ENTRY 41566 20131130 41624156600000001 SUBENT 41566001 20131130 41624156600100001 BIB 12 44 4156600100002 TITLE Total delayed neutron yield from 232Th fission by 4156600100003 3.2-4.9 MeV neutrons. 4156600100004 AUTHOR (V.M.Piksaikin, A.S.Egorov, K.V.Mitrofanov, 4156600100005 A.A.Goverdovski) 4156600100006 INSTITUTE (4RUSFEI) V.M.Piksaikin alias V.M.Piksaykin . 4156600100007 REFERENCE (J,AE,112,(6),350,2012) 4156600100008 (J,AE/T,112,(6),428,2012) Engl.translation of J,AE. 4156600100009 #doi:10.1007/s10512-012-9579-5 4156600100010 (R,INDC(NDS)-0646,2013) In English. 4156600100011 FACILITY (VDG,4RUSFEI) Cascade generator CG-2.5 4156600100012 Pneumatic sample transfer system. 4156600100013 INC-SOURCE (D-D) 4156600100014 INC-SPECT Mono-energetic neutrons. 4156600100015 DETECTOR (FISCH) Np-237 fission chamber - for neutron beam 4156600100016 monitoring. 4156600100017 (D4PI) 4pi detector for delayed neutrons registration-4156600100018 (PROPC) consisted of thirty B-10 proportional counters4156600100019 SNM-11 in polyethylene. Protected by boron carbide, 4156600100020 borated polyethylene, cadmium . 4156600100021 Neutron registration dead time 2.3+- 0.2 microsec. 4156600100022 Standard Am(Li) and Pu(Li) sources were used to 4156600100023 monitor stability of detector . 4156600100024 Energy dependence of neutron detector was calculated 4156600100025 by Monte-Carlo method and absolute normalization by 4156600100026 data of detector efficiency measured via V-51(p,n)Cr-514156600100027 reaction and Cf-252 spontaneous fission source. 4156600100028 METHOD (ACTIV) The irradiation time intervals were 15,180 and 4156600100029 300 s. Depending on background conditions the delayed 4156600100030 neutron counting intervals were 424.5 and 724.5 s with 4156600100031 the time channel sequence after the end of sample 4156600100032 irradiation: 0.01s (150 channels), 0.02s (150 channels)4156600100033 , 0.1 s (200 channels), 1 s (200 channels) and 10 s (304156600100034 or 50 channels). 4156600100035 The times of sample transportation from the irradiation4156600100036 position to the neutron detector were from 150 to 200ms4156600100037 depending on gas pressure and the weight of samples. 4156600100038 SAMPLE No information. 4156600100039 CORRECTION For backgrounds: 4156600100040 Counting interval, s 724.5 224.5 4156600100041 Relative background, % 1.10-1.84 0.35-0.58 4156600100042 Intensity of background,n/s 0.16 4156600100043 HISTORY (20121018C) Compiled at CJD. M.M. 4156600100044 (20131130A) Ref. INDC(NDS)-0646 was added. 4156600100045 Subents 003-004 were added. 4156600100046 ENDBIB 44 0 4156600100047 NOCOMMON 0 0 4156600100048 ENDSUBENT 47 0 4156600199999 SUBENT 41566002 20131130 41624156600200001 BIB 4 5 4156600200002 REACTION (90-TH-232(N,F),DL,NU) 4156600200003 SAMPLE No information. 4156600200004 ERR-ANALYS (DATA-ERR) Errors are not specified 4156600200005 STATUS (TABLE) Table of J,AE,112,(6),350,2012. 