ENTRY 41058 20111021 41544105800000001 SUBENT 41058001 20111021 41544105800100001 BIB 14 43 4105800100002 TITLE Measurement of the ratio of the cross sections for 4105800100003 fission of 243-Am and 235-U by 5-10.5-MeV neutrons 4105800100004 AUTHOR (A.A.Goverdovsky,A.K.Gordyushin,B.D.Kuz'minov, 4105800100005 V.F.Mitrofanov,A.I.Sergachev,S.M.Solov'ev, 4105800100006 T.E.Kuz'mina) 4105800100007 INSTITUTE (4RUSFEI) A.A.Goverdovsky=A.A.Goverdovskiy 4105800100008 REFERENCE (J,AE,67,(1),30,198907) Data table is given 4105800100009 (J,SJA,67,(1),524,1989) Engl.translation of J,AE,67 . 4105800100010 #doi:10.1007/BF01126393 4105800100011 FACILITY (VDG) Accelerator EGP-10M, pulse frequency 5 MHz, 4105800100012 pulse duration 1 nanosec 4105800100013 INC-SOURCE (D-D) 4105800100014 DETECTOR (FISCH) Double ionization chamber, xenon 90%, 4105800100015 methane 10%,pressure 1.1E+5 Pa 4105800100016 Fission fragments registration efficiency 95 %. 4105800100017 SAMPLE Thin foils from americium and uranium oxides on 4105800100018 aluminum backing. U-235 content 99.992 %. 4105800100019 ...1st sample - Am-243 content 97.3+-0.1 % , 4105800100020 Am-241 content 2.7+-0.1 % , Pu-242 content 0.009 % . 4105800100021 ...2nd sample - Am-243 content 63.5+-0.2 % , 4105800100022 Am-241 content 1.70+-0.05 % , Pu-242 content 0.0060 % 4105800100023 U-235 content 35.8+-0.5 %. 4105800100024 METHOD (TOF) Flight path < 20 cm. Time resolution 3 ns (FWHM).4105800100025 (MOMIX) 2-nd sample. 4105800100026 CORRECTION Correction due to fission of admixed isotopes by fast 4105800100027 neutrons 0.5%, due to neutron scattering on detector 4105800100028 and on backings 0.3%, on finite space between layers 4105800100029 0.2%, on fission fragments slowing-down in layers 4105800100030 0.4%, on the experimental hall background 4. % . 4105800100031 MONITOR .. NO INFORMATION.. 4105800100032 STATUS Data are taken from the reference 4105800100033 ERR-ANALYS (ERR-1) Error of normalization of the energy 4105800100034 dependence. 4105800100035 (ERR-2) Error of fission fragments counts due to fast 4105800100036 neutrons. 4105800100037 (ERR-3) Error of U-235 nucleus relative content in 4105800100038 samples. 4105800100039 (ERR-4) Error due to registration efficiency. 4105800100040 (ERR-5) Error of the background determination. 4105800100041 (ERR-6) Error the corrections. 4105800100042 (ERR-7) Error of fission counts due to slow neutrons. 4105800100043 (ERR-S) Statistical error. 4105800100044 HISTORY (19920309C) + + Compiled at the centre - CJD + + 4105800100045 ENDBIB 43 0 4105800100046 COMMON 7 6 4105800100047 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 4105800100048 ERR-7 4105800100049 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4105800100050 PER-CENT 4105800100051 2.5 1. 1.5 1.2 0.5 0.3 4105800100052 0.3 4105800100053 ENDCOMMON 6 0 4105800100054 ENDSUBENT 53 0 4105800199999 SUBENT 41058002 20111021 41544105800200001 BIB 2 3 4105800200002 REACTION ((95-AM-243(N,F),,SIG)/(92-U-235(N,F),,SIG)) 4105800200003 STATUS (TABLE) Table 2 of J,AE,67,(1),30,1989 . 4105800200004 (DEP,40912002) previous publication. 4105800200005 ENDBIB 3 0 4105800200006 COMMON 1 3 4105800200007 EN-NRM 4105800200008 MEV 4105800200009 7.34 4105800200010 ENDCOMMON 3 0 4105800200011 DATA 5 32 4105800200012 EN EN-ERR DATA ERR-S ERR-T 4105800200013 MEV MEV NO-DIM PER-CENT PER-CENT 4105800200014 4.97 0.16 1.552 0.9 3.6 4105800200015 5.21 0.16 1.567 1.1 2.8 4105800200016 5.41 0.15 1.560 1.3 2.8 4105800200017 5.64 0.14 1.655 1.5 2.9 4105800200018 5.89 0.14 1.634 0.5 2.6 4105800200019 6.14 0.13 1.586 1.2 2.8 4105800200020 6.38 0.12 1.598 1.1 2.8 4105800200021 6.56 0.11 1.593 1.0 3.7 4105800200022 6.79 0.11 1.573 0.8 2.4 4105800200023 6.96 0.10 1.522 1.0 2.7 4105800200024 7.19 0.10 1.503 0.7 2.6 4105800200025 7.35 0.10 1.502 0.7 2.6 4105800200026 7.58 0.10 1.472 0.8 2.6 4105800200027 7.74 0.09 1.481 0.9 2.7 4105800200028 7.90 0.09 1.494 0.9 2.6 4105800200029 8.07 0.09 1.492 0.9 2.7 4105800200030 8.23 0.09 1.473 0.7 2.6 4105800200031 8.39 0.08 1.429 0.8 3.6 4105800200032 8.55 0.08 1.420 0.8 2.6 4105800200033 8.86 0.08 1.393 1.0 2.8 4105800200034 9.02 0.07 1.391 0.7 2.7 4105800200035 9.18 0.07 1.423 1.1 2.8 4105800200036 9.33 0.07 1.409 1.2 2.8 4105800200037 9.49 0.07 1.417 1.0 2.8 4105800200038 9.59 0.07 1.411 0.7 2.7 4105800200039 9.74 0.07 1.423 0.8 3.7 4105800200040 9.85 0.07 1.429 0.8 2.7 4105800200041 9.95 0.06 1.418 1.1 2.8 4105800200042 10.05 0.06 1.409 0.9 2.7 4105800200043 10.20 0.06 1.391 1.0 2.8 4105800200044 10.31 0.06 1.369 0.8 2.7 4105800200045 10.41 0.06 1.392 0.8 2.7 4105800200046 ENDDATA 34 0 4105800200047 ENDSUBENT 46 0 4105800299999 ENDENTRY 2 0 4105899999999