ENTRY 40131 20150109 41724013100000001 SUBENT 40131001 20150109 41724013100100001 BIB 17 59 4013100100002 INSTITUTE (4RUSFEI) 4013100100003 REFERENCE (J,SJA,29,1080,1970) Eng.trans.of AE,29,338,1970 4013100100004 (J,AE,29,(5),338,197011) Graphs, tables 4013100100005 (R,YFI-12,14,1971) abstract 4013100100006 (R,INDC(CCP)-030,11,1972) Engl.translation of YFI-12,144013100100007 AUTHOR (A.T.Bakov,V.G.Dvukhsherstnov,Yu.A.Kazanskii) 4013100100008 TITLE Cross sections for the production of gamma-rays 4013100100009 as a result of inelastic scattering of neutrons of 4013100100010 a fission spectrum 4013100100011 INC-SOURCE (REAC) Reactor RIZ 4013100100012 INC-SPECT Incident neutron spectrum was measured at the sample 4013100100013 position by the same spectrometer. Spectrum is 4013100100014 presented on Fig.3 of SJA,29,1080,1970 4013100100015 DETECTOR (SCIN) Scintillation spectrometer with stilbene crystal4013100100016 of 30 mm in diameter and 20 mm in height was used 4013100100017 PART-DET (G) Gammas were detected at the angle 90 degrees 4013100100018 relative to incident neutrons flux 4013100100019 SAMPLE The samples were planar and the angle of their 4013100100020 plane to the direction of the beam was 45.degr. 4013100100021 ANALYSIS (4PI1A) 4Pi times sigma at 90 degrees 4013100100022 MONITOR Sources of known activity Cs-137 with uncertainty 4013100100023 4-5% were used 4013100100024 CORRECTION Correction for background of neutrons and gammas 4013100100025 were 30-50% in continuous range and less in the 4013100100026 range of the single lines. Correction for multiscatte- 4013100100027 ring was calculated using method described in AE,4,244 4013100100028 correction for angular distribution of gamma-emission 4013100100029 was not introduced 4013100100030 REL-REF (M,,Yu.A.Kazanskii+,J,AE,20,143,1966) - 4013100100031 (M,,V.G.Dvukhsherstnov+,J,PTE,4,39,1969) - 4013100100032 Conversion of the amplitude distributions of the 4013100100033 pulses into energy spectra of the neutrons and the 4013100100034 gamma-rays described. 4013100100035 (M,,V.F.Turchin+,J,AE,4,244,1958) - Description of 4013100100036 multiscattering correction 4013100100037 (I,,S.P.Belov+,J,AE,18,136,1965) - Reactor description 4013100100038 (I,20938001,F.D.Brooks+,J,NIM,4,151,1959)) - 4013100100039 Scintillation spectrometer description 4013100100040 ERR-ANALYS (DATA-ERR) Root mean square error. 4013100100041 Error of inelastic scattering cross section was not 4013100100042 introduced . 4013100100043 (ERR-1) Uncertainty due to geometry factor and neutron 4013100100044 and gamma detection efficiencies ~ 7.% . 