ENTRY 40956 20160604 41764095600000001 SUBENT 40956001 20160604 41764095600100001 BIB 15 51 4095600100002 INSTITUTE (4RUSFEI,4RUSMIF) 4095600100003 REFERENCE (J,SJA,63,721,1987) Engl.transl.of AE,63,207,1987 4095600100004 (J,AE,63,(3),207,1987) Data are given 4095600100005 AUTHOR (A.V.Bushuev,A.V.Zvonarev,V.A.Kolyzhenkov, 4095600100006 V.P.Netsvet,V.N.Ozerkov,M.Yu.Semenov,N.V.Skorikov, 4095600100007 A.M.Tsibulya,V.V.Chachin,V.S.Shkol'nik) 4095600100008 TITLE Determination of the cross-sections for some 4095600100009 neutron reactions with structural materials in 4095600100010 the BN-350 reactor core 4095600100011 FACILITY (REAC,4RUSFEI) Fast reactor BN-350 of the Shevchenko 4095600100012 nuclear electric station 4095600100013 LP-4900 analyzer. 4095600100014 INC-SPECT Neutron spectrum in the section of large 4095600100015 enrichment of the fast reactor 'BN-350'; 4095600100016 Integrated neutron flux of 5 x 10**18 /cm2 4095600100017 SAMPLE Metallic uranium, U-238 content is 8.53%, 4095600100018 U-235 content is 90.07% 4095600100019 METHOD (ACTIV) Method of activation 4095600100020 DETECTOR (GELI) For gamma-ray spectra measurement. 4095600100021 20cm3, resolution 4 keV at 662 keV. 4095600100022 ANALYSIS (AREA) Gamma-rays line area was measured 4095600100023 MONITOR (92-U-235(N,F)57-LA-140,,SIG) 4095600100024 Yield of La-140 6.03E-2 4095600100025 DECAY-MON (57-LA-140,40.24HR,DG,1596.5,0.9995) 4095600100026 ERR-ANALYS (ERR-S,1.5,2.0) Statistical error 4095600100027 (ERR-1,2.0,2.5) Error of the gamma detector's 4095600100028 efficiency determination 4095600100029 (ERR-2,1.0,1.5) Error of the reduction to unified 4095600100030 geometry 4095600100031 (ERR-3,1.,3.) Error due to the nuclear data used 4095600100032 (ERR-4,1.0,1.5) Error due to the samples' weighting 4095600100033 (ERR-T) Total error 4095600100034 STATUS (TABLE) Data from AE,63,(3),207,1987; 4095600100035 Data declared as preliminary in 1988. 4095600100036 (APRVD) Kolyzhenkov, 1888/09/14 4095600100037 HISTORY (19880708C) Compiled at the CJD 4095600100038 (19880915A) Data declared as preliminary by Tsibulya 4095600100039 Several numerical errors corrected 4095600100040 (19900720A) Data quality is revised and cross-sections4095600100041 given in Subents 002 - 006 split in two Subents each 4095600100042 (19920727A) Incident neutron energy changed from 1 to 4095600100043 1.3 MeV in Subent 001 - 009,reference code corrected. 4095600100044 Decay particles added to DECAY-DATA in Subents 002-005 4095600100045 (20010316A) Date corrected 4095600100046 (20160604U) SD:Updated to new date formats,lower case. 4095600100047 Ref. SJA,63,721,1987 was added. Title and list of 4095600100048 authors update following SJA,63,721,1987. DECAY-DATA 4095600100049 corrected in Subent 008. STATUS 'PRELIM' -> TABLE. 