ENTRY 41380 20241022 421941380000 1 SUBENT 41380001 20241022 421941380001 1 BIB 12 56 41380001 2 TITLE Study of neutron cross-sections and 41380001 3 alpha=SIGgamma/SIGf value for U-235 in the 41380001 4 1 meV - 2 eV energy range 41380001 5 AUTHOR (Yu.V.Grigoriev, V.V.Sinitsa, S.B.Borzakov, G.L.Ilchev,41380001 6 H.Faikov-Stanczyk, Ts.Ts.Panteleev, N.B.Yaneva) 41380001 7 INSTITUTE (4RUSFEI) Grigoriev, Sinitsa 41380001 8 (4ZZZDUB) Borzakov, Ilchev, Faikov-Stanczyk, 41380001 9 Panteleev 41380001 10 (3BULBLA) Yaneva 41380001 11 REFERENCE (R,INDC(CCP)-430,7,2001) 41380001 12 English translation of YK,,(1),3,2000. 41380001 13 (J,YK,,(1),3,2000) Main reference. 41380001 14 ((S,ISINN-8,328,2000)=(S,JINR-E3-2000-192,2000)) 41380001 15 First author S.B.Borzakov. 41380001 16 (T,GRIGORIEV,2005) Dissertation of Grigor'ev Yuriy 41380001 17 Vasil'evich, "Neutron cross section and their integral41380001 18 characteristics in resonance and thermal energy 41380001 19 regions", thesis for Dr. of Phys. and Math.Sciences 41380001 20 submitted to IPPE, Obninsk, 2005. 41380001 21 FACILITY (REAC,4ZZZDUB) Pulse neutron booster IBR-2 of the 41380001 22 Frank Laboratory of Neutron Physics. 41380001 23 INC-SPECT .Mirror neutron guide on 6th neutron channel of the 41380001 24 reactor for measurements with 3 - 70 milli-eV neutron 41380001 25 energy giving neutron flux 3.e+6 n/cm**2/sec 41380001 26 .Neutron beam on 1st neutron channel of the reactor 41380001 27 for measurements with 3 milli-eV - 2 eV neutron energy41380001 28 giving neutron flux 1.e+6 n/cm**2/sec 41380001 29 METHOD (TOF) Flight bases are 27 m and 34 m 41380001 30 DETECTOR (HPGE) Detector volume 80cm**3.Used on 34m flight base.41380001 31 Surrounded by lead and boron carbide with paraffin 41380001 32 placed on 15 cm distance from sample-radiator . 41380001 33 Energy resolution 3 keV. 41380001 34 (GELI) Detector volume 55cm**3.Used on 27m flight base.41380001 35 Without shield placed on 15 cm distance from 41380001 36 sample-radiator. 41380001 37 Energy resolution < 5 keV. 41380001 38 (BF3) Boron counter CHM-13 for neutron spectrum 41380001 39 measurement. 41380001 40 Relative detector efficiency was obtained by NaCl 41380001 41 sample of 102 g weight using gamma yields for Cl-nat 41380001 42 from REL-REF. 41380001 43 REL-REF (R,,A.M.J.Spits+,J,NP/A,264,63,1976) 41380001 44 CORRECTION .To measure recycled neutrons background beryllium 41380001 45 (20 mm), indium(1 mm) and cadmium (2 mm) filters were 41380001 46 used 41380001 47 STATUS (COREL,41368001) ALF at resonances and for different 41380001 48 energy groups ( flight base 122 and 500 m) . 41380001 49 HISTORY (20001005C) + + Compiled at the center - CJD + + 41380001 50 (20001005U) Last checking has been done. 41380001 51 (20090504A) Reference S,ISINN-8 was added. 41380001 52 Free text was corrected to be human-readable. 41380001 53 BIB and COMMON information was added. 41380001 54 (20110424A) M.M. Reference T,GRIGORIEV,2005 was added. 41380001 55 Subent 003 was added. 41380001 56 (20191114U) Ref. YK was corrected. 41380001 57 (20241022U) Status was updated for new rules. 41380001 58 ENDBIB 56 0 41380001 59 NOCOMMON 0 0 41380001 60 ENDSUBENT 59 0 4138000199999 SUBENT 41380002 20241022 421941380002 1 BIB 9 22 41380002 2 REACTION (92-U-235(N,ABS),,ALF) 41380002 3 MONITOR ((MONIT)92-U-235(N,ABS),,ALF) at thermal energy. 