ENTRY 41510 20200720 41884151000000001 SUBENT 41510001 20200720 41884151000100001 BIB 16 63 4151000100002 TITLE REPS facility for investigation of structure of 4151000100003 neutron cross-sections and neutron fundamental 4151000100004 characteristics. 4151000100005 AUTHOR (A.I.Berlev, Yu.V.Grigor'ev) 4151000100006 INSTITUTE (4RUSFEI) Yu.V.Grigor'ev( = Yu.V.Grigoriev) 4151000100007 (4RUSJIA) A.I.Berlev 4151000100008 REFERENCE (R,JIA-1183,200707) Main reference. 4151000100009 FACILITY (LINAC,4RUSJIA) REPS (Resonance Experimental 4151000100010 Transmissions and Cross-sections) exp.setup of Meson 4151000100011 Facility at Institute for Nuclear Research of Russian 4151000100012 Academy of Science. 4151000100013 INC-SOURCE Pulse neutron source RADEX (Radiational experiments).4151000100014 System of collimators as carbon and lead disks. 4151000100015 DETECTOR (SCIN) Eight-sections liquid scintillator as aluminum 4151000100016 tank of 40 l volume, 40 cm length, 40 cm diameter, 4151000100017 with hole of 110 mm diameter; solution 4151000100018 of scintillation admixtures and 5.5 liter of trimethyl4151000100019 borate B(OCH3)3 and 34.5 l of toluene C6H5CH3 4151000100020 as scintillation liquid. For TOF spectra measurement 4151000100021 as (n,gamma)-detector. Registration efficiency 30%, 4151000100022 geometrical efficiency 96%, energy resolution about 4151000100023 30% for gamma-lines 662 keV of cesium source at 4151000100024 voltage of +1500 V. 4151000100025 (PROPC) He-3 cylindrical counter of high efficiency as4151000100026 neutron detector in form of cylinder of 12 cm 4151000100027 diameter and 3.5 cm thickness , made from stainless 4151000100028 steel of 1 mm thickness. Filled by gas mixture of 4151000100029 He-3 at 7 Athm. and Ar at 3 Athm. Thermal neutron 4151000100030 efficiency registration about 100%. Anode voltage 4151000100031 +2500 V. 4151000100032 Other He-3 proportional counter SNM-18 for neutron 4151000100033 source intensity monitoring. 4151000100034 Lead and boron carbid protection around 4151000100035 (n,gamma)- and neutron detectors. 4151000100036 METHOD (COINC) Coincidence multiplicities from pulses of eight4151000100037 spectrometric channels. 4151000100038 (TOF) Flight path 50 m. 4151000100039 (TRN) Transmission measurement for total cross-sections4151000100040 determination. 4151000100041 Resonance filters from manganese and cadmium for 4151000100042 background determination. 4151000100043 SAMPLE Thin metallic disks of 80 mm diameter. 4151000100044 ANALYSIS Radiative capture reaction group cross-sections were 4151000100045 defined from TOF spectra using normalization on 4151000100046 U-238 standard cross-sections. 4151000100047 Program GRUCON was used for group cross-section 4151000100048 calculations. 4151000100049 REL-REF (N,,V.V.Sinitsa,J,YK,5,(59),34,1984) Program GRUCON. 4151000100050 CORRECTION For background. 4151000100051 For resonance self-shielding. 4151000100052 For zero thickness of sample 4151000100053 STATUS (TABLE) Table 1 of rep. JIA-1183,2007 4151000100054 ERR-ANALYS (DATA-ERR) Errors are not specified. 4151000100055 COMMENT Of author and compiler . There is a misprint in data 4151000100056 Table 1 of reference : U-235 capture c-s was used as 4151000100057 monitor and given in Table, not total. 4151000100058 Of author. Measurement of this work (MESON,4RUSJIA) 4151000100059 repeats the measurement at (REAC,4ZZZDUB) IBR-30 4151000100060 as a confirmation test. 4151000100061 HISTORY (20080215C) Compiled at CJD. M.M. 4151000100062 (20081202U) One STATUS line was added. 4151000100063 (20200720U) MESON -> LINAC, 4151000100064 STATUS information was updated. 4151000100065 ENDBIB 63 0 4151000100066 NOCOMMON 0 0 4151000100067 ENDSUBENT 66 0 4151000199999 SUBENT 41510002 20200720 41884151000200001 BIB 3 4 4151000200002 REACTION (41-NB-93(N,TOT),,SIG,,AV) 4151000200003 MONITOR Absolute measurements. 