ENTRY 41380 20191114 41844138000000001 SUBENT 41380001 20191114 41844138000100001 BIB 12 51 4138000100002 TITLE Study of neutron cross-sections and 4138000100003 alpha=SIGgamma/SIGf value for U-235 in the 4138000100004 1 meV - 2 eV energy range 4138000100005 AUTHOR (Yu.V.Grigoriev, V.V.Sinitsa, S.B.Borzakov, G.L.Ilchev,4138000100006 H.Faikov-Stanczyk, Ts.Ts.Panteleev, N.B.Yaneva) 4138000100007 INSTITUTE (4RUSFEI) Grigoriev, Sinitsa 4138000100008 (4ZZZDUB) Borzakov, Ilchev, Faikov-Stanczyk, 4138000100009 Panteleev 4138000100010 (3BULBLA) Yaneva 4138000100011 REFERENCE (J,YK,,(1),3,2000) Main reference. 4138000100012 (R,INDC(CCP)-430,7,2001) 4138000100013 English translation of YK,2000. 4138000100014 ((S,ISINN-8,328,200005)=(S,JINR-E3-2000-192,200005)) 4138000100015 First author S.B.Borzakov. 4138000100016 (T,GRIGORIEV,2005) Dissertation of Yu.Grigoriev. 4138000100017 FACILITY (REAC,4ZZZDUB) Pulse neutron booster IBR-2 of the 4138000100018 Frank Laboratory of Neutron Physics. 4138000100019 INC-SPECT .Mirror neutron guide on 6th neutron channel of the 4138000100020 reactor for measurements with 3 - 70 milli-eV neutron 4138000100021 energy giving neutron flux 3.e+6 n/cm**2/sec 4138000100022 .Neutron beam on 1st neutron channel of the reactor 4138000100023 for measurements with 3 milli-eV - 2 eV neutron energy4138000100024 giving neutron flux 1.e+6 n/cm**2/sec 4138000100025 METHOD (TOF) Flight bases are 27 m and 34 m 4138000100026 DETECTOR (HPGE) Detector volume 80cm**3.Used on 34m flight base.4138000100027 Surrounded by lead and boron carbide with paraffin 4138000100028 placed on 15 cm distance from sample-radiator . 4138000100029 Energy resolution 3 keV. 4138000100030 (GELI) Detector volume 55cm**3.Used on 27m flight base.4138000100031 Without shield placed on 15 cm distance from 4138000100032 sample-radiator. 4138000100033 Energy resolution < 5 keV. 4138000100034 (BF3) Boron counter CHM-13 for neutron spectrum 4138000100035 measurement. 4138000100036 Relative detector efficiency was obtained by NaCl 4138000100037 sample of 102 g weight using gamma yields for Cl-nat 4138000100038 from REL-REF. 4138000100039 REL-REF (R,,A.M.J.Spits+,J,NP/A,264,63,1976) 4138000100040 CORRECTION .To measure recycled neutrons background beryllium 4138000100041 (20 mm), indium(1 mm) and cadmium (2 mm) filters were 4138000100042 used 4138000100043 STATUS (COREL,41368001) ALF at resonances and for different 4138000100044 energy groups ( flight base 122 and 500 m) . 4138000100045 HISTORY (20001005C) + + Compiled at the Center - CJD + + 4138000100046 (20001005U) Last checking has been done. 4138000100047 (20090504A) Reference S,ISINN-8 was added. 4138000100048 Free text was corrected to be human-readable. 4138000100049 BIB and COMMON information was added. 4138000100050 (20110424A) M.M. Reference T,GRIGORIEV,2005 was added. 4138000100051 Subent 003 was added. 4138000100052 (20191114U) Ref. YK was corrected. 4138000100053 ENDBIB 51 0 4138000100054 NOCOMMON 0 0 4138000100055 ENDSUBENT 54 0 4138000199999 SUBENT 41380002 20191114 41844138000200001 BIB 7 16 4138000200002 REACTION (92-U-235(N,ABS),,ALF) 4138000200003 MONITOR ((MONIT)92-U-235(N,ABS),,ALF) at thermal energy. 