ENTRY 40358 20130130 41594035800000001 SUBENT 40358001 20130130 41594035800100001 BIB 13 27 4035800100002 INSTITUTE (4RUSFEI) 4035800100003 REFERENCE (J,AE,38,(2),108,197502) Data are not given 4035800100004 (J,SJA,38,140,1975) Engl.translation of J,AE,38,108 . 4035800100005 AUTHOR (Z.A.Aleksandrova,V.I.Bol'shov,V.F.Kuznetsov, 4035800100006 G.N.Smirenkin,M.Z.Tarasko) 4035800100007 TITLE Spectra of secondary neutrons at fission of U-235 and 4035800100008 Pu-239 by neutrons with 0.1 MeV energy. 4035800100009 INC-SOURCE (P-T) Proton-tritium 4035800100010 DETECTOR (SCIN) Scintillation Detector 4035800100011 SAMPLE Metallic U-235 and Pu-239 disks of 28 and 42 g . 4035800100012 REL-REF (R,40250001,Z.A.Alexandrova+,J,AE,36,(4),282,1974) 4035800100013 Data of Cf-252 spontaneous fission were used to 4035800100014 control stability of measurement facility using 4035800100015 Cf-252 source instead of sample. 4035800100016 COMMENT Presentation form of neutron spectrum is given 4035800100017 N(En)=((E/PI/T**3)**0.5)*EXP(-En/T). 4035800100018 ADD-RES T was defined by Maxwell approximation as 4035800100019 1.30+-0.02 and 1.38+-0.02 MeV for U-235 and Pu-239, 4035800100020 respectively. 4035800100021 STATUS (TABLE) Data obtained from the author . 4035800100022 Spectra are presented on Fig.2 as N(E)/sqrt(E). 4035800100023 HISTORY (19770531C) Compiled at the centre 4035800100024 (20100812A) BIB information, ref.J,SJA,38,140,1975 were4035800100025 added. Free text was corrected to be human-readable. 4035800100026 (20130130A) REACTION SF8 was corrected in Subents 4035800100027 002-005. 4035800100028 ERR-ANALYS No information available 4035800100029 ENDBIB 27 0 4035800100030 COMMON 1 3 4035800100031 EN 4035800100032 MEV 4035800100033 1.0000E-01 4035800100034 ENDCOMMON 3 0 4035800100035 ENDSUBENT 34 0 4035800199999 SUBENT 40358002 20130130 41594035800200001 BIB 3 9 4035800200002 REACTION (94-PU-239(N,F),,NU/DE,,RRE/REL) 4035800200003 Relatively to energy 4035800200004 of incident neutron. 4035800200005 ANALYSIS Treatment by Lantsosh's method 4035800200006 HISTORY (20100812A) Reaction was corrected 4035800200007 ,DE,N,REL -> ,NU/DE,,RTE/REL 4035800200008 according to opinion N.Otsuka (NDS IAEA). 4035800200009 (20130130A) REACTION SF8 was corrected RTE -> RRE 4035800200010 according to opinion N.Otsuka (NDS IAEA). 4035800200011 ENDBIB 9 0 4035800200012 NOCOMMON 0 0 4035800200013 DATA 2 54 4035800200014 E DATA 4035800200015 MEV ARB-UNITS 4035800200016 1.5030E+00 4.3998E+04 4035800200017 1.6020E+00 3.9928E+04 4035800200018 1.7040E+00 3.6597E+04 4035800200019 1.8090E+00 3.4323E+04 4035800200020 1.9170E+00 3.0985E+04 4035800200021 2.0290E+00 2.8610E+04 4035800200022 2.1440E+00 2.7092E+04 4035800200023 2.2610E+00 2.4276E+04 4035800200024 2.3830E+00 2.2514E+04 4035800200025 2.5070E+00 2.1373E+04 4035800200026 2.6340E+00 1.9100E+04 4035800200027 2.7650E+00 1.7676E+04 4035800200028 2.8990E+00 1.6082E+04 4035800200029 3.0360E+00 1.4283E+04 4035800200030 3.1760E+00 1.2417E+04 4035800200031 3.3190E+00 1.0887E+04 4035800200032 3.4660E+00 1.0270E+04 4035800200033 3.6160E+00 9.2450E+03 4035800200034 3.7680E+00 8.1520E+03 4035800200035 3.9250E+00 7.2980E+03 4035800200036 4.0840E+00 6.5830E+03 4035800200037 4.2460E+00 5.9090E+03 4035800200038 4.4120E+00 5.2540E+03 4035800200039 4.5810E+00 4.6520E+03 4035800200040 4.7530E+00 4.1330E+03 4035800200041 4.9280E+00 3.6900E+03 4035800200042 5.1060E+00 3.2540E+03 