ENTRY 40470 20140728 41644047000000001 SUBENT 40470001 20140728 41644047000100001 BIB 11 27 4047000100002 INSTITUTE (4RUSJIA) 4047000100003 REFERENCE (J,AE,39,(4),291,1975) Data and graphs are given 4047000100004 (J,SJA,39,916,1975) Engl.translation of AE,39,(4),291 4047000100005 #doi:10.1007/BF01261900 4047000100006 (C,75KIEV,6,61,1975) 4047000100007 AUTHOR (A.A.Bergman,A.N.Medvedev,A.E.Samsonov,V.A.Tolstikov) 4047000100008 TITLE Ratio of radiative capture and fission cross-sections 4047000100009 for Pu-239 at neutron energy of 0.2-30. keV . 4047000100010 SAMPLE Plutonium samples with thicknesses 4.2E20 and 4047000100011 4.9E21 atoms/cm2, Pu-239 content not available 4047000100012 METHOD (SLODT) Method of slowing-down time in lead 4047000100013 DETECTOR (PROPC) Proportional gamma-counter 4047000100014 (FISCH) Fission chamber 4047000100015 PART-DET (G,FF) Gamma and fission fragments. 4047000100016 STATUS (TABLE) From Neytronnaya Fizika,part 6,page 61,1976 4047000100017 = Table of J,AE,39,(4),291,1975 4047000100018 (COREL,40435001) Entry 40470 supersedes 40435 as full 4047000100019 duplication. 4047000100020 HISTORY (19771130C) Compiled at the centre 4047000100021 (20140728U) M.M. Upper -> lower case correction. 4047000100022 Dates were corrected for 4-digits year. 4047000100023 BIB information was updated. 4047000100024 Ref. od AE was added. 4047000100025 DATA-ERR1 -> ERR-S, DATA-ERR2 -> ERR-1 . 4047000100026 SDT was added in REACTION. 4047000100027 ERR-ANALYS (ERR-S) Standard deviation 4047000100028 (ERR-1) Normalization error 4047000100029 ENDBIB 27 0 4047000100030 NOCOMMON 0 0 4047000100031 ENDSUBENT 30 0 4047000199999 SUBENT 40470002 20140728 41644047000200001 BIB 6 41 4047000200002 REACTION (94-PU-239(N,ABS),,ALF,,SDT) 4047000200003 SAMPLE Au sample of 1.8E+21 at/cm**2 was used for 4047000200004 normalization - in measurement with carbon prism by 4047000200005 thermal neutrons and "thin" Pu sample. 4047000200006 Measurements with "thick" Pu samples were calibrated by4047000200007 "thin" sample measurement in energy range 8 - 23 keV. 4047000200008 ANALYSIS ALF(E) value was defined by formula: 4047000200009 ALF(E) - ALF(T) = 4047000200010 ((IgammaPu(E)*IfPu(T))/(IfPu(E)*IgammaPu(T))-1.)* 4047000200011 ((IgammaPu(T)*SIGcapAu(T)*Pau*Apu*Bau)/ 4047000200012 (IgammaAu(T)*SIGfPu(T)*Ppu*Aau*Bpu*delta)), where 4047000200013 IgammaPu, IgammaAu - gamma counts for Pu and Au, 4047000200014 IfPu - fission counts for Pu, 4047000200015 at 4047000200016 E - investigated incident neutron energy, 4047000200017 T - thermal neutron Maxwellian spectrum at 22 deg C 4047000200018 temperature; 4047000200019 SIGcapAu(T) - Au capture cross section (value not 4047000200020 given), 4047000200021 SIGfPu(T) - Pu fission cross section (value not 4047000200022 given), 4047000200023 Pau,Ppu,Aau,Apu,Bau,Bpu - sample weight, atomic weight,4047000200024 binding energy for Au and Pu; 4047000200025 delta - coefficient depending from Au and Pu samples 4047000200026 radii; 4047000200027 ALF(T) - ALPHA value for thermal Maxwellian spectrum at4047000200028 22 deg temperature, = 0.398+-0.004 (ASSUM). 4047000200029 ASSUMED (ASSUM,94-PU-239(N,ABS),,ALF,,MXW) at thermal spectrum 4047000200030 CORRECTION Correction on spectrometer resolution < 4.0 % . 4047000200031 STATUS (COREL,40103002) In 40103 - previous measurement, 4047000200032 mentioned in C,75KIEV,6,61,1976 as preliminary result. 4047000200033 In this measurement - 4047000200034 electronics stability was increased, 4047000200035 slowing down time was measured better, 4047000200036 Neutron pulse duration was decreased twice to 0.5 4047000200037 microsec, 4047000200038 new data for fission decreased ALPHA value in energy 4047000200039 range En > 8 keV. 4047000200040 (COREL,40105015) Ref.s of 40105 are not mentioned in 4047000200041 C,75KIEV,6,61,1976. 