4138000200004 (92-U-235(N,G)92-U-236,,SIG) 4138000200005 (92-U-235(N,F),,SIG) 4138000200006 MONIT-REF ((MONIT),H.Weigman+,C,91JUELIC,,38,1991) 4138000200007 SAMPLE .Metallic disk samples-radiator with 90% 235U and 4138000200008 10% 238U, 0.25 mm thickness, sample diameter 48 mm, 4138000200009 weight 8 gram . 4138000200010 ANALYSIS (AREA) Value of ALF was calculated as ratio of sum of 4138000200011 areas for radiative capture lines( 642 and triplet 910,4138000200012 913, 915 keV) to the sum of areas for fission lines 4138000200013 (707, 815, 1279 keV). Then was normalized to value for4138000200014 thermal neutrons 0.169. 4138000200015 ERR-ANALYS (DATA-ERR) Max. total error at 95% confidence level 4138000200016 STATUS (TABLE) From Table 1 of J,YK,,(1),3,2000 4138000200017 Table 1 of ISINN-8 . 4138000200018 ENDBIB 16 0 4138000200019 COMMON 2 3 4138000200020 EN-NRM MONIT 4138000200021 EV NO-DIM 4138000200022 2.53E-02 0.169 4138000200023 ENDCOMMON 3 0 4138000200024 DATA 3 6 4138000200025 EN DATA DATA-ERR 4138000200026 EV NO-DIM NO-DIM 4138000200027 6.0-3 0.171 0.045 4138000200028 8.6-3 0.189 0.01 4138000200029 1.28-2 0.191 0.01 4138000200030 2.05-2 0.179 0.012 4138000200031 3.2-2 0.159 0.012 4138000200032 5.5-2 0.172 0.012 4138000200033 ENDDATA 8 0 4138000200034 ENDSUBENT 33 0 4138000299999 SUBENT 41380003 20110425 41524138000300001 BIB 6 12 4138000300002 REACTION (92-U-235(N,ABS),,ALF) Alpha 4138000300003 MONITOR (92-U-235(N,ABS),,ALF) at thermal energy and 4138000300004 at resonances 0.29, 1.135 eV. 4138000300005 SAMPLE .Metallic disk samples-radiator with 90% 235U and 4138000300006 10% 238U, 0.25 mm thickness, sample diameter 48 mm, 4138000300007 weight 8 gram . 4138000300008 ANALYSIS (AREA) Areas for radiative capture line 642, triplet 4138000300009 910, 913, 915 keV, and fission gamma-lines 707, 815, 4138000300010 duplets 1178+1181 and 1222+124, 1279 keV were defined. 4138000300011 ERR-ANALYS (DATA-ERR) Not specified. 4138000300012 STATUS (TABLE) Table 52 of T,GRIGORIEV,2005. 4138000300013 Table 1 of ISINN-8 . 4138000300014 ENDBIB 12 0 4138000300015 NOCOMMON 0 0 4138000300016 DATA 4 24 4138000300017 EN-MAX EN-MIN DATA DATA-ERR 4138000300018 EV EV NO-DIM NO-DIM 4138000300019 1.62 1.37 0.28 0.07 4138000300020 1.37 1.09 0.21 0.06 4138000300021 0.70 0.46 0.24 0.07 4138000300022 0.46 0.34 0.22 0.06 4138000300023 0.34 0.26 0.18 0.05 4138000300024 0.26 0.20 0.21 0.06 4138000300025 0.20 0.14 0.19 0.05 4138000300026 0.14 0.11 0.14 0.03 4138000300027 0.11 0.09 0.16 0.04 4138000300028 0.09 0.07 0.21 0.06 4138000300029 0.07 0.06 0.17 0.04 4138000300030 0.06 0.05 0.19 0.05 4138000300031 0.05 0.04 0.15 0.04 4138000300032 0.04 0.03 0.10 0.03 4138000300033 0.03 0.02 0.10 0.03 4138000300034 0.0225 0.0158 0.12 0.03 4138000300035 0.0158 0.0117 0.12 0.03 4138000300036 0.0117 0.00836 0.22 0.06 4138000300037 0.00836 0.00625 0.20 0.05 4138000300038 0.00625 0.00388 0.34 0.08 4138000300039 0.00388 0.00263 0.22 0.06 4138000300040 0.00263 0.00191 0.37 0.09 4138000300041 0.00191 0.00144 0.43 0.010 4138000300042 0.00144 0.00101 0.53 0.012 4138000300043 ENDDATA 26 0 4138000300044 ENDSUBENT 43 0 4138000399999 ENDENTRY 3 0 4138099999999