 (Sig(backward)*Err(backward))**2)/(Sig(forward) 3288000100046 +(Sig(backward)) 3288000100047 Where the Sig(forward) are 0.1295 mb at 5.5 MeV, 3288000100048 0.3011 mb at 6.5 MeV; the Sig(backward) are 3288000100049 0.0636 mb at 5.5 MeV, 0.1117 mb at 6.5 MeV. 3288000100050 ERR-ANALYS (ERR-T) The total uncertainty 3288000100051 (ERR-1) Statistical error of alpha-particles forward 3288000100052 (ERR-2) Statistical error of alpha-particles backward 3288000100053 (ERR-3) Valid-event-area of alpha-sources events 3288000100054 forward 3288000100055 (ERR-4) Valid-event-area of alpha-sources events 3288000100056 backward 3288000100057 (ERR-5) Detection efficiency of alpha-particles forward3288000100058 (ERR-6) Detection efficiency of alpha-particles 3288000100059 backward 3288000100060 (ERR-7) Background reduction forward 3288000100061 (ERR-8) Background reduction backward 3288000100062 (ERR-9) Background uncertainty forward 3288000100063 (ERR-10) Background uncertainty backward 3288000100064 (ERR-11) Neutron energy spreads for fission events 3288000100065 (ERR-12) Statistical error of fission events 3288000100066 (ERR-13) Detection efficiency for fission fragment 3288000100067 (ERR-14) Numbers of 238U nucleus 3288000100068 (ERR-15) Normalization of the BF3 counts 3288000100069 (ERR-16) Numbers of 144Sm nucleus 3288000100070 (MONIT-ERR) 238U(n,f) cross sections 3288000100071 STATUS (TABLE,,Yu.M.Gledenov+,S,ISINN-26,63,2019) Table 3 3288000100072 HISTORY (20251202C) Compiled by Xi Tao (CNDC) 3288000100073 ENDBIB 71 0 3288000100074 COMMON 3 3 3288000100075 ERR-14 ERR-16 MONIT-ERR 3288000100076 PER-CENT PER-CENT PER-CENT 3288000100077 0.45 1.00 0.70 3288000100078 ENDCOMMON 3 0 3288000100079 ENDSUBENT 78 0 3288000199999 SUBENT 32880002 20251202 20260228 3288000200001 BIB 1 1 3288000200002 REACTION (62-SM-144(N,A)60-ND-141,,SIG) 3288000200003 ENDBIB 1 0 3288000200004 NOCOMMON 0 0 3288000200005 DATA 18 2 3288000200006 EN EN-RSL DATA ERR-T ERR-1 ERR-2 3288000200007 ERR-3 ERR-4 ERR-5 ERR-6 ERR-7 ERR-8 3288000200008 ERR-9 ERR-10 ERR-11 ERR-12 ERR-13 ERR-15 3288000200009 MEV MEV MB PER-CENT PER-CENT PER-CENT 3288000200010 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3288000200011 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3288000200012 5.5 0.14 0.19 9.1 3.45 5.603288000200013 0.47 0.70 6.16 11.82 1.41 3.683288000200014 0.80 0.45 5.11 3.303288000200015 6.5 0.10 0.41 15.1 3.49 6.503288000200016 0.15 1.03 5.13 9.49 0.87 3.883288000200017 3.09 17.82 6.87 0.54 5.03 9.653288000200018 ENDDATA 12 0 3288000200019 ENDSUBENT 18 0 3288000299999 ENDENTRY 2 0 3288099999999