ENTRY 40057 20141114 41674005700000001 SUBENT 40057001 20141114 41674005700100001 BIB 12 45 4005700100002 TITLE Measurements of fission cross sections and anisotropy 4005700100003 in Uranium-232 by 0.1-1.5 MeV neutrons 4005700100004 AUTHOR (P.E.Vorotnikov,S.M.Dubrovina,G.A.Otroshchenko, 4005700100005 V.A.Shigin,A.V.Davydov,E.S.Palshin) 4005700100006 INSTITUTE (4RUSKUR) Vorotnikov, Dubrovina, Otroshchenko, Shigin 4005700100007 (4RUSGAC) Davydov, Pal'shin 4005700100008 REFERENCE (R,YFI-10,30,197011) Main reference. 4005700100009 Data tables. Text- short abstract. 4005700100010 (R,INDC(CCP)-15,32,197111)Engl.translation of YFI-10,304005700100011 (J,YF,12,(3),474,1970) 4005700100012 Detailed description of experiment. 4005700100013 (J,SNP,12,259,1971) Eng.trans.of YF,12,(3),474,1970 4005700100014 FACILITY (VDG,4RUSKUR) Van de Graaff accelerator 4005700100015 SAMPLE U-232 was obtained by chemical separation from 4005700100016 previously purified Pa-231 irradiated by reactor 4005700100017 neutrons. 4005700100018 Impurity of U-233 < 1%. 4005700100019 INC-SOURCE Neutron sources were solid targets of LiF,TiT, TiD, 4005700100020 bombarded by protons and deuterons. 4005700100021 INC-SPECT Energy resolution about 30 keV. 4005700100022 Neutron flux was monitored by long counters; absolute 4005700100023 flux was obtained by standard Pu-Be neutron source. 4005700100024 DETECTOR (GLASD) Four glass detectors for fission fragments 4005700100025 detection at angles 0,30,60,90 deg relative to incident4005700100026 neutron beam. 4005700100027 (LONGC) Long counters for neutron flux monitoring 4005700100028 ERR-ANALYS (DATA-ERR) Relative uncertainty 4005700100029 (DATA-ERR1) Error of absolute normalization. 4005700100030 (ERR-1) Neutron flux accuracy. 4005700100031 STATUS (TABLE) Data received from author, checked with 4005700100032 (APRVD) main reference and INDC(CCP)-15 4005700100033 HISTORY (19710322C) Compiled at the CJD 4005700100034 (19980531U) BIB-information updated, 4005700100035 ISO-QUANT converted to REACTION 4005700100036 final corrections are made 4005700100037 (19980618U) .institute code 'GAK' corrected to 'GAC' 4005700100038 .ERR-1 changed to DATA-ERR1 4005700100039 (20141114U) SD: Updated to new date formats,lower case.4005700100040 Corrections according last EXFOR rules and Dict. 4005700100041 Ref. on Engl. transl. of YF added. 4005700100042 (20150125A) M.M. Articles were checked, BIB information4005700100043 was updated in AUTHOR,TITLE,STATUS,REFERENCE, SAMPLE, 4005700100044 INC-SOURCE,INC-SPECT,DETECTOR,ERR-ANALYS,MONITOR, 4005700100045 ANALYSIS,REL-REF . 4005700100046 EN-NRM, MONIT were added. 4005700100047 ENDBIB 45 0 4005700100048 COMMON 2 3 4005700100049 DATA-ERR1 ERR-1 4005700100050 PER-CENT PER-CENT 4005700100051 15. 7. 4005700100052 ENDCOMMON 3 0 4005700100053 ENDSUBENT 52 0 4005700199999 SUBENT 40057002 20141114 41674005700200001 BIB 5 21 4005700200002 REACTION (92-U-232(N,F),,SIG) 4005700200003 MONITOR ((MONIT)92-U-232(N,F),,SIG) 4005700200004 ANALYSIS Counting rates of all four detectors were used. 4005700200005 Detection probability was taken as 100.%. 4005700200006 Number of U-232 atoms in layer was defined by 4005700200007 - counting alpha-particles from U-232 decay and its 4005700200008 daughter elements in semiconductor alpha spectrometer, 4005700200009 - comparison of number of fissions in U-232 layer and 4005700200010 in a layer of U-natural, calibrated by its alpha 4005700200011 activity and placed back-to-back with U232 layer, in 4005700200012 thermal-neutron flux and at flux of 1000-keV neutrons. 