41380002 4 MONIT-REF ((MONIT),H.Weigman+,C,91JUELIC,,38,1991) 41380002 5 SAMPLE .Metallic disk samples-radiator with 90% 235U and 41380002 6 10% 238U, 0.25 mm thickness, sample diameter 48 mm, 41380002 7 weight 8 gram . 41380002 8 ANALYSIS (AREA) Value of ALF was calculated as ratio of sum of 41380002 9 areas for radiative capture lines( 642 and triplet 910,41380002 10 913, 915 keV) to the sum of areas for fission lines 41380002 11 (707, 815, 1279 keV). Then was normalized to value for41380002 12 thermal neutrons 0.169. 41380002 13 ERR-ANALYS (DATA-ERR) Total error ( see also MISC-COL ). 41380002 14 MISC-COL (MISC) Max. total error at 95% confidence level ( as 41380002 15 was given in initial compilation, but information 41380002 16 "Max. total error at 95% confidence level" is absent 41380002 17 in the articles; may be this informaion is from an 41380002 18 author, it is not clear). 41380002 19 STATUS (TABLE,,Yu.V.Grigoriev+,R,INDC(CCP)-430,7,2001) Table 141380002 20 Table of J,YK,,(1),3,2000. 41380002 21 Table 1 of S,ISINN-8,328,2000 . 41380002 22 HISTORY (20241022A) Monitors (n,g) and (n,f) C-S were deleted. 41380002 23 DATA-ERR values were corrected 2SIGMA - 1SIGMA error. 41380002 24 ENDBIB 22 0 41380002 25 COMMON 2 3 41380002 26 EN-NRM MONIT 41380002 27 EV NO-DIM 41380002 28 2.53E-02 0.169 41380002 29 ENDCOMMON 3 0 41380002 30 DATA 4 6 41380002 31 EN DATA DATA-ERR MISC 41380002 32 EV NO-DIM NO-DIM NO-DIM 41380002 33 6.0-3 0.171 0.0225 0.045 41380002 34 8.6-3 0.189 0.005 0.010 41380002 35 1.28-2 0.191 0.005 0.010 41380002 36 2.05-2 0.179 0.006 0.012 41380002 37 3.20-2 0.159 0.006 0.012 41380002 38 5.50-2 0.172 0.006 0.012 41380002 39 ENDDATA 8 0 41380002 40 ENDSUBENT 39 0 4138000299999 SUBENT 41380003 20241022 421941380003 1 BIB 6 11 41380003 2 REACTION (92-U-235(N,ABS),,ALF) 41380003 3 MONITOR (92-U-235(N,ABS),,ALF) at thermal energy and 41380003 4 at resonances 0.29, 1.135 eV. 41380003 5 SAMPLE .Metallic disk samples-radiator with 90% 235U and 41380003 6 10% 238U, 0.25 mm thickness, sample diameter 48 mm, 41380003 7 weight 8 gram . 41380003 8 ANALYSIS (AREA) Areas for radiative capture line 642, triplet 41380003 9 910, 913, 915 keV, and fission gamma-lines 707, 815, 41380003 10 doublets 1178+1181 and 1222+124, 1279 keV were defined.41380003 11 ERR-ANALYS (DATA-ERR) Not specified. 41380003 12 STATUS (TABLE,,Yu.V.Grigoriev,T,GRIGORIEV,2005) Table 52 41380003 13 ENDBIB 11 0 41380003 14 NOCOMMON 0 0 41380003 15 DATA 4 24 41380003 16 EN-MAX EN-MIN DATA DATA-ERR 41380003 17 EV EV NO-DIM NO-DIM 41380003 18 1.62 1.37 0.28 0.07 41380003 19 1.37 1.09 0.21 0.06 41380003 20 0.70 0.46 0.24 0.07 41380003 21 0.46 0.34 0.22 0.06 41380003 22 0.34 0.26 0.18 0.05 41380003 23 0.26 0.20 0.21 0.06 41380003 24 0.20 0.14 0.19 0.05 41380003 25 0.14 0.11 0.14 0.03 41380003 26 0.11 0.09 0.16 0.04 41380003 27 0.09 0.07 0.21 0.06 41380003 28 0.07 0.06 0.17 0.04 41380003 29 0.06 0.05 0.19 0.05 41380003 30 0.05 0.04 0.15 0.04 41380003 31 0.04 0.03 0.10 0.03 41380003 32 0.03 0.02 0.10 0.03 41380003 33 0.0225 0.0158 0.12 0.03 41380003 34 0.0158 0.0117 0.12 0.03 41380003 35 0.0117 0.00836 0.22 0.06 41380003 36 0.00836 0.00625 0.20 0.05 41380003 37 0.00625 0.00388 0.34 0.08 41380003 38 0.00388 0.00263 0.22 0.06 41380003 39 0.00263 0.00191 0.37 0.09 41380003 40 0.00191 0.00144 0.43 0.010 41380003 41 0.00144 0.00101 0.53 0.012 41380003 42 ENDDATA 26 0 41380003 43 ENDSUBENT 42 0 4138000399999 ENDENTRY 3 0 4138099999999