4013100100045 COMMENT Authors consider correction for angular distribution 4013100100046 to be less than 10-15% 4013100100047 STATUS (TABLE) Tbl.1 from AE,29,(5),338,1970 4013100100048 HISTORY (19730129C) Compiled at the centre 4013100100049 (20010307A) Updated to new date formats. Institute 4013100100050 updated. 4013100100051 (20150109A) SD: Updated to new date formats,lower case.4013100100052 Ref. on Engl.transl. of AE added. BIB updated. 4013100100053 (METHOD moved to REL-REF; SAMPLE moved to Sub.1 and 4013100100054 updated). 4013100100055 (20151020A) M.M. Articles were checked, BIB information4013100100056 was updated in TITLE,AUTHOR,INC-SPECT,ERR-ANALYS, 4013100100057 REFERENCE . 4013100100058 REACTION was corrected: 4013100100059 SIG,G,FIS -> DA,G,4PI/FIS - 4PI*SIG(90deg). 4013100100060 Angle 90 deg was added . 4013100100061 ENDBIB 59 0 4013100100062 COMMON 3 3 4013100100063 EN-DUMMY ANG ERR-1 4013100100064 MEV ADEG PER-CENT 4013100100065 1. 90. 7. 4013100100066 ENDCOMMON 3 0 4013100100067 ENDSUBENT 66 0 4013100199999 SUBENT 40131002 20150109 41724013100200001 BIB 1 1 4013100200002 REACTION (11-NA-23(N,INL)11-NA-23,PAR,DA,G,4PI/FIS) 4013100200003 ENDBIB 1 0 4013100200004 NOCOMMON 0 0 4013100200005 DATA 3 2 4013100200006 E DATA DATA-ERR 4013100200007 MEV B PER-CENT 4013100200008 4.4000E-01 5.0000E-01 3.0000E+01 4013100200009 1.6400E+00 1.5000E-01 1.7000E+01 4013100200010 ENDDATA 4 0 4013100200011 ENDSUBENT 10 0 4013100299999 SUBENT 40131003 20150109 41724013100300001 BIB 1 1 4013100300002 REACTION (13-AL-27(N,INL)13-AL-27,PAR,DA,G,4PI/FIS) 4013100300003 ENDBIB 1 0 4013100300004 NOCOMMON 0 0 4013100300005 DATA 3 6 4013100300006 E DATA DATA-ERR 4013100300007 MEV B PER-CENT 4013100300008 8.4000E-01 8.0000E-02 1.1000E+01 4013100300009 1.0100E+00 1.9000E-01 1.0000E+01 4013100300010 1.7300E+00 7.0000E-02 1.1000E+01 4013100300011 2.2100E+00 2.0000E-01 1.1000E+01 4013100300012 2.7300E+00 6.0000E-02 2.2000E+01 4013100300013 2.9800E+00 1.3000E-01 1.0000E+01 4013100300014 ENDDATA 8 0 4013100300015 ENDSUBENT 14 0 4013100399999 SUBENT 40131004 20150109 41724013100400001 BIB 2 3 4013100400002 REACTION (22-TI-0(N,INL)22-TI-0,PAR,DA,G,4PI/FIS) 4013100400003 HISTORY (20010307A) SF4 added to reaction. 4013100400004 Record with no data field deleted. 4013100400005 ENDBIB 3 0 4013100400006 NOCOMMON 0 0 4013100400007 DATA 3 2 4013100400008 E DATA DATA-ERR 4013100400009 MEV B PER-CENT 4013100400010 9.9000E-01 6.5000E-01 9.0000E+00 4013100400011 2.4300E+00 1.1000E-01 1.0000E+01 4013100400012 ENDDATA 4 0 4013100400013 ENDSUBENT 12 0 4013100499999 SUBENT 40131005 20150109 41724013100500001 BIB 2 2 4013100500002 REACTION (23-V-0(N,INL)23-V-0,PAR,DA,G,4PI/FIS) 4013100500003 HISTORY (20010307A) SF4 added to reaction. 