ENTRY 40950 20180202 41784095000000001 SUBENT 40950001 20180202 41784095000100001 BIB 11 20 4095000100002 INSTITUTE (4RUSFEI) 4095000100003 REFERENCE (J,AE,61,389,1986) Issue 5. 4095000100004 (J,SJA,61,973,1986) Engl.transl.of J,AE,61,389,1986 4095000100005 AUTHOR (R.K.Goncharov,A.V.Zvonarev,V.I.Ivanov,Yu.A.Kazanskii, 4095000100006 V.P.Netsvet,M.N.Nikolaev,V.B.Pavlovich,M.Yu.Semenov, 4095000100007 N.V.Skorikov,E.Ya.Smetanin,A.M.Tsibulya) 4095000100008 TITLE Determination of the 237Np(n,2n) reaction cross section4095000100009 in the core of the BN-350 reactor 4095000100010 FACILITY (REAC,4RUSFEI) BN-350 reactor 4095000100011 MONITOR Absolute measurement of the ratio 4095000100012 METHOD (ASPEC) Alpha-spectrometry of irradiated samples was 4095000100013 applied to measure Pu236/Pu238 isotopes ratio. 4095000100014 DECAY-DATA (93-NP-237,1.15E+5YR) 4095000100015 ERR-ANALYS (DATA-ERR) Error not explained in the article 4095000100016 REL-REF (D,10549001,C.Paulson+,J,NSE,55,24,1974) 4095000100017 HISTORY (19880602C) Compiled at the CJD 4095000100018 (20010315A) Date is corrected 4095000100019 (20180202U) M.M. Upper -> lower case correction. 4095000100020 Ref. J,SJA,61,973,1986 was added. 4095000100021 BIB information was updated. 4095000100022 ENDBIB 20 0 4095000100023 NOCOMMON 0 0 4095000100024 ENDSUBENT 23 0 4095000199999 SUBENT 40950002 20180202 41784095000200001 BIB 4 7 4095000200002 REACTION (((93-NP-237(N,2N)93-NP-236,,SIG,,FIS)+ 4095000200003 (93-NP-237(G,N)93-NP-236,,SIG,,FIS))/ 4095000200004 (93-NP-237(N,G)93-NP-238,,SIG,,FIS)) 4095000200005 INC-SPECT Reactor zone with low-fuel-enrichment, 4095000200006 fast neutron fission spectrum 4095000200007 SAMPLE Reactor fuel element 4095000200008 STATUS (TABLE) Table 1 of SJA,61,973,1986 4095000200009 ENDBIB 7 0 4095000200010 NOCOMMON 0 0 4095000200011 DATA 3 1 4095000200012 EN-DUMMY DATA DATA-ERR 4095000200013 MEV NO-DIM NO-DIM 4095000200014 1. 1.65 E-04 .09 E-04 4095000200015 ENDDATA 3 0 4095000200016 ENDSUBENT 15 0 4095000299999 SUBENT 40950003 20180202 41784095000300001 BIB 4 7 4095000300002 REACTION (((93-NP-237(N,2N)93-NP-236,,SIG,,FIS)+ 4095000300003 (93-NP-237(G,N)93-NP-236,,SIG,,FIS))/ 4095000300004 (93-NP-237(N,G)93-NP-238,,SIG,,FIS)) 4095000300005 INC-SPECT Fast neutron reactor spectrum in the reactor core 4095000300006 with high fuel enrichment 4095000300007 SAMPLE Reactor fuel element 4095000300008 STATUS (TABLE) Table 1 of SJA,61,973,1986 4095000300009 ENDBIB 7 0 4095000300010 NOCOMMON 0 0 4095000300011 DATA 3 1 4095000300012 EN-DUMMY DATA DATA-ERR 4095000300013 MEV NO-DIM NO-DIM 4095000300014 1. 2.55 E-04 .14 E-04 4095000300015 ENDDATA 3 0 4095000300016 ENDSUBENT 15 0 4095000399999 SUBENT 40950004 20180202 41784095000400001 BIB 4 7 4095000400002 REACTION (((93-NP-237(N,2N)93-NP-236,,SIG,,FIS)+ 4095000400003 (93-NP-237(G,N)93-NP-236,,SIG,,FIS))/ 4095000400004 (93-NP-237(N,G)93-NP-238,,SIG,,FIS)) 4095000400005 INC-SPECT Fast neutron reactor spectrum in the reactor core 4095000400006 with low fuel enrichment 4095000400007 SAMPLE Ampoule with Np-237 sample 4095000400008 STATUS (TABLE) Table 1 of SJA,61,973,1986 4095000400009 ENDBIB 7 0 4095000400010 NOCOMMON 0 0 4095000400011 DATA 3 1 4095000400012 EN-DUMMY DATA DATA-ERR 4095000400013 MEV NO-DIM NO-DIM 4095000400014 1. 