ENTRY 41500 20191116 41844150000000001 SUBENT 41500001 20191116 41844150000100001 BIB 12 52 4150000100002 TITLE Cumulative yields of delayed neutrons precursors in 4150000100003 neutron induced fission of 237-Np and 238-U in the 4150000100004 energy range from 0.5 up to 5. MeV. 4150000100005 AUTHOR (V.A.Roshchenko, V.M.Piksaykin, G.G.Korolev, 4150000100006 Yu.F.Balakshev, S.G.Isaev) 4150000100007 INSTITUTE (4RUSFEI) 4150000100008 REFERENCE (J,YF,62,1358,1999) Iss. 8 4150000100009 Schemes of experiment , graphs. 4150000100010 (J,PAN,62,1279,1999) 4150000100011 (J,YK,,(1-2),43,2006) Data table for Np-237. 4150000100012 (R,INDC(CCP)-445,15,2007) Engl.translation of J,YK 4150000100013 REL-REF (I,,V.M.Piksaikin+,J,YK,,(1-2),26,1997) 4150000100014 Detector efficiency measurement details. 4150000100015 (R,,R.J.Tuttle+,R,INDC(NDS)-107,29,1979) 4150000100016 FACILITY (VDG) Electrostatic accelerator KG-2.5 4150000100017 Pneumatic system to transport the sample from 4150000100018 radiation position into neutron detector and backward.4150000100019 Transportation time about 150 ms. 4150000100020 INC-SOURCE (P-T) T(P,N) Reaction on solid tritium-titanium target.4150000100021 (D-D) D(D,N) Reaction on solid deuterium-titanium 4150000100022 target. 4150000100023 SAMPLE Np-237 sample as cylinder of 0.56 cm diameter, 0.35 cm4150000100024 high, from pressed powder of neptunium oxide. 4150000100025 Np-237 sample weight - 2.281 g. 4150000100026 U-235 samples from metallic uranium of 90% enrichment.4150000100027 U-235 sample weight - 2.466 g. 4150000100028 Each sample was in stainless steel capsule of 0.3mm 4150000100029 thickness walls, installed in titanium container. 4150000100030 DETECTOR (D4PI) Distributed in polyethylene moderator along 4150000100031 three concentric circles with diameters of 53, 4150000100032 80 and 110 mm assemblage of 30 boron counters 4150000100033 SNM-11 was used for neutron detection. 4150000100034 Protection by boron carbide, cadmium and borated 4150000100035 polyethylene. 4150000100036 Detector efficiency was measured at additional 4150000100037 experiment. See 1st REL-REF. 4150000100038 (FISCH) Two fission chambers near sample for fission 4150000100039 reaction rate measurement and neutron beam monitoring.4150000100040 METHOD (ACTIV) Cyclic radiation. 4150000100041 Time channel widths- 0.01, 0.02, 0.1, 1., 10. sec. 4150000100042 Total irradiation time -300.s, counting time 720.sec. 4150000100043 CORRECTION Corrections were made for: 4150000100044 multiple neutron scattering, 4150000100045 neutron scattering in materials of facility, 4150000100046 neutrons multiplication in fissionable samples, 4150000100047 admixture of U-238 in U-235 sample. 4150000100048 HISTORY (20070827C) Compiled at CJD. M.M. 4150000100049 (20080903A) M.M. Units were corrected : 4150000100050 PC/FIS -> PRT/FIS in Subent 003 . 4150000100051 (20130218U) Ref. J,PAN,62,(8),1279,1999, and 4150000100052 R,INDC(CCP)-445,15,2007 were added. 4150000100053 (20191116U) Refs. YK were corrected 4150000100054 ENDBIB 52 0 4150000100055 NOCOMMON 0 0 4150000100056 ENDSUBENT 55 0 4150000199999 SUBENT 41500002 20191116 41844150000200001 BIB 4 9 4150000200002 REACTION (93-NP-237(N,F),DL,NU) 4150000200003 ANALYSIS Absolute total delayed neutron yields were measured at4150000200004 En=1.154 and 3.868 MeV. 4150000200005 Energy dependence of relative total delayed neutrons 4150000200006 yields was measured in range En= 1. - 5. MeV, 4150000200007 normalized to total measured yield at En=1.154 MeV. 4150000200008 ERR-ANALYS (DATA-ERR) Errors are not specified. 4150000200009 STATUS (TABLE) From Table 2 of INDC(CCP)-445,15,2007 4150000200010 (DEP,41291007) 4150000200011 ENDBIB 9 0 4150000200012 NOCOMMON 0 0 4150000200013 DATA 3 8 4150000200014 EN DATA DATA-ERR 4150000200015 MEV PC/FIS PC/FIS 4150000200016 0.370 1.141 0.054 4150000200017 0.600 1.141 0.054 4150000200018 0.800 1.141 0.054 4150000200019 1.08 1.141 0.054 4150000200020 3.231 1.006 0.048 4150000200021 3.745 0.948 0.045 4150000200022 4.196 0.926 0.044 4150000200023 4.719 0.897 0.042 4150000200024 ENDDATA 10 0 4150000200025 ENDSUBENT 24 0 4150000299999 SUBENT 41500003 20191116 41844150000300001 BIB 4 12 4150000300002 REACTION (92-U-235(N,F),DL,NU) 4150000300003 ANALYSIS Absolute total delayed neutron yields were measured at4150000300004 En=1.165 MeV (EXFOR 41291.006). 4150000300005 Energy dependence of relative total delayed neutrons 4150000300006 yields was measured in range En= 0.769 - 5. MeV, 4150000300007 normalized at En=0.769 MeV to value, which was 4150000300008 obtained by linear interpolation of evaluated data 4150000300009 values for thermal and fast neutrons from 2nd REL-REF.4150000300010 ERR-ANALYS (DATA-ERR) Error bar on Fig.5. 4150000300011 Type of error is not explained in the article. 4150000300012 STATUS (CURVE) Fig.5 of Yad.Fiz.,62,1358,1999 4150000300013 (DEP,41291006) 4150000300014 ENDBIB 12 0 4150000300015 COMMON 2 3 4150000300016 EN-ERR-DIG ERR-DIG 4150000300017 MEV PRT/FIS 4150000300018 0.446E-02 0.682E-05 4150000300019 ENDCOMMON 3 0 4150000300020 DATA 3 5 4150000300021 EN DATA DATA-ERR 4150000300022 MEV PRT/FIS PRT/FIS 4150000300023 0.769 0.166E-01 0.732E-03 4150000300024 3.302 0.158E-01 0.102E-02 4150000300025 3.848 0.159E-01 0.102E-02 4150000300026 4.325 0.144E-01 0.865E-03 4150000300027 4.882 0.139E-01 0.865E-03 4150000300028 ENDDATA 7 0 4150000300029 ENDSUBENT 28 0 4150000399999 ENDENTRY 3 0 4150099999999