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