ENTRY 41675 20190805 41834167500000001 SUBENT 41675001 20190805 41834167500100001 BIB 12 29 4167500100002 INSTITUTE (4RUSFEI) 4167500100003 REFERENCE (J,JET,8,367,1959) Eng.transl.of: 4167500100004 (J,ZET,35,532,1958) 4167500100005 AUTHOR (V.G.Nesterov,G.N.Smirenkin) 4167500100006 TITLE Fission cross section of Pu240 by fast neutrons 4167500100007 REL-REF (N,40021001,V.G.Nesterov+,J,AE,9,16,1960) 4167500100008 Re-measured data 4167500100009 FACILITY (VDG,4RUSFEI) For P-T incident source. 4167500100010 (NGEN,4RUSFEI) Cascade generator 4167500100011 for D-D and D-T incident sources. 4167500100012 INC-SOURCE (P-T) For neutron energy < 2 MeV 4167500100013 (D-D) For 2 - 4 MeV 4167500100014 (D-T) For 15 MeV 4167500100015 SAMPLE Pu-240 (2.5 mg) and Pu-239 4 mg) layers of 5 cm diam.4167500100016 were deposited on common high-voltage electrode. 4167500100017 Pu-239 layer contained 1.80+-0.05% of Pu-240. 4167500100018 Pu-240 layer contained 7.7+-0.5% of Pu-239, 4167500100019 < 0.2% of Pu-241. 4167500100020 METHOD Thermal neutrons ( obtained by moderating fast 4167500100021 neutrons in a paraffin block; Cd was used to exclude 4167500100022 resonance neutrons) were used to determine the ratio 4167500100023 of effective amounts of fissionable matter in the 4167500100024 chambers. 4167500100025 DETECTOR (FISCH) Working gas 90% Ar + 10% CO(2) at pressure 4167500100026 35mm Hg. 4167500100027 MONITOR (94-PU-239(N,F),,SIG) 4167500100028 Pu-239 CS were obtained by averaging the data of 4167500100029 latest investigations of these authors. 4167500100030 HISTORY (20190805C) 4167500100031 ENDBIB 29 0 4167500100032 NOCOMMON 0 0 4167500100033 ENDSUBENT 32 0 4167500199999 SUBENT 41675002 20190805 41834167500200001 BIB 3 4 4167500200002 REACTION (94-PU-240(N,F),,SIG) 4167500200003 REL-REF (A,,G.A.Dorofeev+,J,AE,2,10,1957) 4167500200004 STATUS (CURVE) Fig. in 4167500200005 J.of Exp. and Theor. Physics,v.8,p.367,1959 4167500200006 ENDBIB 4 0 4167500200007 COMMON 2 3 4167500200008 EN-ERR-DIG ERR-DIG 4167500200009 PER-CENT PER-CENT 4167500200010 0.23679 0.43962 4167500200011 ENDCOMMON 3 0 4167500200012 DATA 2 19 4167500200013 EN DATA 4167500200014 MEV B 4167500200015 1.412E-01 6.283E-02 4167500200016 2.510E-01 7.888E-02 4167500200017 3.628E-01 1.202E-01 4167500200018 4.268E-01 1.698E-01 4167500200019 5.021E-01 2.426E-01 4167500200020 5.716E-01 3.778E-01 4167500200021 6.437E-01 6.011E-01 4167500200022 7.018E-01 8.401E-01 4167500200023 7.737E-01 9.360E-01 4167500200024 8.716E-01 1.187E+00 4167500200025 9.300E-01 1.426E+00 4167500200026 1.095E+00 1.473E+00 4167500200027 1.331E+00 1.555E+00 4167500200028 1.844E+00 1.382E+00 4167500200029 2.217E+00 1.412E+00 4167500200030 2.941E+00 1.460E+00 4167500200031 3.424E+00 1.508E+00 4167500200032 3.942E+00 1.644E+00 4167500200033 1.404E+01 2.649E+00 4167500200034 ENDDATA 21 0 4167500200035 ENDSUBENT 34 0 4167500299999 SUBENT 41675003 20190805 41834167500300001 BIB 3 5 4167500300002 REACTION (94-PU-240(N,F),,SIG) 4167500300003 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 4167500300004 article. 4167500300005 STATUS (TABLE) Text, page 368 in 4167500300006 J.of Exp. and Theor. Physics,v.8,p.367,1959 4167500300007 ENDBIB 5 0 4167500300008 NOCOMMON 0 0 4167500300009 DATA 3 1 4167500300010 EN DATA DATA-ERR 4167500300011 MEV B B 4167500300012 15. 2.6 0.2 4167500300013 ENDDATA 3 0 4167500300014 ENDSUBENT 13 0 4167500399999 SUBENT 41675004 20190805 41834167500400001 BIB 4 8 4167500400002 REACTION (94-PU-240(N,F),,SIG,,AV) 4167500400003 Fission cross section at the plateau 4167500400004 REL-REF (A,40355002,G.A.Dorofeev+,J,AE,2,10,1957) 4167500400005 1.40+-0.15 b for neutrons from Ra-Be source 4167500400006 ERR-ANALYS (DATA-ERR) Type of error is not explained in the 4167500400007 article. 4167500400008 STATUS (TABLE) Text, page 368 in 4167500400009 J.of Exp. and Theor. Physics,v.8,p.367,1959 4167500400010 ENDBIB 8 0 4167500400011 NOCOMMON 0 0 4167500400012 DATA 4 1 4167500400013 EN-MIN EN-MAX DATA DATA-ERR 4167500400014 MEV MEV B B 4167500400015 2. 4. 1.50 0.15 4167500400016 ENDDATA 3 0 4167500400017 ENDSUBENT 16 0 4167500499999 ENDENTRY 4 0 4167599999999