4035800200043 5.2880E+00 2.8310E+03 4035800200044 5.4730E+00 2.3670E+03 4035800200045 5.6610E+00 2.0700E+03 4035800200046 5.8520E+00 1.8770E+03 4035800200047 6.0460E+00 1.5410E+03 4035800200048 6.2440E+00 1.3580E+03 4035800200049 6.4440E+00 1.2490E+03 4035800200050 6.6480E+00 1.0430E+03 4035800200051 6.8550E+00 9.1700E+02 4035800200052 7.0660E+00 8.3100E+02 4035800200053 7.2790E+00 6.3200E+02 4035800200054 7.4960E+00 5.3100E+02 4035800200055 7.7150E+00 4.8500E+02 4035800200056 7.9380E+00 3.8500E+02 4035800200057 8.1650E+00 3.4500E+02 4035800200058 8.3940E+00 2.8100E+02 4035800200059 8.6270E+00 2.4900E+02 4035800200060 8.8620E+00 2.2400E+02 4035800200061 9.1010E+00 1.6200E+02 4035800200062 9.3430E+00 1.4000E+02 4035800200063 9.5890E+00 9.5000E+01 4035800200064 9.8370E+00 1.0100E+02 4035800200065 1.0089E+01 7.8000E+01 4035800200066 1.0344E+01 5.8000E+01 4035800200067 1.0602E+01 6.7000E+01 4035800200068 1.0863E+01 5.6000E+01 4035800200069 1.1128E+01 3.3000E+01 4035800200070 ENDDATA 56 0 4035800200071 ENDSUBENT 70 0 4035800299999 SUBENT 40358003 20130130 41594035800300001 BIB 3 9 4035800300002 REACTION (94-PU-239(N,F),,NU/DE,,RRE/REL) 4035800300003 Relatively to energy 4035800300004 of incident neutron . 4035800300005 ANALYSIS Treatment by Barras's method 4035800300006 HISTORY (20100812A) Reaction was corrected 4035800300007 ,DE,N,REL -> ,NU/DE,,RTE/REL 4035800300008 according to opinion N.Otsuka (NDS IAEA). 4035800300009 (20130130A) REACTION SF8 was corrected RTE -> RRE 4035800300010 according to opinion N.Otsuka (NDS IAEA). 4035800300011 ENDBIB 9 0 4035800300012 NOCOMMON 0 0 4035800300013 DATA 2 19 4035800300014 E DATA 4035800300015 MEV ARB-UNITS 4035800300016 1.5000E+00 3.9961E+04 4035800300017 2.0000E+00 2.7799E+04 4035800300018 2.5000E+00 1.9835E+04 4035800300019 3.0000E+00 1.2498E+04 4035800300020 3.5000E+00 8.9110E+03 4035800300021 4.0000E+00 6.4580E+03 4035800300022 4.5000E+00 4.3200E+03 4035800300023 5.0000E+00 3.3770E+03 4035800300024 5.5000E+00 2.1800E+03 4035800300025 6.0000E+00 1.4770E+03 4035800300026 7.0000E+00 6.5600E+02 4035800300027 7.5000E+00 5.3700E+02 4035800300028 8.0000E+00 3.5600E+02 4035800300029 8.5000E+00 2.3000E+02 4035800300030 9.0000E+00 1.5400E+02 4035800300031 9.5000E+00 1.0900E+02 4035800300032 1.0000E+01 7.3600E+01 4035800300033 1.0500E+01 5.1000E+01 4035800300034 1.1000E+01 4.3000E+01 4035800300035 ENDDATA 21 0 4035800300036 ENDSUBENT 35 0 4035800399999 SUBENT 40358004 20130130 41594035800400001 BIB 3 9 4035800400002 REACTION (92-U-235(N,F),,NU/DE,,RRE/REL) 4035800400003 Relatively to energy 4035800400004 of incident neutron. 4035800400005 ANALYSIS Treatment by Lantsosh's method 4035800400006 HISTORY (20100812A) Reaction was corrected 4035800400007 ,DE,N,REL -> ,NU/DE,,RTE/REL 4035800400008 according to opinion N.Otsuka (NDS IAEA). 4035800400009 (20130130A) REACTION SF8 was corrected RTE -> RRE 4035800400010 according to opinion N.Otsuka (NDS IAEA). 