4095600100050 (20170710U) M.M. Previous correction of SD was 4095600100051 checked at CJD. ERR-ANALYS was corrected . 4095600100052 DATA-ERR -> ERR-T 4095600100053 ENDBIB 51 0 4095600100054 NOCOMMON 0 0 4095600100055 ENDSUBENT 54 0 4095600199999 SUBENT 40956002 20160604 41764095600200001 BIB 6 9 4095600200002 REACTION ((26-FE-54(N,P)25-MN-54,,SIG,,FST)/ 4095600200003 (92-U-235(N,F),,SIG,,FST)) averaged over reactor's 4095600200004 BN-350 neutron spectrum 4095600200005 INC-SPECT neutron spectrum in the core of the BN-350 reactor. 4095600200006 SAMPLE (26-FE-54,ENR=0.998) Metallic, Fe-54 content is 99.8% 4095600200007 DECAY-DATA (25-MN-54,312.6D,DG,834.8,.9998) 4095600200008 STATUS (TABLE) Table 2 of SJA,63,721,1987 4095600200009 HISTORY (19920727A) Incident neutron energy changed. 'DG' in 4095600200010 SF3 of decay-data added 4095600200011 ENDBIB 9 0 4095600200012 NOCOMMON 0 0 4095600200013 DATA 3 1 4095600200014 EN-DUMMY DATA ERR-T 4095600200015 EV NO-DIM NO-DIM 4095600200016 1.3 E+06 6.7 E-03 6. E-04 4095600200017 ENDDATA 3 0 4095600200018 ENDSUBENT 17 0 4095600299999 SUBENT 40956003 20160604 41764095600300001 BIB 6 9 4095600300002 REACTION ((26-FE-56(N,P)25-MN-56,,SIG,,FST)/ 4095600300003 (92-U-235(N,F),,SIG,,FST)) averaged over reactor's 4095600300004 BN-350 neutron spectrum 4095600300005 INC-SPECT neutron spectrum in the core of the BN-350 reactor. 4095600300006 SAMPLE (26-FE-56,ENR=0.999) Metallic, Fe-56 content is 99.9% 4095600300007 DECAY-DATA (25-MN-56,2.578HR,DG,846.6,.990) 4095600300008 STATUS (TABLE) Table 2 of SJA,63,721,1987 4095600300009 HISTORY (19920727A) Incident neutron energy changed. 'DG' in 4095600300010 SF3 of decay-data added 4095600300011 ENDBIB 9 0 4095600300012 NOCOMMON 0 0 4095600300013 DATA 3 1 4095600300014 EN-DUMMY DATA ERR-T 4095600300015 EV NO-DIM NO-DIM 4095600300016 1.3 E+06 7.1 E-05 6. E-06 4095600300017 ENDDATA 3 0 4095600300018 ENDSUBENT 17 0 4095600399999 SUBENT 40956004 20160604 41764095600400001 BIB 6 9 4095600400002 REACTION ((26-FE-54(N,A)24-CR-51,,SIG,,FST)/ 4095600400003 (92-U-235(N,F),,SIG,,FST)) averaged over reactor's 4095600400004 BN-350 neutron spectrum 4095600400005 INC-SPECT neutron spectrum in the core of the BN-350 reactor. 4095600400006 SAMPLE (26-FE-54,ENR=0.998) Metallic, Fe-54 content is 99.8% 4095600400007 DECAY-DATA (24-CR-51,27.73D,DG,320.1,.0983) 4095600400008 STATUS (TABLE) Table 2 of SJA,63,721,1987 4095600400009 HISTORY (19920727A) Incident neutron energy changed. 'DG' in 4095600400010 SF3 of decay-data added 4095600400011 ENDBIB 9 0 4095600400012 NOCOMMON 0 0 4095600400013 DATA 3 1 4095600400014 EN-DUMMY DATA ERR-T 4095600400015 EV NO-DIM NO-DIM 4095600400016 1.3 E+06 4.73E-05 3.3 E-06 4095600400017 ENDDATA 3 0 4095600400018 ENDSUBENT 17 0 4095600499999 SUBENT 40956005 20160604 41764095600500001 BIB 6 9 4095600500002 REACTION ((28-NI-58(N,P)27-CO-58,,SIG,,FST)/ 4095600500003 (92-U-235(N,F),,SIG,,FST)) averaged over reactor's 4095600500004 BN-350 neutron spectrum 4095600500005 INC-SPECT neutron spectrum in the core of the BN-350 reactor. 