ENTRY 40995 20221228 42114099500000001 SUBENT 40995001 20221228 42114099500100001 BIB 7 19 4099500100002 TITLE Np-236 neutron fission cross-section in the energy 4099500100003 range up to 10 keV 4099500100004 AUTHOR (G.V.Val'skiy,E.A.Gromova,V.V.Danichev,V.N.Dement'ev, 4099500100005 V.S.Zenkevich,S.S.Kovalenko,G.V.Mozolev,Yu.S.Pleva, 4099500100006 Yu.A.Selitskiy,N.I.Trubaev,A.M.Fridkin,V.B.Funshtein, 4099500100007 V.A.Yakovlev) 4099500100008 REFERENCE (C,87KIEV,3,99,1987) 4099500100009 INSTITUTE (4RUSKUR,4RUSRI,4RUSLIN) 4099500100010 SAMPLE Np-236 sample was obtained by the means of irradiation4099500100011 of U-238 by the 30-MeV protons. Sample contains 36.2 4099500100012 +-1.3 nanogram of Np-236, 5.0+-0.3 nanogram of Np-235,4099500100013 254+-8 nanogram of Np-237, 10.9+-0.5 nanogram of U-2354099500100014 ADD-RES On page 102 of C,87KIEV,3,99,1987 there are curves of 4099500100015 Np-236 C-S, C-S of admixtures U-235 and Np-237 4099500100016 taking into account their content in sample. 4099500100017 HISTORY (19890922C) Compiled at the centre - CJD 4099500100018 (20221228A) Correction for current rules. 4099500100019 Subents 005-007 are deleted - quality of curves is 4099500100020 bad for digitization, see also ADD-RES. 4099500100021 ENDBIB 19 0 4099500100022 NOCOMMON 0 0 4099500100023 ENDSUBENT 22 0 4099500199999 SUBENT 40995002 20221228 42114099500200001 BIB 7 10 4099500200002 REACTION (93-NP-236(N,F),,SIG) 4099500200003 FACILITY (REAC,4RUSLIN) Reactor WWR-M 4099500200004 INC-SOURCE (REAC) Neutrons from the graphite monochromator 4099500200005 MONITOR (92-U-235(N,F),,SIG) 4099500200006 525 +- 16 ng of U-235. 4099500200007 DETECTOR (SOLST) Mica layers between Np and U layers. 4099500200008 FF registration efficiency 96 +- 1 %. 4099500200009 ERR-ANALYS (ERR-1) Error due to the U-235 admixture in sample 4099500200010 (ERR-T) Total error 4099500200011 STATUS (TABLE) Table 1 of C,87KIEV,3,99,1987 4099500200012 ENDBIB 10 0 4099500200013 COMMON 1 3 4099500200014 ERR-1 4099500200015 PER-CENT 4099500200016 4. 4099500200017 ENDCOMMON 3 0 4099500200018 DATA 4 5 4099500200019 EN EN-RSL DATA ERR-T 4099500200020 EV EV B B 4099500200021 2.53E-02 5.E-04 2.770E+03 2.60E+02 4099500200022 1.01E-01 4.E-03 1.430E+03 9.0 E+01 4099500200023 1.62E-01 8.E-03 1.260E+03 8.0 E+01 4099500200024 2.28E-01 1.4E-02 1.22E+03 8.0 E+01 4099500200025 3.0 E-01 2. E-02 9.00E+02 7.0 E+01 4099500200026 ENDDATA 7 0 4099500200027 ENDSUBENT 26 0 4099500299999 SUBENT 40995003 20221228 42114099500300001 BIB 8 15 4099500300002 REACTION (93-NP-236(N,F),,SIG,,AV/SDT) 4099500300003 ANALYSIS Cross section averaged over 1/E spectrum in energy 4099500300004 interval in frames of 26 groups constants system. 4099500300005 FACILITY (LINAC,4RUSKUR) LUE-60 4099500300006 50 MeV electrons pulse of 50 - 100 nsec, 200 Hz 4099500300007 frequency. Electron-gamma-n converter from W . 4099500300008 5.E+12 neutron/sec. 4099500300009 MONITOR (92-U-235(N,F),,SIG) 4099500300010 METHOD (SLODT) Neutron slowing down time in lead. 4099500300011 DETECTOR (PPAC) For FF detection. 