1.69-04 .10 -04 4095000400015 ENDDATA 3 0 4095000400016 ENDSUBENT 15 0 4095000499999 SUBENT 40950005 20180202 41784095000500001 BIB 4 7 4095000500002 REACTION (((93-NP-237(N,2N)93-NP-236,,SIG,,FIS)+ 4095000500003 (93-NP-237(G,N)93-NP-236,,SIG,,FIS))/ 4095000500004 (93-NP-237(N,G)93-NP-238,,SIG,,FIS)) 4095000500005 INC-SPECT Fast neutron reactor spectrum in the reactor core 4095000500006 with high fuel enrichment 4095000500007 SAMPLE Ampoule with Np-237 sample 4095000500008 STATUS (TABLE) Table 1 of SJA,61,973,1986 4095000500009 ENDBIB 7 0 4095000500010 NOCOMMON 0 0 4095000500011 DATA 3 1 4095000500012 EN-DUMMY DATA DATA-ERR 4095000500013 MEV NO-DIM NO-DIM 4095000500014 1. 2.28E-04 .14 E-04 4095000500015 ENDDATA 3 0 4095000500016 ENDSUBENT 15 0 4095000599999 SUBENT 40950006 20180202 41784095000600001 BIB 4 7 4095000600002 REACTION (((93-NP-237(N,2N)93-NP-236,,SIG,,FIS)+ 4095000600003 (93-NP-237(G,N)93-NP-236,,SIG))/ 4095000600004 (93-NP-237(N,G)93-NP-238,,SIG,,FIS)) 4095000600005 INC-SPECT Fast neutron reactor spectrum in the reactor core 4095000600006 with high fuel enrichment 4095000600007 SAMPLE Ampoule with U-236 sample 4095000600008 STATUS (TABLE) Table 1 of SJA,61,973,1986 4095000600009 ENDBIB 7 0 4095000600010 NOCOMMON 0 0 4095000600011 DATA 3 1 4095000600012 EN-DUMMY DATA DATA-ERR 4095000600013 MEV NO-DIM NO-DIM 4095000600014 1. 2.43E-04 .18E-04 4095000600015 ENDDATA 3 0 4095000600016 ENDSUBENT 15 0 4095000699999 SUBENT 40950007 20180202 41784095000700001 BIB 4 6 4095000700002 REACTION (((93-NP-237(N,2N)93-NP-236,,SIG,,FIS)+ 4095000700003 (93-NP-237(G,N)93-NP-236,,SIG))/ 4095000700004 (93-NP-237(N,G)93-NP-238,,SIG,,FIS)) 4095000700005 INC-SPECT Neutron spectrum in the inner side-screen 4095000700006 SAMPLE Ampoule with Np-237 sample 4095000700007 STATUS (TABLE) Table 1 of SJA,61,973,1986 4095000700008 ENDBIB 6 0 4095000700009 NOCOMMON 0 0 4095000700010 DATA 3 1 4095000700011 EN-DUMMY DATA DATA-ERR 4095000700012 MEV NO-DIM NO-DIM 4095000700013 1. .62E-04 .07E-04 4095000700014 ENDDATA 3 0 4095000700015 ENDSUBENT 14 0 4095000799999 SUBENT 40950008 20180202 41784095000800001 BIB 4 7 4095000800002 REACTION (((93-NP-237(N,2N)93-NP-236,,SIG,,FIS)+ 4095000800003 (93-NP-237(G,N)93-NP-236,,SIG))/ 4095000800004 (93-NP-237(N,G)93-NP-238,,SIG,,FIS)) 4095000800005 INC-SPECT Neutron spectrum in the inner side-screen of the 4095000800006 reactor 4095000800007 SAMPLE Ampoule with U-236 sample 4095000800008 STATUS (TABLE) Table 1 of SJA,61,973,1986 4095000800009 ENDBIB 7 0 4095000800010 NOCOMMON 0 0 4095000800011 DATA 3 1 4095000800012 EN-DUMMY DATA DATA-ERR 4095000800013 MEV NO-DIM NO-DIM 4095000800014 1. .82E-04 .09E-04 4095000800015 ENDDATA 3 0 4095000800016 ENDSUBENT 15 0 4095000899999 SUBENT 40950009 20180202 41784095000900001 BIB 4 7 4095000900002 REACTION (((93-NP-237(N,2N)93-NP-236,,SIG,,FIS)+ 4095000900003 (93-NP-237(G,N)93-NP-236,,SIG))/ 4095000900004 (93-NP-237(N,G)93-NP-238,,SIG,,FIS)) 4095000900005 INC-SPECT Neutron spectrum of the outer side-screen of the 4095000900006 reactor 4095000900007 SAMPLE Ampoule with Np-237 sample 4095000900008 STATUS (TABLE) Table 1 of SJA,61,973,1986 4095000900009 ENDBIB 7 0 4095000900010 NOCOMMON 0 0 4095000900011 DATA 3 1 4095000900012 EN-DUMMY DATA DATA-ERR 4095000900013 MEV NO-DIM NO-DIM 4095000900014 1. .33E-04 4. E-06 4095000900015 ENDDATA 3 0 4095000900016 ENDSUBENT 15 0 4095000999999 ENDENTRY 9 0 4095099999999