4013100500004 ENDBIB 2 0 4013100500005 NOCOMMON 0 0 4013100500006 DATA 3 4 4013100500007 E DATA DATA-ERR 4013100500008 MEV B PER-CENT 4013100500009 9.2000E-01 1.0000E-01 1.0000E+01 4013100500010 1.6200E+00 2.8000E-01 1.0000E+01 4013100500011 1.8300E+00 1.6000E-01 1.0000E+01 4013100500012 3.6000E+00 1.0000E-01 1.7000E+01 4013100500013 ENDDATA 6 0 4013100500014 ENDSUBENT 13 0 4013100599999 SUBENT 40131006 20150109 41724013100600001 BIB 1 1 4013100600002 REACTION (25-MN-55(N,INL)25-MN-55,PAR,DA,G,4PI/FIS) 4013100600003 ENDBIB 1 0 4013100600004 NOCOMMON 0 0 4013100600005 DATA 3 6 4013100600006 E DATA DATA-ERR 4013100600007 MEV B PER-CENT 4013100600008 8.6000E-01 2.4000E-01 8.0000E+00 4013100600009 1.1600E+00 1.1000E-01 8.0000E+00 4013100600010 1.5300E+00 1.8000E-01 9.0000E+00 4013100600011 1.8800E+00 1.2000E-01 9.0000E+00 4013100600012 2.3000E+00 1.9000E-01 8.0000E+00 4013100600013 2.8500E+00 1.2000E-01 1.8000E+01 4013100600014 ENDDATA 8 0 4013100600015 ENDSUBENT 14 0 4013100699999 SUBENT 40131007 20150109 41724013100700001 BIB 2 2 4013100700002 REACTION (26-FE-0(N,INL)26-FE-0,PAR,DA,G,4PI/FIS) 4013100700003 HISTORY (20010307A) SF4 added to reaction. 4013100700004 ENDBIB 2 0 4013100700005 NOCOMMON 0 0 4013100700006 DATA 3 6 4013100700007 E DATA DATA-ERR 4013100700008 MEV B PER-CENT 4013100700009 8.5000E-01 7.4000E-01 7.0000E+00 4013100700010 1.2500E+00 2.5000E-01 8.0000E+00 4013100700011 1.8600E+00 2.2000E-01 1.0000E+01 4013100700012 2.1200E+00 2.0000E-01 8.0000E+00 4013100700013 2.6600E+00 1.6000E-01 1.8000E+01 4013100700014 3.6000E+00 2.6000E-01 1.8000E+01 4013100700015 ENDDATA 8 0 4013100700016 ENDSUBENT 15 0 4013100799999 SUBENT 40131008 20150109 41724013100800001 BIB 2 2 4013100800002 REACTION (28-NI-0(N,INL)28-NI-0,PAR,DA,G,4PI/FIS) 4013100800003 HISTORY (20010307A) SF4 added to reaction. 4013100800004 ENDBIB 2 0 4013100800005 NOCOMMON 0 0 4013100800006 DATA 3 3 4013100800007 E DATA DATA-ERR 4013100800008 MEV B PER-CENT 4013100800009 8.3000E-01 1.3000E-01 1.7000E+01 4013100800010 1.3300E+00 7.6000E-01 8.0000E+00 4013100800011 1.8000E+00 5.0000E-02 1.2000E+01 4013100800012 ENDDATA 5 0 4013100800013 ENDSUBENT 12 0 4013100899999 SUBENT 40131009 20150109 41724013100900001 BIB 2 2 4013100900002 REACTION (29-CU-0(N,INL)29-CU-0,PAR,DA,G,4PI/FIS) 4013100900003 HISTORY (20010307A) SF4 added to reaction. 4013100900004 ENDBIB 2 0 4013100900005 NOCOMMON 0 0 4013100900006 DATA 3 7 4013100900007 E DATA DATA-ERR 4013100900008 MEV B PER-CENT 4013100900009 6.7000E-01 1.4000E-01 1.0000E+01 4013100900010 7.6000E-01 7.0000E-02 1.2000E+01 4013100900011 9.7000E-01 4.4000E-01 8.0000E+00 4013100900012 1.1100E+00 2.9000E-01 1.0000E+01 4013100900013 1.4300E+00 4.4000E-01 8.0000E+00 4013100900014 1.5400E+00 7.0000E-02 1.0000E+01 4013100900015 2.0600E+00 4.0000E-02 2.0000E+01 4013100900016 ENDDATA 9 0 4013100900017 ENDSUBENT 16 0 4013100999999 SUBENT 40131010 20150109 41724013101000001 BIB 2 2 4013101000002 REACTION (30-ZN-0(N,INL)30-ZN-0,PAR,DA,G,4PI/FIS) 4013101000003 HISTORY (20010307A) SF4 added to reaction. 