4047000200042 Thick sample is different; method mainly the same. 4047000200043 ENDBIB 41 0 4047000200044 COMMON 3 3 4047000200045 EN-NRM ASSUM ASSUM-ERR 4047000200046 EV NO-DIM NO-DIM 4047000200047 0.0253 0.398 0.004 4047000200048 ENDCOMMON 3 0 4047000200049 DATA 5 21 4047000200050 EN-MIN EN-MAX DATA ERR-S ERR-1 4047000200051 KEV KEV NO-DIM NO-DIM NO-DIM 4047000200052 2.0000E-01 3.0000E-01 7.4000E-01 1.0000E-02 6.0000E-02 4047000200053 3.0000E-01 4.0000E-01 9.5000E-01 3.0000E-02 8.0000E-02 4047000200054 4.0000E-01 5.0000E-01 7.6000E-01 2.0000E-02 6.0000E-02 4047000200055 5.0000E-01 6.0000E-01 9.5000E-01 3.0000E-02 8.0000E-02 4047000200056 6.0000E-01 7.0000E-01 1.1500E+00 3.0000E-02 9.0000E-02 4047000200057 7.0000E-01 8.0000E-01 9.8000E-01 4.0000E-02 8.0000E-02 4047000200058 8.0000E-01 9.0000E-01 8.8000E-01 4.0000E-02 8.0000E-02 4047000200059 9.0000E-01 1.0000E+00 9.0000E-01 5.0000E-02 8.0000E-02 4047000200060 1.0000E+00 2.0000E+00 1.0200E+00 2.0000E-02 8.0000E-02 4047000200061 2.0000E+00 3.0000E+00 9.8000E-01 2.0000E-02 8.0000E-02 4047000200062 3.0000E+00 4.0000E+00 8.4000E-01 4.0000E-02 7.0000E-02 4047000200063 4.0000E+00 5.0000E+00 8.0000E-01 4.0000E-02 7.0000E-02 4047000200064 5.0000E+00 6.0000E+00 7.8000E-01 5.0000E-02 7.0000E-02 4047000200065 6.0000E+00 7.0000E+00 8.6000E-01 3.0000E-02 7.0000E-02 4047000200066 7.0000E+00 8.0000E+00 8.1000E-01 4.0000E-02 7.0000E-02 4047000200067 8.0000E+00 9.0000E+00 7.6000E-01 4.0000E-02 6.0000E-02 4047000200068 9.0000E+00 1.0000E+01 7.4000E-01 4.0000E-02 6.0000E-02 4047000200069 1.0000E+01 1.5000E+01 6.1000E-01 2.0000E-02 6.0000E-02 4047000200070 1.5000E+01 2.0000E+01 5.5000E-01 2.0000E-02 5.0000E-02 4047000200071 2.0000E+01 2.5000E+01 5.1000E-01 3.0000E-02 5.0000E-02 4047000200072 2.5000E+01 3.0000E+01 4.5000E-01 2.0000E-02 5.0000E-02 4047000200073 ENDDATA 23 0 4047000200074 ENDSUBENT 73 0 4047000299999 SUBENT 40470003 20140728 41644047000300001 BIB 2 2 4047000300002 REACTION (94-PU-239(N,F),,SIG,,SDT) 4047000300003 ANALYSIS Not explained in articles. 4047000300004 ENDBIB 2 0 4047000300005 NOCOMMON 0 0 4047000300006 DATA 5 21 4047000300007 EN-MIN EN-MAX DATA ERR-S ERR-1 4047000300008 KEV KEV B B B 4047000300009 2.0000E-01 3.0000E-01 1.7000E+01 1.0000E-01 3.2000E-01 4047000300010 3.0000E-01 4.0000E-01 1.2100E+01 1.1000E-01 2.4000E-01 4047000300011 4.0000E-01 5.0000E-01 1.0400E+01 1.1000E-01 2.1000E-01 4047000300012 5.0000E-01 6.0000E-01 9.6300E+00 1.1000E-01 1.9000E-01 4047000300013 6.0000E-01 7.0000E-01 7.2900E+00 1.0000E-01 1.5000E-01 4047000300014 7.0000E-01 8.0000E-01 6.3700E+00 1.1000E-01 1.3000E-01 4047000300015 8.0000E-01 9.0000E-01 6.2900E+00 1.6000E-01 1.3000E-01 4047000300016 9.0000E-01 1.0000E+00 6.4100E+00 1.4000E-01 1.3000E-01 4047000300017 1.0000E+00 2.0000E+00 4.9200E+00 4.0000E-02 1.0000E-01 4047000300018 2.0000E+00 3.0000E+00 3.3400E+00 3.0000E-02 7.0000E-02 4047000300019 3.0000E+00 4.0000E+00 2.9200E+00 4.0000E-02 6.0000E-02 4047000300020 4.0000E+00 5.0000E+00 2.6100E+00 6.0000E-02 5.0000E-02 4047000300021 5.0000E+00 6.0000E+00 2.4200E+00 4.0000E-02 5.0000E-02 4047000300022 6.0000E+00 7.0000E+00 2.2100E+00 4.0000E-02 4.0000E-02 4047000300023 7.0000E+00 8.0000E+00 2.1100E+00 5.0000E-02 4.0000E-02 4047000300024 8.0000E+00 9.0000E+00 2.0900E+00 5.0000E-02 5.0000E-02 4047000300025 9.0000E+00 1.0000E+01 2.0100E+00 4.0000E-02 4.0000E-02 4047000300026 1.0000E+01 1.5000E+01 1.9800E+00 2.0000E-02 4.0000E-02 4047000300027 1.5000E+01 2.0000E+01 1.8100E+00 2.0000E-02 4.0000E-02 4047000300028 2.0000E+01 2.5000E+01 1.7900E+00 3.0000E-02 4.0000E-02 4047000300029 2.5000E+01 3.0000E+01 1.7700E+00 3.0000E-02 3.0000E-02 4047000300030 ENDDATA 23 0 4047000300031 ENDSUBENT 30 0 4047000399999 ENDENTRY 3 0 4047099999999