4035800400011 ENDBIB 9 0 4035800400012 NOCOMMON 0 0 4035800400013 DATA 2 65 4035800400014 E DATA 4035800400015 MEV ARB-UNITS 4035800400016 1.5110E+00 3.8643E+04 4035800400017 1.6090E+00 3.6327E+04 4035800400018 1.7110E+00 3.2894E+04 4035800400019 1.8150E+00 2.9245E+04 4035800400020 1.9230E+00 2.7311E+04 4035800400021 2.0340E+00 2.5283E+04 4035800400022 2.1480E+00 2.2358E+04 4035800400023 2.2650E+00 2.0802E+04 4035800400024 2.3860E+00 1.9670E+04 4035800400025 2.5090E+00 1.8396E+04 4035800400026 2.6360E+00 1.6038E+04 4035800400027 2.7660E+00 1.4764E+04 4035800400028 2.8990E+00 1.3113E+04 4035800400029 3.0350E+00 1.1887E+04 4035800400030 3.1740E+00 1.0283E+04 4035800400031 3.3170E+00 9.1980E+03 4035800400032 3.4630E+00 8.1130E+03 4035800400033 3.6110E+00 7.2170E+03 4035800400034 3.7640E+00 6.4620E+03 4035800400035 3.9190E+00 5.8020E+03 4035800400036 4.0770E+00 5.1410E+03 4035800400037 4.2390E+00 4.5330E+03 4035800400038 4.4030E+00 4.1040E+03 4035800400039 4.5710E+00 3.5940E+03 4035800400040 4.7420E+00 3.0660E+03 4035800400041 4.9160E+00 2.7360E+03 4035800400042 5.0940E+00 2.5000E+03 4035800400043 5.2740E+00 2.1890E+03 4035800400044 5.4580E+00 1.8680E+03 4035800400045 5.6450E+00 1.6510E+03 4035800400046 5.8350E+00 1.3440E+03 4035800400047 6.0280E+00 1.1890E+03 4035800400048 6.2240E+00 1.0850E+03 4035800400049 6.4240E+00 8.4900E+02 4035800400050 6.6270E+00 7.7400E+02 4035800400051 6.8330E+00 6.7000E+02 4035800400052 7.0420E+00 5.6600E+02 4035800400053 7.2540E+00 4.8600E+02 4035800400054 7.4700E+00 4.1400E+02 4035800400055 7.6880E+00 3.3500E+02 4035800400056 7.9100E+00 2.7800E+02 4035800400057 8.1350E+00 2.2500E+02 4035800400058 8.3630E+00 1.8800E+02 4035800400059 8.5950E+00 1.5600E+02 4035800400060 8.8290E+00 1.3300E+02 4035800400061 9.0670E+00 1.1300E+02 4035800400062 9.3080E+00 9.2000E+01 4035800400063 9.5520E+00 7.5000E+01 4035800400064 9.7990E+00 6.3000E+01 4035800400065 1.0050E+01 5.4000E+01 4035800400066 1.0303E+01 4.6000E+01 4035800400067 1.0560E+01 3.9000E+01 4035800400068 1.0820E+01 3.2000E+01 4035800400069 1.1083E+01 2.6000E+01 4035800400070 1.1349E+01 2.1000E+01 4035800400071 1.1619E+01 1.7000E+01 4035800400072 1.1892E+01 1.4000E+01 4035800400073 1.2168E+01 1.2000E+01 4035800400074 1.2446E+01 1.1000E+01 4035800400075 1.2729E+01 7.0000E+00 4035800400076 1.3014E+01 7.0000E+00 4035800400077 1.3303E+01 5.0000E+00 4035800400078 1.3595E+01 5.0000E+00 4035800400079 1.3890E+01 4.0000E+00 4035800400080 1.4188E+01 3.0000E+00 4035800400081 ENDDATA 67 0 4035800400082 ENDSUBENT 81 0 4035800499999 SUBENT 40358005 20130130 41594035800500001 BIB 3 9 4035800500002 REACTION (92-U-235(N,F),,NU/DE,,RRE/REL) 4035800500003 Relatively to energy 4035800500004 of incident neutron. 4035800500005 ANALYSIS Treatment by Barras's method 4035800500006 HISTORY (20100812A) Reaction was corrected 4035800500007 ,DE,N,REL -> ,NU/DE,,RTE/REL 4035800500008 according to opinion N.Otsuka (NDS IAEA). 4035800500009 (20130130A) REACTION SF8 was corrected RTE -> RRE 4035800500010 according to opinion N.Otsuka (NDS IAEA). 4035800500011 ENDBIB 9 0 4035800500012 NOCOMMON 0 0 4035800500013 DATA 2 19 4035800500014 E DATA 4035800500015 MEV ARB-UNITS 4035800500016 1.5000E+00 4.0100E+04 4035800500017 2.0000E+00 3.4200E+04 4035800500018 2.5000E+00 1.7908E+04 4035800500019 3.0000E+00 1.1125E+04 4035800500020 3.5000E+00 7.6200E+03 4035800500021 4.0000E+00 5.3220E+03 4035800500022 4.5000E+00 3.5110E+03 4035800500023 5.0000E+00 2.6000E+03 4035800500024 5.5000E+00 1.7030E+03 4035800500025 6.0000E+00 1.2020E+03 4035800500026 6.5000E+00 8.2400E+02 4035800500027 7.0000E+00 5.8800E+02 4035800500028 7.5000E+00 3.9800E+02 4035800500029 8.0000E+00 2.4900E+02 4035800500030 8.5000E+00 1.4960E+02 4035800500031 9.0000E+00 1.0340E+02 4035800500032 9.5000E+00 7.2300E+01 4035800500033 1.0000E+01 5.1300E+01 4035800500034 1.0500E+01 3.6100E+01 4035800500035 ENDDATA 21 0 4035800500036 ENDSUBENT 35 0 4035800599999 ENDENTRY 5 0 4035899999999