ENTRY 41512 20200609 41884151200000001 SUBENT 41512001 20200609 41884151200100001 BIB 15 72 4151200100002 TITLE Experimental studies of the absolute total delayed 4151200100003 neutron yields from neutron induced fission of U-236 4151200100004 in the energy rage 1-5 MeV. 4151200100005 REFERENCE ((S,ISINN-14,144,2007)= 4151200100006 (S,JINR-E3-2007-23,144,2007)) 4151200100007 Main reference. 4151200100008 (R,INDC(NDS)-0646,2013) In English. 4151200100009 AUTHOR (V.A.Roschenko, V.M.Piksaykin, G.G.Korolev, 4151200100010 Yu.F.Balakshev,A.S.Egorov, K.V.Mitrofanov) 4151200100011 INSTITUTE (4RUSFEI) 4151200100012 FACILITY (VDG,4RUSFEI) Cascade Generator CG-2.5. 4151200100013 Pneumatic transfer system on base of 2 electromagnetic 4151200100014 valves, stainless steel tube of 10 mm diameter, 0.3 mm 4151200100015 wall thickness. Times of sample transportation from 1504151200100016 to 500 msec were defined in test runs. 4151200100017 INC-SOURCE (P-T) T(p,n)He-3 for monoenergetic neutrons of 1.2 MeV.4151200100018 Proton energy 1.974 MeV. 4151200100019 (D-D) D(d,n)He-3 for monoenergetic neutrons from 3.5 to4151200100020 5.MeV. Deuterons energy 0.493, 0.888, 1.283, 1.777 MeV.4151200100021 INC-SPECT Neutron energy distributions calculated my Monte-Carlo 4151200100022 method are presented on Fig.5 and Fig.6 of main 4151200100023 reference. EN-MAX -maximal energy of neutrons generated4151200100024 in neutron production reactions. 4151200100025 METHOD (ACTIV) Periodic radiation in neutron beam of fixed 4151200100026 energy, moving the sample in neutron detector by 4151200100027 pneumatic system, and measuring the time-dependence of 4151200100028 delayed neutron activity. 4151200100029 Two different types of experiment: 4151200100030 -measurement of delayed neutron abundances and periods.4151200100031 -measurement of total delayed neutron yields. 4151200100032 Irradiation time intervals 15, 180, 300 sec. Counting 4151200100033 intervals 424.5 and 724.5 sec. 4151200100034 DETECTOR (FISCH) Two fission chambers with Np-237 or Pu-239 4151200100035 layers. 4151200100036 (D4PI) For delayed neutron registration, thirty SNM-11 4151200100037 boron counters assembly in polyethylene cylinder of 4151200100038 400 mm diameter and 300 mm length.Counters were placed4151200100039 at three circles of 106, 160, 110 mm diameters. 4151200100040 In the center - hole of 36mm diameter to sample flight4151200100041 tube. Boron carbide powder, borated polyethylene, 4151200100042 cadmium sheets - for detector protection. 4151200100043 Absolute efficiency of neutron detector was measured: 4151200100044 1)by activation method based on V-51(p,n)Cr-51reaction4151200100045 2) by measurement of average number of prompt neutrons4151200100046 from Cf-252 spontaneous fission neutrons with surface 4151200100047 barrier detector.Energy dependence of relative 4151200100048 efficiency was determined by Monte-Carlo calculations.4151200100049 Energy dependence of absolute efficiency is presented 4151200100050 on Fig.4 of main reference (about from 8.6 to 7. %). 4151200100051 (LONGC) Long counter. 4151200100052 SAMPLE No information. 4151200100053 ANALYSIS Composite delayed neutron decay curves, value of 4151200100054 fission rates in Np-237 or Pu-239 flux monitors, 4151200100055 number of counts registered by long-counter and 4151200100056 current integrator were analyzed.6-group approximation4151200100057 and iterative least-squares method were used in decay 4151200100058 curve analysis. 