4095600500006 SAMPLE Metallic, natural nickel 4095600500007 DECAY-DATA (27-CO-58-G,70.78D,DG,812.2,0.9945) 4095600500008 STATUS (TABLE) Table 2 of SJA,63,721,1987 4095600500009 HISTORY (19920727A) Incident neutron energy changed. 'DG' in 4095600500010 SF3 of decay-data added 4095600500011 ENDBIB 9 0 4095600500012 NOCOMMON 0 0 4095600500013 DATA 3 1 4095600500014 EN-DUMMY DATA ERR-T 4095600500015 EV NO-DIM NO-DIM 4095600500016 1.3 E+06 9.3 E-03 6. E-04 4095600500017 ENDDATA 3 0 4095600500018 ENDSUBENT 17 0 4095600599999 SUBENT 40956006 20160604 41764095600600001 BIB 5 7 4095600600002 REACTION ((27-CO-59(N,P)26-FE-59,,SIG,,FST)/ 4095600600003 (92-U-235(N,F),,SIG,,FST)) averaged over reactor's 4095600600004 bn-350 neutron spectrum 4095600600005 INC-SPECT neutron spectrum in the core of the BN-350 reactor. 4095600600006 SAMPLE (27-CO-59,NAT=1.) Metallic, C0-50 content is 100.% 4095600600007 STATUS (TABLE) Table 2 of SJA,63,721,1987 4095600600008 HISTORY (19920727A) Incident neutron energy changed. 4095600600009 ENDBIB 7 0 4095600600010 NOCOMMON 0 0 4095600600011 DATA 3 1 4095600600012 EN-DUMMY DATA ERR-T 4095600600013 EV NO-DIM NO-DIM 4095600600014 1.3 E+06 1.43E-04 1.2E-05 4095600600015 ENDDATA 3 0 4095600600016 ENDSUBENT 15 0 4095600699999 SUBENT 40956007 20160604 41764095600700001 BIB 6 9 4095600700002 REACTION ((42-MO-92(N,P)41-NB-92-M,,SIG,,FST)/ 4095600700003 (92-U-235(N,F),,SIG,,FST)) Averaged over reactor's 4095600700004 BN-350 neutron spectrum 4095600700005 INC-SPECT neutron spectrum in the core of the BN-350 reactor. 4095600700006 SAMPLE Metallic, natural mixture of isotopes 4095600700007 DECAY-DATA (41-NB-92-M,10.13D,DG,684.0,0.991) 4095600700008 STATUS (TABLE) Table 2 of SJA,63,721,1987 4095600700009 HISTORY (19920727A) Incident neutron energy changed. 'DG' in 4095600700010 SF3 of decay-data added 4095600700011 ENDBIB 9 0 4095600700012 NOCOMMON 0 0 4095600700013 DATA 3 1 4095600700014 EN-DUMMY DATA ERR-T 4095600700015 EV NO-DIM NO-DIM 4095600700016 1.3 E+06 2.60E-04 0.20E-04 4095600700017 ENDDATA 3 0 4095600700018 ENDSUBENT 17 0 4095600799999 SUBENT 40956008 20160604 41764095600800001 BIB 6 10 4095600800002 REACTION ((25-MN-55(N,G)25-MN-56,,SIG,,FST)/ 4095600800003 (92-U-235(N,F),,SIG,,FST)) averaged over reactor's 4095600800004 BN-350 neutron spectrum 4095600800005 INC-SPECT neutron spectrum in the core of the BN-350 reactor. 4095600800006 SAMPLE (25-MN-55,NAT=1.) Metallic, Mn-55 content is 100.