4151000200004 STATUS (COREL,41505002) Measurement at IBR-30 reactor at Dubna4151000200005 , see COMMENT of author in 41505.001 4151000200006 ENDBIB 4 0 4151000200007 NOCOMMON 0 0 4151000200008 DATA 4 6 4151000200009 EN-MIN EN-MAX DATA DATA-ERR 4151000200010 KEV KEV B B 4151000200011 0.100 0.215 9.2 0.3 4151000200012 0.215 0.465 8.6 0.3 4151000200013 0.465 1.0 8.9 0.5 4151000200014 1.0 2.15 12. 0.3 4151000200015 2.15 4.65 11. 0.3 4151000200016 4.65 10.0 9.6 0.3 4151000200017 ENDDATA 8 0 4151000200018 ENDSUBENT 17 0 4151000299999 SUBENT 41510003 20200720 41884151000300001 BIB 3 6 4151000300002 REACTION (41-NB-93(N,G)41-NB-94,,SIG,,AV) 4151000300003 MONITOR ((MONIT)92-U-238(N,G)92-U-239,,SIG,,AV) Averaged over 4151000300004 energy group ENDF/B-6 cross-section used for 4151000300005 normalization. 4151000300006 STATUS (COREL,41505003) Measurement at IBR-30 reactor at Dubna4151000300007 , see COMMENT of author in 41505.001 4151000300008 ENDBIB 6 0 4151000300009 NOCOMMON 0 0 4151000300010 DATA 5 5 4151000300011 EN-MIN EN-MAX DATA DATA-ERR MONIT 4151000300012 KEV KEV B B B 4151000300013 0.100 0.215 3.0 0.1 20.3 4151000300014 0.215 0.465 1.7 0.1 4.55 4151000300015 0.465 1.0 1.2 0.1 3.32 4151000300016 1.0 2.15 2.0 0.3 1.70 4151000300017 2.15 4.65 0.8 0.1 1.24 4151000300018 ENDDATA 7 0 4151000300019 ENDSUBENT 18 0 4151000399999 SUBENT 41510004 20200720 41884151000400001 BIB 4 6 4151000400002 REACTION (42-MO-0(N,TOT),,SIG,,AV) 4151000400003 MONITOR Absolute measurement 4151000400004 STATUS (COREL,41505004) Measurement at IBR-30 reactor at Dubna4151000400005 , see COMMENT of author in 41505.001 4151000400006 HISTORY (20200720A) DATA-ERR at 2.15-4.65 group was corrected 4151000400007 0.4 -> 0.7 b. 4151000400008 ENDBIB 6 0 4151000400009 NOCOMMON 0 0 4151000400010 DATA 4 6 4151000400011 EN-MIN EN-MAX DATA DATA-ERR 4151000400012 KEV KEV B B 4151000400013 0.100 0.215 16.2 1.2 4151000400014 0.215 0.465 10.9 1.3 4151000400015 0.465 1.0 11.2 0.5 4151000400016 1.0 2.15 10.3 0.4 4151000400017 2.15 4.65 10.5 0.7 4151000400018 4.65 10.0 9.3 0.2 4151000400019 ENDDATA 8 0 4151000400020 ENDSUBENT 19 0 4151000499999 SUBENT 41510005 20200720 41884151000500001 BIB 3 6 4151000500002 REACTION (42-MO-0(N,G),,SIG,,AV) 4151000500003 MONITOR ((MONIT)92-U-238(N,G)92-U-239,,SIG,,AV) Averaged over 4151000500004 energy group ENDF/B-6 cross-section used for 4151000500005 normalization. 4151000500006 STATUS (COREL,41505005) Measurement at IBR-30 reactor at Dubna4151000500007 , see COMMENT of author in 41505.001 4151000500008 ENDBIB 6 0 4151000500009 NOCOMMON 0 0 4151000500010 DATA 5 5 4151000500011 EN-MIN EN-MAX DATA DATA-ERR MONIT 4151000500012 KEV KEV B B B 4151000500013 0.100 0.215 4.2 0.40 20.3 4151000500014 0.215 0.465 1.4 0.20 4.55 4151000500015 0.465 1.0 1.2 0.20 3.32 4151000500016 1.0 2.15 0.9 0.10 1.70 4151000500017 2.15 4.65 0.6 0.05 1.24 4151000500018 ENDDATA 7 0 4151000500019 ENDSUBENT 18 0 4151000599999 SUBENT 41510006 20200720 41884151000600001 BIB 3 4 4151000600002 REACTION (73-TA-0(N,TOT),,SIG,,AV) 4151000600003 MONITOR Absolute measurement 4151000600004 STATUS (COREL,41505006) Measurement at IBR-30 reactor at Dubna4151000600005 , see COMMENT of author in 41505.001 4151000600006 ENDBIB 4 0 4151000600007 NOCOMMON 0 0 4151000600008 DATA 4 6 4151000600009 EN-MIN EN-MAX DATA DATA-ERR 4151000600010 KEV KEV B B 4151000600011 0.100 0.215 69.5 5.0 4151000600012 0.215 0.465 48.4 4.0 4151000600013 0.465 1.0 40.2 4.0 4151000600014 1.0 2.15 34.4 3.0 4151000600015 2.15 4.65 26.8 1.0 4151000600016 4.65 10.0 17.4 1.5 4151000600017 ENDDATA 8 0 4151000600018 ENDSUBENT 17 0 4151000699999 SUBENT 41510007 20080215 41434151000700001 BIB 2 3 4151000700002 REACTION (74-W-0(N,TOT),,SIG,,AV) Average over energy group, 4151000700003 boundaries are given in data table. 4151000700004 MONITOR Absolute measurement 4151000700005 ENDBIB 3 0 4151000700006 NOCOMMON 0 0 4151000700007 DATA 4 4 4151000700008 EN-MIN EN-MAX DATA DATA-ERR 4151000700009 KEV KEV B B 4151000700010 0.465 1.0 40.6 1.5 4151000700011 1.0 2.15 33.5 1.4 4151000700012 2.15 4.65 24.1 1.0 4151000700013 4.65 10.0 19.3 0.8 4151000700014 ENDDATA 6 0 4151000700015 ENDSUBENT 14 0 4151000799999 ENDENTRY 7 0 4151099999999