ENTRY 40550 20210224 41954055000000001 SUBENT 40550001 20210224 41954055000100001 BIB 10 24 4055000100002 TITLE Measurement of radiation-capture and fission 4055000100003 cross-sections and their ratio alfa for uranium-235 4055000100004 AUTHOR (G.V.Muradyan,G.I.Ustroev,Yu.G.Shchepkin, 4055000100005 Yu.G.Adamchuk,M.A.Voskanyan,L.Yu.Prokof'eva) 4055000100006 INSTITUTE (4RUSKUR) 4055000100007 REFERENCE ((C,77KIEV,3,119,1977)= 4055000100008 (R,INDC(CCP)-118,(3),119,1977)) 4055000100009 FACILITY (LINAC,4RUSKUR) Electron linear accelerator LEU-60 4055000100010 SAMPLE U sample weight 1.1925 gram, diameter 28.5 mm. 4055000100011 METHOD Multiplicity spectrometry method for 4055000100012 particles associated with capture and fission. 4055000100013 (FNB) Al (27 mm), B-10(0.3 g/cm3) constant filters. 4055000100014 Co, Na, Cu filters are additional. 4055000100015 DETECTOR (NAICR) 12-cells NaI(Tl) 4PI-detector 4055000100016 PART-DET (G,N) Gamma, neutrons were converted into gammas 4055000100017 by boron-10 converter 4055000100018 HISTORY (19771130C) Compiled at the centre 4055000100019 (19870623A) One author name corrected (Ustrojev to 4055000100020 Ustroev), data of SAN 002 superseded by 40581002 4055000100021 ISO-QUANT into REACTION converted 4055000100022 (20210224A) M.M. Upper -> lower case correction. 4055000100023 Dates were corrected for 4-digits year. 4055000100024 Ref. INDC(CCP)-118,(3),119,1977 was added. 4055000100025 BIB information was updated. 4055000100026 ENDBIB 24 0 4055000100027 NOCOMMON 0 0 4055000100028 ENDSUBENT 27 0 4055000199999 SUBENT 40550002 20210224 41954055000200001 BIB 3 5 4055000200002 REACTION (92-U-235(N,ABS),,ALF) 4055000200003 ERR-ANALYS (ERR-S,,2.) Relative statistical error 4055000200004 STATUS (SPSDD,40581002) New measurement by 46-sectional 4055000200005 NaI(Tl) detector 4055000200006 (TABLE) Table of INDC(CCP)-118,v.3,p.119,1977 4055000200007 ENDBIB 5 0 4055000200008 NOCOMMON 0 0 4055000200009 NODATA 0 0 4055000200010 ENDSUBENT 9 0 4055000299999 SUBENT 40550003 20210224 41954055000300001 BIB 4 7 4055000300002 REACTION (92-U-235(N,F),,SIG) 4055000300003 MONITOR (92-U-235(N,F),,INT) 4055000300004 Normalization was done to fission cross-section 4055000300005 integral from 100 eV to 1000. eV = 12209 b*eV. 4055000300006 ERR-ANALYS (ERR-S,2.,3.) Relative error. 4055000300007 Normalization errors not included. 4055000300008 STATUS (TABLE) Table of INDC(CCP)-118,v.3,p.119,1977 4055000300009 ENDBIB 7 0 4055000300010 COMMON 3 3 4055000300011 EN-NRM-MIN EN-NRM-MAX MONIT 4055000300012 EV EV B*EV 4055000300013 100. 1000. 12209. 4055000300014 ENDCOMMON 3 0 4055000300015 DATA 3 21 4055000300016 EN-MIN EN-MAX DATA 4055000300017 KEV KEV B 4055000300018 0.1 0.2 20.79 4055000300019 0.2 0.3 19.94 4055000300020 0.3 0.4 12.67 4055000300021 0.4 0.5 14.39 4055000300022 0.5 0.6 15.85 4055000300023 0.6 0.7 11.08 4055000300024 0.7 0.8 11.40 4055000300025 0.8 0.9 8.40 4055000300026 0.9 1.0 7.66 4055000300027 1.0 2.0 7.33 4055000300028 2.0 3.0 5.31 4055000300029 3.0 4.0 4.63 4055000300030 4.0 5.0 4.22 4055000300031 5.0 6.0 3.80 4055000300032 6.0 7.0 3.43 4055000300033 7.0 8.0 3.25 4055000300034 8.0 9.0 3.08 4055000300035 9.0 10.0 3.11 4055000300036 10.0 15.0 2.68 4055000300037 15.0 20.0 2.34 4055000300038 20.0 30.0 2.17 4055000300039 ENDDATA 23 0 4055000300040 ENDSUBENT 39 0 4055000399999 SUBENT 40550004 20210224 41954055000400001 BIB 2 2 4055000400002 REACTION (92-U-235(N,G)92-U-236,,SIG) 4055000400003 STATUS (TABLE) Table of INDC(CCP)-118,v.3,p.119,1977 4055000400004 ENDBIB 2 0 4055000400005 NOCOMMON 0 0 4055000400006 DATA 3 21 4055000400007 EN-MIN EN-MAX DATA 4055000400008 KEV KEV B 4055000400009 0.1 0.2 14.04 4055000400010 0.2 0.3 10.68 4055000400011 0.3 0.4 7.86 4055000400012 0.4 0.5 6.29 4055000400013 0.5 0.6 6.44 4055000400014 0.6 0.7 5.50 4055000400015 0.7 0.8 6.12 4055000400016 0.8 0.9 5.07 4055000400017 0.9 1.0 5.82 4055000400018 1.0 2.0 3.74 4055000400019 2.0 3.0 2.65 4055000400020 3.0 4.0 2.17 4055000400021 4.0 5.0 2.04 4055000400022 5.0 6.0 1.79 4055000400023 6.0 7.0 1.90 4055000400024 7.0 8.0 1.70 4055000400025 8.0 9.0 1.81 4055000400026 9.0 10.0 1.52 4055000400027 10.0 15.0 1.31 4055000400028 15.0 20.0 1.11 4055000400029 20.0 30.0 1.01 4055000400030 ENDDATA 23 0 4055000400031 ENDSUBENT 30 0 4055000499999 ENDENTRY 4 0 4055099999999