% 4095600800007 DECAY-DATA (25-MN-56,2.578HR,DG,846.6,0.99) 4095600800008 STATUS (TABLE) Table 2 of SJA,63,721,1987 4095600800009 HISTORY (19920727A) Incident neutron energy changed. 'DG' in 4095600800010 SF3 of decay-data added 4095600800011 (20160604A) SD: hl=2.578yr -> 2.578hr in DECAY-DATA. 4095600800012 ENDBIB 10 0 4095600800013 NOCOMMON 0 0 4095600800014 DATA 3 1 4095600800015 EN-DUMMY DATA ERR-T 4095600800016 EV NO-DIM NO-DIM 4095600800017 1.3 E+06 1.5E-02 0.1E-02 4095600800018 ENDDATA 3 0 4095600800019 ENDSUBENT 18 0 4095600899999 SUBENT 40956009 20160604 41764095600900001 BIB 7 14 4095600900002 REACTION ((27-CO-59(N,G)27-CO-60,,SIG,,FST)/ 4095600900003 (92-U-235(N,F),,SIG,,FST)) averaged over reactor's 4095600900004 BN-350 core neutron spectrum 4095600900005 INC-SPECT Neutron spectrum in the core of the BN-350 reactor. 4095600900006 SAMPLE (27-CO-59,NAT=1.) Metallic, C0-50 content is 100.% 4095600900007 DECAY-DATA (27-CO-60,5.272YR,DG,1173.2,0.9987) 4095600900008 COMMENT Of compiler. Co-59 HL 5.272d given in the article is 4095600900009 too short. HL 1925.28d is in J.K.Tuli,Nuclear Wallet 4095600900010 Cards, 2011 . Probably a misprint was done in HL units:4095600900011 days -> years. This correction was done in DECAY-DATA. 4095600900012 STATUS (TABLE) Table 2 of SJA,63,721,1987 4095600900013 HISTORY (19920727A) Incident neutron energy changed. 'DG' in 4095600900014 SF3 of DECAY-DATA added 4095600900015 (20160604A) D -> YR , see comment. 4095600900016 ENDBIB 14 0 4095600900017 NOCOMMON 0 0 4095600900018 DATA 3 1 4095600900019 EN-DUMMY DATA ERR-T 4095600900020 EV NO-DIM NO-DIM 4095600900021 1.3 E+06 1.74E-02 1.3E-03 4095600900022 ENDDATA 3 0 4095600900023 ENDSUBENT 22 0 4095600999999 SUBENT 40956010 20160604 41764095601000001 BIB 8 9 4095601000002 REACTION (26-FE-54(N,P)25-MN-54,,SIG,,FIS) 4095601000003 INC-SPECT U-238 fission neutron spectrum. 4095601000004 SAMPLE (26-FE-54,ENR=0.998) Metallic, Fe-54 content is 99.8% 4095601000005 ANALYSIS Data are recalculated on the fission spectrum 4095601000006 DECAY-DATA (25-MN-54,312.6D,DG,834.8,.9998) 4095601000007 ERR-ANALYS (ERR-5,7.,10.) Conversion ( to the fission spectrum) 4095601000008 error 4095601000009 STATUS (TABLE) Table 3 of SJA,63,721,1987 4095601000010 HISTORY (19900720C) 4095601000011 ENDBIB 9 0 4095601000012 NOCOMMON 0 0 4095601000013 DATA 3 1 4095601000014 EN-DUMMY DATA ERR-T 4095601000015 EV MB MB 4095601000016 1.00E+06 85.5 10.2 4095601000017 ENDDATA 3 0 4095601000018 ENDSUBENT 17 0 4095601099999 SUBENT 40956011 20160604 41764095601100001 BIB 8 9 4095601100002 REACTION (26-FE-56(N,P)25-MN-56,,SIG,,FIS) 4095601100003 INC-SPECT U-238 fission neutron spectrum. 