4151200100059 CORRECTION For fission events masked by alpha-events and other 4151200100060 low pulse height signals. 4151200100061 ERR-ANALYS (ERR-T) Total uncertainty, includes: 4151200100062 (ERR-1) Uncertainties of delayed neutron abundance and 4151200100063 period values - 1.8 - 2.0 %, 4151200100064 - Error of the sample under investigation and fission 4151200100065 chamber positions relative to neutron target, 4151200100066 - Uncertainties of fission rate calculations, 4151200100067 - Statistical uncertainty. 4151200100068 COMMENT Work was made by support of RFBR grant #05-02-08044 4151200100069 and ISTC #2253. 4151200100070 HISTORY (20080424C) Compiled at CJD. M.M. 4151200100071 (20131129A) Ref. INDC(NDS)-0646 was added. 4151200100072 Subents 003-004 were added. 4151200100073 (20200609U) ref. S,JINR-E3-2007-23,144 was added. 4151200100074 ENDBIB 72 0 4151200100075 COMMON 1 3 4151200100076 ERR-1 4151200100077 PER-CENT 4151200100078 2.0 4151200100079 ENDCOMMON 3 0 4151200100080 ENDSUBENT 79 0 4151200199999 SUBENT 41512002 20200609 41884151200200001 BIB 4 8 4151200200002 REACTION (92-U-236(N,F),DL,NU) 4151200200003 STATUS (APRVD) Prelim.data received from author V.Roschenko - 4151200200004 Fig.7 of S,ISINN-14,144,2006 . 4151200200005 (TABLE) Table on page 27 of INDC(NDS)-0646. 4151200200006 COMMENT Of Author. On Fig.7 of S,ISINN-14,144,200 the data are 4151200200007 presented for maximal energy of neutron spectrum. 4151200200008 HISTORY (20131129A) Prelim.data were replaced by data of newer 4151200200009 publication INDC(NDS)-0646. 4151200200010 ENDBIB 8 0 4151200200011 NOCOMMON 0 0 4151200200012 DATA 4 5 4151200200013 EN EN-ERR DATA ERR-T 4151200200014 MEV MEV PC/FIS PC/FIS 4151200200015 1.01 0.10 2.18 0.22 4151200200016 3.23 0.15 2.33 0.12 4151200200017 3.75 0.14 2.32 0.12 4151200200018 4.20 0.17 2.18 0.11 4151200200019 4.72 0.21 2.20 0.11 4151200200020 ENDDATA 7 0 4151200200021 ENDSUBENT 20 0 4151200299999 SUBENT 41512003 20131129 41624151200300001 BIB 4 12 4151200300002 REACTION ((92-U-236(N,F),DL/GRP,NU)/(92-U-236(N,F),DL,NU)) 4151200300003 Relative abundances of delayed neutrons in 6-groups 4151200300004 model presentation. 4151200300005 ADD-RES Average half-life of delayed neutron precursors: 4151200300006 EN, MeV HL, sec 4151200300007 1.01 +- 0.10 7.93 +- 0.10 4151200300008 3.23 +- 0.15 7.76 +- 0.13 4151200300009 3.75 +- 0.14 7.72 +- 0.11 4151200300010 4.20 +- 0.17 7.58 +- 0.39 4151200300011 4.72 +- 0.21 7.51 +- 0.11 4151200300012 STATUS (TABLE) Table on page 18 of INDC(NDS)-0646. 4151200300013 HISTORY (20131129C) Subent was added. 4151200300014 ENDBIB 12 0 4151200300015 NOCOMMON 0 0 4151200300016 DATA 6 30 4151200300017 EN EN-ERR HL HL-ERR DATA DATA-ERR 4151200300018 MEV MEV SEC SEC NO-DIM NO-DIM 4151200300019 1.01 0.10 54.58 0.37 0.0249 0.0005 4151200300020 1.01 0.10 21.68 0.13 0.214 0.004 4151200300021 1.01 0.10 4.29 0.05 0.337 0.006 4151200300022 1.01 0.10 1.425 0.033 0.314 0.007 4151200300023 1.01 0.10 0.479 0.014 0.098 0.003 4151200300024 1.01 0.10 0.214 0.006 0.0121 0.0004 4151200300025 3.23 0.15 55.43 0.55 0.0246 0.0006 4151200300026 3.23 0.15 22.33 0.22 0.195 0.005 4151200300027 3.23 0.15 4.29 0.07 0.353 0.008 4151200300028 3.23 0.15 1.477 0.045 0.317 0.009 4151200300029 3.23 0.15 0.477 0.017 0.098 0.003 4151200300030 3.23 0.15 0.214 0.008 0.0124 0.0004 4151200300031 3.75 0.14 55.81 0.38 0.0255 0.0006 