4013101000004 ENDBIB 2 0 4013101000005 NOCOMMON 0 0 4013101000006 DATA 3 4 4013101000007 E DATA DATA-ERR 4013101000008 MEV B PER-CENT 4013101000009 8.2000E-01 4.1000E-01 1.5000E+01 4013101000010 1.0200E+00 9.0000E-01 1.4000E+01 4013101000011 1.3800E+00 2.4000E-01 1.3000E+01 4013101000012 1.8500E+00 2.4000E-01 8.0000E+00 4013101000013 ENDDATA 6 0 4013101000014 ENDSUBENT 13 0 4013101099999 SUBENT 40131011 20150109 41724013101100001 BIB 2 2 4013101100002 REACTION (40-ZR-0(N,INL)40-ZR-0,PAR,DA,G,4PI/FIS) 4013101100003 HISTORY (20010307A) SF4 added to reaction. 4013101100004 ENDBIB 2 0 4013101100005 NOCOMMON 0 0 4013101100006 DATA 3 4 4013101100007 E DATA DATA-ERR 4013101100008 MEV B PER-CENT 4013101100009 9.3000E-01 5.1000E-01 9.0000E+00 4013101100010 1.2100E+00 7.0000E-02 1.1000E+01 4013101100011 1.4200E+00 1.1000E-01 1.4000E+01 4013101100012 2.2000E+00 5.1000E-01 8.0000E+00 4013101100013 ENDDATA 6 0 4013101100014 ENDSUBENT 13 0 4013101199999 SUBENT 40131012 20150109 41724013101200001 BIB 2 2 4013101200002 REACTION (82-PB-0(N,INL)82-PB-0,PAR,DA,G,4PI/FIS) 4013101200003 HISTORY (20010307A) SF4 added to reaction. 4013101200004 ENDBIB 2 0 4013101200005 NOCOMMON 0 0 4013101200006 DATA 4 3 4013101200007 E-MIN E-MAX DATA DATA-ERR 4013101200008 MEV MEV B PER-CENT 4013101200009 8.0000E-01 8.0000E-01 6.2000E-01 3.1000E+01 4013101200010 1.0000E+00 2.0000E+00 3.3000E-01 2.0000E+01 4013101200011 2.6200E+00 2.6200E+00 6.7000E-01 2.7000E+01 4013101200012 ENDDATA 5 0 4013101200013 ENDSUBENT 12 0 4013101299999 SUBENT 40131013 20150109 41724013101300001 BIB 1 1 4013101300002 REACTION (83-BI-209(N,INL)83-BI-209,PAR,DA,G,4PI/FIS) 4013101300003 ENDBIB 1 0 4013101300004 NOCOMMON 0 0 4013101300005 DATA 3 4 4013101300006 E DATA DATA-ERR 4013101300007 MEV B PER-CENT 4013101300008 7.0000E-01 2.6000E-01 3.0000E+01 4013101300009 9.0000E-01 4.9000E-01 9.0000E+00 4013101300010 1.6200E+00 6.2000E-01 9.0000E+00 4013101300011 2.6200E+00 4.6000E-01 2.7000E+01 4013101300012 ENDDATA 6 0 4013101300013 ENDSUBENT 12 0 4013101399999 SUBENT 40131014 20150109 41724013101400001 BIB 2 2 4013101400002 REACTION (92-U-238(N,INL)92-U-238,PAR,DA,G,4PI/FIS) 4013101400003 HISTORY (20010307A) Data sorted. 4013101400004 ENDBIB 2 0 4013101400005 NOCOMMON 0 0 4013101400006 DATA 4 3 4013101400007 E-MIN E-MAX DATA DATA-ERR 4013101400008 MEV MEV B PER-CENT 4013101400009 1.0000E+00 2.0000E+00 3.0000E+00 4013101400010 1.0600E+00 1.0600E+00 1.5400E+00 1.5000E+01 4013101400011 2.0000E+00 3.0000E+00 1.5000E+00 4013101400012 ENDDATA 5 0 4013101400013 ENDSUBENT 12 0 4013101499999 ENDENTRY 14 0 4013199999999