4005700200013 At En=100 keV, fis.c-s obtained were 2.0+-0.35 and 4005700200014 2.6+-0.5 b, thus the weighted mean 2.2+-0.3 b. 4005700200015 The data of energies, half-lives, alpha-decay 4005700200016 intensities were used from: 4005700200017 REL-REF I.P.Perlman,J.Rasmussen,Alpha Radioactivity, 4005700200018 Russ.Transl., IIL,1959 . 4005700200019 (R,,,R,BNL-325,1965) 2nd edition, Suppl. 2 . 4005700200020 Fission cross-section from Brookhaven atlas. 4005700200021 STATUS (TABLE) Table I of R,YFI-10,30,1970 4005700200022 Cross section is on Fig.2 of J,YF,12,(3),474,1970 4005700200023 ENDBIB 21 0 4005700200024 COMMON 3 3 4005700200025 EN-NRM MONIT MONIT-ERR 4005700200026 KEV B B 4005700200027 1000. 2.2 0.3 4005700200028 ENDCOMMON 3 0 4005700200029 DATA 4 22 4005700200030 EN EN-ERR DATA DATA-ERR 4005700200031 KEV KEV B B 4005700200032 125. 10. 2.72 0.03 4005700200033 180. 10. 2.53 0.03 4005700200034 220. 10. 2.35 0.04 4005700200035 265. 17. 2.33 0.04 4005700200036 280. 10. 2.16 0.06 4005700200037 390. 15. 2.20 0.04 4005700200038 420. 15. 2.11 0.03 4005700200039 530. 15. 2.02 0.04 4005700200040 625. 15. 2.11 0.03 4005700200041 680. 15. 2.19 0.04 4005700200042 730. 15. 2.16 0.03 4005700200043 825. 15. 2.19 0.04 4005700200044 880. 15. 2.19 0.03 4005700200045 920. 15. 2.18 0.03 4005700200046 1020. 15. 2.26 0.05 4005700200047 1030. 15. 2.19 0.06 4005700200048 1120. 15. 2.16 0.03 4005700200049 1220. 15. 2.22 0.04 4005700200050 1230. 15. 2.25 0.06 4005700200051 1320. 15. 2.20 0.04 4005700200052 1400. 15. 2.15 0.04 4005700200053 1480. 15. 2.27 0.09 4005700200054 ENDDATA 24 0 4005700200055 ENDSUBENT 54 0 4005700299999 SUBENT 40057003 20141114 41674005700300001 BIB 3 5 4005700300002 REACTION (92-U-232(N,F),,DA,FF,RSD) 4005700300003 STATUS (TABLE) Table II of R,YFI-10,30,1970 4005700300004 Anisotropy is on Fig.1 of J,YF,12,(3),474,1970 4005700300005 HISTORY (19980531A) Several data points were added 4005700300006 from YFI-10,30 4005700300007 ENDBIB 5 0 4005700300008 COMMON 1 3 4005700300009 ANG 4005700300010 ADEG 4005700300011 0. 4005700300012 ENDCOMMON 3 0 4005700300013 DATA 4 33 4005700300014 EN EN-ERR DATA DATA-ERR 4005700300015 KEV KEV NO-DIM NO-DIM 4005700300016 125. 10. 1.15 0.04 4005700300017 180. 10. 1.18 0.04 4005700300018 220. 17. 1.16 0.04 4005700300019 230. 10. 1.23 0.10 4005700300020 265. 17. 1.19 0.05 4005700300021 280. 10. 1.18 0.06 4005700300022 380. 15. 1.27 0.06 4005700300023 390. 15. 1.22 0.05 4005700300024 420. 15. 1.14 0.04 4005700300025 480. 15. 1.02 0.04 4005700300026 520. 15. 1.07 0.04 4005700300027 530. 15. 1.06 0.04 4005700300028 580. 15. 0.99 0.04 4005700300029 625. 15. 0.96 0.04 4005700300030 680. 15. 0.97 0.03 4005700300031 690. 15. 0.97 0.04 4005700300032 730. 15. 0.99 0.03 4005700300033 780. 15. 1.18 0.06 4005700300034 785. 15. 1.10 0.05 4005700300035 825. 15. 1.06 0.03 4005700300036 880. 15. 1.09 0.04 4005700300037 920. 15. 0.97 0.03 4005700300038 980. 15. 1.03 0.03 4005700300039 1020. 15. 1.06 0.04 4005700300040 1030. 15. 1.05 0.05 4005700300041 1120. 15. 1.09 0.03 4005700300042 1220. 15. 1.15 0.04 4005700300043 1230. 15. 1.14 0.05 4005700300044 1320. 15. 1.15 0.04 4005700300045 1330. 15. 1.18 0.04 4005700300046 1400. 15. 1.14 0.04 4005700300047 1480. 15. 1.15 0.09 4005700300048 5000. 65. 1.14 0.04 4005700300049 ENDDATA 35 0 4005700300050 ENDSUBENT 49 0 4005700399999 ENDENTRY 3 0 4005799999999