ENTRY 40103 20150921 41704010300000001 SUBENT 40103001 20150921 41704010300100001 BIB 10 55 4010300100002 INSTITUTE (4RUSFEI) 4010300100003 REFERENCE (J,SNP,14,625,1972) Engl. transl. of YF,14,1123,1971 4010300100004 (J,YF,14,(6),1123,1971) Data Tables and graph given 4010300100005 (R,INDC(CCP)-22,1,1972) Engl.transl. of YF,14,1123 4010300100006 (R,YFI-12,5,197106) Average values of fission cross4010300100007 sections, radiative capture cross sections and alpha 4010300100008 (R,INDC(CCP)-30,3,1972) Engl.translation of YFI-12,5 . 4010300100009 Fission, capture CS and ALF - average values at 4010300100010 100 eV - 60 keV energy range- in Table. 4010300100011 AUTHOR (A.A.Bergman,Yu.Ya.Stavissky,V.B.Chelnokov, 4010300100012 A.E.Samsonov,V.A.Tolstikov,A.N.Medvedev) 4010300100013 TITLE Ratio of neutron cross-sections of radiative capture 4010300100014 and fission for Pu-239 in the energy region below 4010300100015 ~50.0 keV 4010300100016 SAMPLE PuO2 samples (about 1.8% Pu-240) with effective 4010300100017 thicknesses (4.4 x 10**21; 4.2 x 10**20 and 4010300100018 1.7 x 10**20 atom/cm2). The measurements of the 4010300100019 effect of fission were carried out with ionization 4010300100020 fission chambers containing 1.6 and 12 mg of 4010300100021 Pu-239 dioxide. 4010300100022 For normalization, the measurements in the graphite 4010300100023 prism were performed, in addition, with samples of 4010300100024 Ag-107, 109 (4.3 x 10**21 atom/cm2) and 4010300100025 Au197 (1.8 x 10**21 atom/cm2). 4010300100026 METHOD (SLODT) Slowing-down-time in lead. 4010300100027 Gammas from neutron capture and fissions of Pu-239 4010300100028 and the number of Pu-239 fissions into sample were 4010300100029 measured directly. 4010300100030 Alpha was calculated by means of formula 4010300100031 alf(E)=(kf/kg)*(ng(t)/nf(t))-beta. 4010300100032 Measurement constant, kf, kg and beta were determined 4010300100033 from additional measurement on graphite prism for 4010300100034 thermal neutrons. 4010300100035 MONITOR For calculation of measurement constants the thermal 4010300100036 fission cross-section and alpha of Pu-239 (see Atomic 4010300100037 Energy Rev.,7,4,Vienna,1969) and thermal capture 4010300100038 cross-sections of Au-197 and Ag-107,109 (see Neutron 4010300100039 Cross-Sections,Suppl.2 to BNL-325,second edition,1966) 4010300100040 were used. 4010300100041 CORRECTION Gamma background and natural radioactivity background 4010300100042 were measured. 4010300100043 Sample activation, recycle neutron contribution, 4010300100044 correction on miscalculations and beam decrease into 4010300100045 sample were taken into account 4010300100046 ERR-ANALYS (ERR-S) Statistical error given except for En=0.47, 4010300100047 1.47 and 6.0 keV, for which total errors are given. 4010300100048 (ERR-T) Total error. 4010300100049 Normalization error was determined also. 4010300100050 HISTORY (19731204C) Compiled at the centre 4010300100051 (20141115A) SD: Updated to new date formats,lower case.4010300100052 Engl.transl. of YF added. STATUS in Sub.2 added. 4010300100053 FLAG deleted. ERR-ANALYS updated. 4010300100054 (20150921A) Ref. R,INDC(CCP)-30,3,1972 was added. 4010300100055 Articles were checked, BIB information was updated in 4010300100056 STATUS. 4010300100057 ENDBIB 55 0 4010300100058 NOCOMMON 0 0 4010300100059 ENDSUBENT 58 0 4010300199999 SUBENT 40103002 20150921 41704010300200001 BIB 3 8 4010300200002 REACTION (94-PU-239(N,ABS),,ALF,,SDT) 4010300200003 STATUS (TABLE) Table III of J,SNP,14,625,1972. 4010300200004 Table of YFI-12,5 - fission, capture CS and ALF - 4010300200005 average values at 100 eV - 60 keV energy range 4010300200006 (SPSDD,40470002) Explained as prelim. in AE,39,(4),291 4010300200007 Superseded by newer publication. 4010300200008 HISTORY (20141115A) SD: STATUS "SPSDD" added 4010300200009 (20150921A) M.M. SDT was added in SF8 4010300200010 ENDBIB 8 0 4010300200011 NOCOMMON 0 0 4010300200012 DATA 4 25 4010300200013 EN DATA ERR-S ERR-T 4010300200014 KEV NO-DIM NO-DIM NO-DIM 4010300200015 0.20 0.69 0.09 4010300200016 0.23 0.76 0.09 4010300200017 0.27 0.90 0.09 4010300200018 0.30 1.02 0.09 4010300200019 0.35 1.05 0.09 4010300200020 0.40 0.92 0.09 4010300200021 0.47 0.85 0.14 4010300200022 0.53 0.94 0.10 4010300200023 0.60 1.07 0.10 4010300200024 0.70 1.13 0.11 4010300200025 0.80 1.08 0.11 4010300200026 0.92 1.05 0.11 4010300200027 1.05 1.04 0.11 4010300200028 1.23 1.03 0.12 4010300200029 1.47 1.05 0.16 4010300200030 1.77 1.16 0.12 4010300200031 2.17 1.12 0.12 4010300200032 2.60 1.01 0.12 4010300200033 3.20 0.95 0.12 4010300200034 4.00 0.88 0.13 4010300200035 5.00 0.86 0.13 4010300200036 6.00 0.87 0.16 4010300200037 7.50 0.89 0.13 4010300200038 9.50 0.79 0.13 4010300200039 12.5 0.65 0.13 4010300200040 ENDDATA 27 0 4010300200041 ENDSUBENT 40 0 4010300299999 ENDENTRY 2 0 4010399999999