4099500300012 ERR-ANALYS (ERR-1) Error due to the detectors' efficiency 4099500300013 uncertainty 4099500300014 (ERR-S) Statistical uncertainty 4099500300015 (ERR-T) Total uncertainty 4099500300016 STATUS (TABLE) Table 2 of C,87KIEV,3,99,1987 4099500300017 ENDBIB 15 0 4099500300018 COMMON 3 3 4099500300019 ERR-1 ERR-S ERR-T 4099500300020 PER-CENT PER-CENT PER-CENT 4099500300021 3. 6. 10. 4099500300022 ENDCOMMON 3 0 4099500300023 DATA 3 14 4099500300024 EN-MIN EN-MAX DATA 4099500300025 EV EV B 4099500300026 4.65E-01 1. 465. 4099500300027 1. 2.15 260. 4099500300028 2.15 4.65 192. 4099500300029 4.65 10.0 110. 4099500300030 10.0 21.5 123. 4099500300031 21.5 46.5 69. 4099500300032 46.5 1.0E+02 45. 4099500300033 1.0 E+02 2.15E+02 31. 4099500300034 2.15E+02 4.65E+02 21.5 4099500300035 4.65E+02 1.0 E+03 15.0 4099500300036 1.0 E+03 2.15E+03 10.3 4099500300037 2.15E+03 4.65E+03 7.1 4099500300038 4.65E+03 1.0 E+04 4.9 4099500300039 1.0 E+04 2.15E+04 3.3 4099500300040 ENDDATA 16 0 4099500300041 ENDSUBENT 40 0 4099500399999 SUBENT 40995004 20221228 42114099500400001 BIB 5 8 4099500400002 REACTION (93-NP-236(N,F),,RI) 4099500400003 FACILITY (REAC,4RUSLIN) 4099500400004 (LINAC,4RUSKUR) 4099500400005 REL-REF (A,40922003,B.N.Belyaev+,J,AE,60,141,1986) Issue 2. 4099500400006 ERR-ANALYS (DATA-ERR) Error is not specified 4099500400007 STATUS (TABLE) Text page 101 of C,87KIEV,3,99,1987 4099500400008 (DEP,40995002) Measured C-S at RUSLIN 4099500400009 (DEP,40995003) Measured C-S at RUSKUR 4099500400010 ENDBIB 8 0 4099500400011 NOCOMMON 0 0 4099500400012 DATA 3 1 4099500400013 EN-MIN DATA DATA-ERR 4099500400014 EV B B 4099500400015 2.53E-02 1040. 60. 4099500400016 ENDDATA 3 0 4099500400017 ENDSUBENT 16 0 4099500499999 NOSUBENT 40995005 20221228 42114099500500001 NOSUBENT 40995006 20221228 42114099500600001 NOSUBENT 40995007 20221228 42114099500700001 SUBENT 40995008 20221228 42114099500800001 BIB 7 16 4099500800002 REACTION 1(93-NP-236(N,TOT),,WID,,AV,DERIV) 4099500800003 2(93-NP-236(N,F),,WID,,AV) 4099500800004 ASSUMED 1(ASSUM,93-NP-236(N,G),,WID,,AV) 4099500800005 Calculated in frame of giant dipole resonance model 4099500800006 by parameters from rel.ref. of S.Bjoernholm+ 4099500800007 REL-REF (R,,S.Bjoernholm+,J,RMP,52,725,1980) Issue 4. 4099500800008 FACILITY (REAC,4RUSLIN) 4099500800009 (LINAC,4RUSKUR) 4099500800010 ERR-ANALYS (DATA-ERR) Not specified 4099500800011 STATUS (TABLE) Text page 102 of C,87KIEV,3,99,1987 4099500800012 (DEP,40995002) Measured C-S at RUSLIN 4099500800013 (DEP,40995003) Measured C-S at RUSKUR 4099500800014 HISTORY (20221228A) AV -> SPA. DERIV was added in reaction. 4099500800015 AV,CALC were added in ASSUMED reaction. 4099500800016 CALC code was deleted according to a comment of 4099500800017 N.Otsuka (NDS, IAEA). 4099500800018 ENDBIB 16 0 4099500800019 COMMON 2 3 4099500800020 EN-MIN EN-MAX 4099500800021 EV EV 4099500800022 2.53E-02 2.15E+03 4099500800023 ENDCOMMON 3 0 4099500800024 DATA 5 1 4099500800025 DATA 1DATA-ERR 1ASSUM 1DATA 2DATA-ERR 2 4099500800026 EV EV EV EV EV 4099500800027 0.46 0.18 0.053 0.41 0.16 4099500800028 ENDDATA 3 0 4099500800029 ENDSUBENT 28 0 4099500899999 ENDENTRY 8 0 4099599999999