ENTRY 40021 20141109 41674002100000001 SUBENT 40021001 20141109 41674002100100001 BIB 15 53 4002100100002 INSTITUTE (4RUSFEI) 4002100100003 REFERENCE (J,AE,9,(1),16,196007) 4002100100004 (J,SJA,9,511,1961) Eng.transl.of AE,9,16,1960 4002100100005 (R,ICD-1,260,196408) Tabulated data. 4002100100006 (R,INDC(CCP)-005,22,1964) Title only. 4002100100007 AUTHOR (V.G.Nesterov,G.N.Smirenkin) 4002100100008 TITLE 0.04 - 4.0 MeV neutron fission cross section of Pu-240.4002100100009 FACILITY (VDG,4RUSFEI) 5. MeV Van de Graaff 4002100100010 INC-SOURCE (P-T) Proton-tritium reaction 4002100100011 INC-SPECT Monochromatic neutrons. 4002100100012 Energy resolution from 15 to 35 keV. 4002100100013 SAMPLE Content of Pu-240 in Pu-239 sample = 1.80+-0.05% , 4002100100014 content of Pu-241 was negligibly small. 4002100100015 Content of Pu-239 in Pu-240 sample = 7.35+-0.15%, 4002100100016 content of Pu-241 was less 0.2 %. 4002100100017 Pu-240 ( 2.5 mg) and Pu-239 ( 4 mg) layers of about 4002100100018 0.2 mg/cm2 were deposit on common high-voltage 4002100100019 electrode. 4002100100020 Mixture of Ar (93%) and CO(2) ( 7.%) under pressure 4002100100021 about 120 mm Hg was used as working gas. 4002100100022 METHOD Counters ratio N40/N39 of fission fragments from 4002100100023 94-Pu-240 and 94-Pu-239 which were placed in the same 4002100100024 fission chamber. 4002100100025 N40/N39 was measured also in a flux of thermal neutrons4002100100026 obtained by moderating fast neutrons in paraffin block.4002100100027 DETECTOR (FISCH) Double fission chamber in cadmium shield of 4002100100028 0.5 mm thickness. 4002100100029 MONITOR (94-PU-239(N,F),,SIG) 4002100100030 The energy dependence of Pu-239 fis. c-s ( used for 4002100100031 calculating the absolute energy dependence of Pu-240 4002100100032 fis. c-s) was obtained by averaging the data from : 4002100100033 MONIT-REF (,A.Hemmendinger,C,58GENEVA,2,89,1959) 4002100100034 (,D.Hughes+,R,BNL-4,1958) 4002100100035 D.Hughes,R.Schwartz. Neutron Cross Sections, 4002100100036 BNL-4,1958 and A.Hemmendinger, 58GENEVA, selected 4002100100037 reports of Foreign Scientists.V.2 - Nejtronnaja 4002100100038 Fizika. M.Atomizdat. 1959.Page 89. 4002100100039 CORRECTION For Pu-241 presence, from 3% to 0.2 % at 1.1 to 1 MeV 4002100100040 energy. 4002100100041 Background due to scattered neutrons < 1.5% at 0 deg 4002100100042 angle and < 5% at other angles. 4002100100043 REL-REF (O,40650001,V.G.Nesterov+,R,ICD-1,260,1964) 4002100100044 Final data for U-233,235,Pu-239 (Table 1 in 4002100100045 R,ICD-1,260,1964). 4002100100046 HISTORY (19700821C) 4002100100047 (20060621A) Misprint in DATA of Sub.002 was corrected. 4002100100048 Dates were corrected for 4-digits year. M.M. 4002100100049 (20141109U) SD: Ref. on Engl.transl. of AE added. 4002100100050 (20141223A) M.M. 4002100100051 STATUS,ANALYSIS,ERR-ANALYS,CORRECTION were added. 4002100100052 INDC(CCP)-005 ref. was added. 4002100100053 Articles were checked, BIB information was updated in 4002100100054 TITLE,SAMPLE,METHOD,DETECTOR,MONITOR,MONIT-REF. 4002100100055 ENDBIB 53 0 4002100100056 NOCOMMON 0 0 4002100100057 ENDSUBENT 56 0 4002100199999 SUBENT 40021002 20141223 41674002100200001 BIB 4 17 4002100200002 REACTION (94-PU-240(N,F),,SIG) 4002100200003 Average result of several measurement series. 4002100200004 ANALYSIS Pu-240 fis.c-s was defined as: 4002100200005 SIG(Pu239)*(A-1)/(alpha0*(C-A)), 4002100200006 A=(N40/N39)*(N39thermal/N40thermal), 4002100200007 C=alpha/alpha0 = 675+-15, 4002100200008 alpha - the ratio of Pu240 nuclei to the number of 4002100200009 Pu239 nuclei in Pu-240 sample; 4002100200010 ERR-ANALYS (DATA-ERR) Not specified in ICD-1,260. Probably total. 4002100200011 Errors in SIG(Pu240)/SIG(Pu239) are mainly from 4002100200012 statistical accuracy of A, alpha0, C, 4002100200013 at EN <0.3 MeV the main contribution is due to error of4002100200014 subtraction of number of Pu-240 spontaneous fission, 4002100200015 which amounts 50-80% of the total number of fissions 4002100200016 events; at other energies this contribution < 2%. 