4095601100004 SAMPLE (26-FE-56,ENR=0.9990) Metallic, Fe-56 content is 99.90%4095601100005 ANALYSIS Data are recalculated on the fission spectrum 4095601100006 DECAY-DATA (25-MN-56,2.578HR,DG,846.6,.990) 4095601100007 ERR-ANALYS (ERR-5,7.,10.) Conversion ( to the fission spectrum) 4095601100008 error 4095601100009 STATUS (TABLE) Table 3 of SJA,63,721,1987 4095601100010 HISTORY (19900720C) 4095601100011 ENDBIB 9 0 4095601100012 NOCOMMON 0 0 4095601100013 DATA 3 1 4095601100014 EN-DUMMY DATA ERR-T 4095601100015 EV MB MB 4095601100016 1.00E+06 1.20 0.15 4095601100017 ENDDATA 3 0 4095601100018 ENDSUBENT 17 0 4095601199999 SUBENT 40956012 20160604 41764095601200001 BIB 8 9 4095601200002 REACTION (26-FE-54(N,A)24-CR-51,,SIG,,FIS) 4095601200003 INC-SPECT U-238 fission neutron spectrum. 4095601200004 SAMPLE (26-FE-54,ENR=0.998) Metallic, Fe-54 content is 99.8% 4095601200005 ANALYSIS Data are recalculated on the fission spectrum 4095601200006 DECAY-DATA (24-CR-51,27.73D,DG,320.1,.0983) 4095601200007 ERR-ANALYS (ERR-5,7.,10.) Conversion ( to the fission spectrum) 4095601200008 error 4095601200009 STATUS (TABLE) Table 3 of SJA,63,721,1987 4095601200010 HISTORY (19900720C) 4095601200011 ENDBIB 9 0 4095601200012 NOCOMMON 0 0 4095601200013 DATA 3 1 4095601200014 EN-DUMMY DATA ERR-T 4095601200015 EV MB MB 4095601200016 1.00E+06 0.85 0.10 4095601200017 ENDDATA 3 0 4095601200018 ENDSUBENT 17 0 4095601299999 SUBENT 40956013 20160604 41764095601300001 BIB 8 9 4095601300002 REACTION (28-NI-58(N,P)27-CO-58,,SIG,,FIS) 4095601300003 INC-SPECT U-238 fission neutron spectrum. 4095601300004 SAMPLE Metallic, natural nickel 4095601300005 ANALYSIS Data are recalculated on the fission spectrum 4095601300006 DECAY-DATA (27-CO-58-G,70.78D,DG,812.2,.9945) 4095601300007 ERR-ANALYS (ERR-5,7.,10.) Conversion ( to the fission spectrum) 4095601300008 error 4095601300009 STATUS (TABLE) Table 3 of SJA,63,721,1987 4095601300010 HISTORY (19900720C) 4095601300011 ENDBIB 9 0 4095601300012 NOCOMMON 0 0 4095601300013 DATA 3 1 4095601300014 EN-DUMMY DATA ERR-T 4095601300015 EV MB MB 4095601300016 1.00E+06 103.3 10.0 4095601300017 ENDDATA 3 0 4095601300018 ENDSUBENT 17 0 4095601399999 SUBENT 40956014 20160604 41764095601400001 BIB 7 8 4095601400002 REACTION (27-CO-59(N,P)26-FE-59,,SIG,,FIS,DERIV) 4095601400003 INC-SPECT U-238 fission neutron spectrum. 4095601400004 SAMPLE (27-CO-59,NAT=1.) Metallic, C0-50 content is 100.% 4095601400005 ANALYSIS Data are recalculated on the fission spectrum 4095601400006 ERR-ANALYS (ERR-5,7.,10.) Conversion ( to the fission spectrum) 4095601400007 error 4095601400008 STATUS (TABLE) Table 3 of SJA,63,721,1987 4095601400009 HISTORY (19900720C) 4095601400010 ENDBIB 8 0 4095601400011 NOCOMMON 0 0 4095601400012 DATA 3 1 4095601400013 EN-DUMMY DATA ERR-T 4095601400014 EV MB MB 4095601400015 1.00E+06 2.1 0.3 4095601400016 ENDDATA 3 0 4095601400017 ENDSUBENT 16 0 4095601499999 ENDENTRY 14 0 4095699999999