4151200300032 3.75 0.14 21.92 0.14 0.195 0.004 4151200300033 3.75 0.14 4.50 0.05 0.322 0.006 4151200300034 3.75 0.14 1.495 0.036 0.347 0.008 4151200300035 3.75 0.14 0.484 0.017 0.098 0.003 4151200300036 3.75 0.14 0.214 0.008 0.0125 0.0005 4151200300037 4.20 0.17 56.68 0.70 0.025 0.001 4151200300038 4.20 0.17 21.68 0.29 0.197 0.007 4151200300039 4.20 0.17 4.22 0.10 0.329 0.010 4151200300040 4.20 0.17 1.352 0.056 0.337 0.013 4151200300041 4.20 0.17 0.484 0.024 0.099 0.005 4151200300042 4.20 0.17 0.214 0.011 0.0130 0.0006 4151200300043 4.72 0.21 55.38 0.42 0.0260 0.0006 4151200300044 4.72 0.21 21.60 0.15 0.191 0.004 4151200300045 4.72 0.21 4.32 0.05 0.332 0.006 4151200300046 4.72 0.21 1.404 0.036 0.332 0.008 4151200300047 4.72 0.21 0.456 0.016 0.106 0.004 4151200300048 4.72 0.21 0.215 0.008 0.0130 0.0005 4151200300049 ENDDATA 32 0 4151200300050 ENDSUBENT 49 0 4151200399999 SUBENT 41512004 20131129 41624151200400001 BIB 4 12 4151200400002 REACTION ((92-U-236(N,F),DL/GRP,NU)/(92-U-236(N,F),DL,NU)) 4151200400003 Relative abundances of delayed neutrons in 8-groups 4151200400004 model presentation. 4151200400005 ADD-RES Average half-life of delayed neutron precursors: 4151200400006 EN, MeV HL, sec 4151200400007 1.01 +- 0.10 7.94 +- 0.16 4151200400008 3.23 +- 0.15 7.75 +- 0.15 4151200400009 3.75 +- 0.14 7.72 +- 0.15 4151200400010 4.20 +- 0.17 7.56 +- 0.15 4151200400011 4.72 +- 0.21 7.50 +- 0.15 4151200400012 STATUS (TABLE) Table II of INDC(NDS)-0646 Appendix. 4151200400013 HISTORY (20131129C) Subent was added. 4151200400014 ENDBIB 12 0 4151200400015 NOCOMMON 0 0 4151200400016 DATA 5 40 4151200400017 EN EN-ERR HL DATA ERR-T 4151200400018 MEV MEV SEC NO-DIM NO-DIM 4151200400019 1.01 0.10 55.6 0.0218 0.0009 4151200400020 1.01 0.10 24.3 0.143 0.006 4151200400021 1.01 0.10 16.3 0.079 0.003 4151200400022 1.01 0.10 5.21 0.196 0.007 4151200400023 1.01 0.10 2.37 0.287 0.009 4151200400024 1.01 0.10 1.04 0.200 0.009 4151200400025 1.01 0.10 0.424 0.049 0.002 4151200400026 1.01 0.10 0.195 0.023 0.001 4151200400027 3.23 0.15 55.6 0.0229 0.0009 4151200400028 3.23 0.15 24.3 0.144 0.005 4151200400029 3.23 0.15 16.3 0.055 0.003 4151200400030 3.23 0.15 5.21 0.209 0.007 4151200400031 3.23 0.15 2.37 0.309 0.010 4151200400032 3.23 0.15 1.04 0.185 0.008 4151200400033 3.23 0.15 0.424 0.049 0.002 4151200400034 3.23 0.15 0.195 0.024 0.001 4151200400035 3.75 0.14 55.6 0.0244 0.0009 4151200400036 3.75 0.14 24.3 0.12872 0.005 4151200400037 3.75 0.14 16.3 0.075 0.003 4151200400038 3.75 0.14 5.21 0.201 0.007 4151200400039 3.75 0.14 2.37 0.291 0.009 4151200400040 3.75 0.14 1.04 0.215 0.009 4151200400041 3.75 0.14 0.424 0.042 0.002 4151200400042 3.75 0.14 0.195 0.023 0.001 4151200400043 4.20 0.17 55.6 0.0249 0.0009 4151200400044 4.20 0.17 24.3 0.120 0.005 4151200400045 4.20 0.17 16.3 0.083 0.003 4151200400046 4.20 0.17 5.21 0.175 0.007 4151200400047 4.20 0.17 2.37 0.291 0.009 4151200400048 4.20 0.17 1.04 0.223 0.009 4151200400049 4.20 0.17 0.424 0.058 0.003 4151200400050 4.20 0.17 0.195 0.025 0.001 4151200400051 4.72 0.21 55.6 0.0242 0.0009 4151200400052 4.72 0.21 24.3 0.122 0.005 4151200400053 4.72 0.21 16.3 0.077 0.003 4151200400054 4.72 0.21 5.21 0.191 0.007 4151200400055 4.72 0.21 2.37 0.295 0.009 4151200400056 4.72 0.21 1.04 0.195 0.009 4151200400057 4.72 0.21 0.424 0.080 0.004 4151200400058 4.72 0.21 0.195 0.0173 0.0009 4151200400059 ENDDATA 42 0 4151200400060 ENDSUBENT 59 0 4151200499999 ENDENTRY 4 0 4151299999999