4002100200017 (MONIT-ERR) Pu-239 Fission c-s error. 4002100200018 STATUS (TABLE) Table 2 of R,ICD-1,260,1964 . 4002100200019 ENDBIB 17 0 4002100200020 COMMON 1 3 4002100200021 MONIT-ERR 4002100200022 PER-CENT 4002100200023 5. 4002100200024 ENDCOMMON 3 0 4002100200025 DATA 3 73 4002100200026 EN DATA DATA-ERR 4002100200027 MEV B PER-CENT 4002100200028 4.0000E-02 9.0000E-02 1.5000E+01 4002100200029 6.0000E-02 6.0000E-02 1.5000E+01 4002100200030 9.0000E-02 6.0000E-02 1.5000E+01 4002100200031 1.2500E-01 6.0000E-02 1.5000E+01 4002100200032 1.6000E-01 6.0000E-02 1.5000E+01 4002100200033 2.0000E-01 1.0000E-01 1.5000E+01 4002100200034 2.3000E-01 1.1000E-01 1.5000E+01 4002100200035 2.8000E-01 1.4000E-01 1.5000E+01 4002100200036 3.3000E-01 1.5000E-01 8.0000E+00 4002100200037 3.7000E-01 1.9000E-01 8.0000E+00 4002100200038 4.1500E-01 2.3000E-01 8.0000E+00 4002100200039 4.4500E-01 3.0000E-01 8.0000E+00 4002100200040 4.6500E-01 3.3000E-01 8.0000E+00 4002100200041 4.8500E-01 3.5000E-01 8.0000E+00 4002100200042 5.0500E-01 4.1000E-01 8.0000E+00 4002100200043 5.3000E-01 4.7000E-01 8.0000E+00 4002100200044 5.5500E-01 5.2000E-01 8.0000E+00 4002100200045 5.7500E-01 6.1000E-01 8.0000E+00 4002100200046 5.9500E-01 6.9000E-01 8.0000E+00 4002100200047 6.2500E-01 7.1000E-01 8.0000E+00 4002100200048 6.5000E-01 7.3000E-01 8.0000E+00 4002100200049 6.7000E-01 8.2000E-01 8.0000E+00 4002100200050 6.9000E-01 8.6000E-01 8.0000E+00 4002100200051 7.1500E-01 9.1000E-01 8.0000E+00 4002100200052 7.4500E-01 9.7000E-01 8.0000E+00 4002100200053 7.7000E-01 1.0100E+00 8.0000E+00 4002100200054 7.8500E-01 1.0500E+00 8.0000E+00 4002100200055 8.1500E-01 1.1100E+00 8.0000E+00 4002100200056 8.3000E-01 1.1800E+00 8.0000E+00 4002100200057 8.5000E-01 1.2300E+00 8.0000E+00 4002100200058 8.7000E-01 1.2200E+00 8.0000E+00 4002100200059 9.1500E-01 1.2800E+00 8.0000E+00 4002100200060 9.2500E-01 1.4400E+00 8.0000E+00 4002100200061 9.4000E-01 1.4800E+00 8.0000E+00 4002100200062 9.7500E-01 1.4800E+00 8.0000E+00 4002100200063 1.0050E+00 1.5100E+00 4.0000E+00 4002100200064 1.0250E+00 1.6200E+00 4.0000E+00 4002100200065 1.0550E+00 1.6000E+00 4.0000E+00 4002100200066 1.0800E+00 1.5700E+00 4.0000E+00 4002100200067 1.1000E+00 1.5300E+00 4.0000E+00 4002100200068 1.1300E+00 1.5900E+00 4.0000E+00 4002100200069 1.1550E+00 1.6600E+00 4.0000E+00 4002100200070 1.1750E+00 1.6900E+00 4.0000E+00 4002100200071 1.2050E+00 1.6500E+00 4.0000E+00 4002100200072 1.2250E+00 1.6300E+00 4.0000E+00 4002100200073 1.2500E+00 1.6200E+00 4.0000E+00 4002100200074 1.2700E+00 1.6100E+00 4.0000E+00 4002100200075 1.3200E+00 1.6100E+00 4.0000E+00 4002100200076 1.3700E+00 1.6100E+00 4.0000E+00 4002100200077 1.4300E+00 1.6100E+00 4.0000E+00 4002100200078 1.4800E+00 1.5900E+00 4.0000E+00 4002100200079 1.5050E+00 1.5700E+00 4.0000E+00 4002100200080 1.5200E+00 1.5500E+00 4.0000E+00 4002100200081 1.5650E+00 1.5400E+00 4.0000E+00 4002100200082 1.5900E+00 1.6200E+00 4.0000E+00 4002100200083 1.6300E+00 1.6000E+00 4.0000E+00 4002100200084 1.6650E+00 1.5900E+00 4.0000E+00 4002100200085 1.7050E+00 1.6500E+00 4.0000E+00 4002100200086 1.7650E+00 1.7100E+00 4.0000E+00 4002100200087 1.8100E+00 1.6900E+00 4.0000E+00 4002100200088 1.8650E+00 1.6200E+00 4.0000E+00 4002100200089 1.9350E+00 1.5900E+00 4.0000E+00 4002100200090 1.9850E+00 1.6100E+00 4.0000E+00 4002100200091 2.1700E+00 1.6200E+00 4.0000E+00 4002100200092 2.3100E+00 1.6600E+00 4.0000E+00 4002100200093 2.4300E+00 1.7100E+00 4.0000E+00 4002100200094 2.5700E+00 1.6500E+00 4.0000E+00 4002100200095 2.7250E+00 1.6400E+00 4.0000E+00 4002100200096 2.8400E+00 1.6300E+00 4.0000E+00 4002100200097 2.9950E+00 1.5900E+00 4.0000E+00 4002100200098 3.1450E+00 1.6000E+00 4.0000E+00 4002100200099 3.4200E+00 1.6400E+00 4.0000E+00 4002100200100 3.7900E+00 1.6800E+00 4.0000E+00 4002100200101 ENDDATA 75 0 4002100200102 ENDSUBENT 101 0 4002100299999 ENDENTRY 2 0 4002199999999