4156600200006 Table on page 25 of R,INDC(NDS)-0646,2013 4156600200007 ENDBIB 5 0 4156600200008 NOCOMMON 0 0 4156600200009 DATA 3 6 4156600200010 EN DATA DATA-ERR 4156600200011 MEV PRT/FIS PRT/FIS 4156600200012 3.2 0.0579 0.0023 4156600200013 3.8 0.0572 0.0024 4156600200014 4.2 0.0550 0.0042 4156600200015 4.5 0.0557 0.0063 4156600200016 4.7 0.0543 0.0031 4156600200017 4.9 0.0568 0.0032 4156600200018 ENDDATA 8 0 4156600200019 ENDSUBENT 18 0 4156600299999 SUBENT 41566003 20131130 41624156600300001 BIB 5 15 4156600300002 REACTION ((90-TH-232(N,F),DL/GRP,NU)/(90-TH-232(N,F),DL,NU)) 4156600300003 Relative abundances of delayed neutrons in 6-groups 4156600300004 model presentation. 4156600300005 SAMPLE No information. 4156600300006 ADD-RES Average half-life of delayed neutron precursors: 4156600300007 EN, MeV HL, sec 4156600300008 3.2 6.66+-0.12 4156600300009 3.8 6.78+-0.06 4156600300010 4.2 6.73+-0.06 4156600300011 4.5 6.57+-0.08 4156600300012 4.7 6.63+-0.07 4156600300013 4.9 6.65+-0.09 4156600300014 5.1 6.51+-0.11 4156600300015 ERR-ANALYS (DATA-ERR) Errors are not specified 4156600300016 STATUS (TABLE) Table on page 14 of R,INDC(NDS)-0646,2013 . 4156600300017 ENDBIB 15 0 4156600300018 NOCOMMON 0 0 4156600300019 DATA 6 42 4156600300020 EN EN-ERR HL HL-ERR DATA DATA-ERR 4156600300021 MEV MEV SEC SEC NO-DIM NO-DIM 4156600300022 3.2 0.2 55.24 0.64 0.0309 0.0011 4156600300023 3.2 0.2 21.05 0.34 0.145 0.005 4156600300024 3.2 0.2 5.51 0.16 0.147 0.007 4156600300025 3.2 0.2 2.161 0.053 0.459 0.011 4156600300026 3.2 0.2 0.547 0.027 0.178 0.009 4156600300027 3.2 0.2 0.2155 0.0108 0.0399 0.0020 4156600300028 3.8 0.1 55.19 0.27 0.0310 0.0005 4156600300029 3.8 0.1 20.63 0.14 0.149 0.002 4156600300030 3.8 0.1 5.81 0.07 0.151 0.003 4156600300031 3.8 0.1 2.211 0.022 0.456 0.005 4156600300032 3.8 0.1 0.592 0.011 0.174 0.003 4156600300033 3.8 0.1 0.2143 0.0043 0.0393 0.0008 4156600300034 4.2 0.2 54.22 0.27 0.0307 0.0005 4156600300035 4.2 0.2 20.86 0.15 0.145 0.002 4156600300036 4.2 0.2 5.952 0.068 0.153 0.003 4156600300037 4.2 0.2 2.218 0.022 0.457 0.005 4156600300038 4.2 0.2 0.598 0.011 0.175 0.003 4156600300039 4.2 0.2 0.215 0.004 0.0399 0.0008 4156600300040 4.5 0.2 53.77 0.34 0.0323 0.0006 4156600300041 4.5 0.2 20.29 0.19 0.144 0.003 4156600300042 4.5 0.2 5.539 0.093 0.149 0.003 4156600300043 4.5 0.2 2.085 0.030 0.466 0.006 4156600300044 4.5 0.2 0.582 0.014 0.167 0.004 4156600300045 4.5 0.2 0.213 0.005 0.0409 0.0010 4156600300046 4.7 0.2 54.29 0.30 0.0318 0.0005 4156600300047 4.7 0.2 20.46 0.16 0.145 0.003 4156600300048 4.7 0.2 5.53 0.07 0.157 0.003 4156600300049 4.7 0.2 2.07 0.02 0.460 0.005 4156600300050 4.7 0.2 0.58308 0.01231 0.163 0.004 4156600300051 4.7 0.2 0.213 0.005 0.0418 0.0009 4156600300052 4.9 0.2 54.07 0.38 0.0327 0.0007 4156600300053 4.9 0.2 19.95 0.19 0.149 0.003 4156600300054 4.9 0.2 5.49 0.09 0.147 0.004 4156600300055 4.9 0.2 2.09 0.03 0.471 0.007 4156600300056 4.9 0.2 0.566 0.016 0.158 0.005 4156600300057 4.9 0.2 0.213 0.006 0.0411 0.0012 4156600300058 5.1 0.2 53.86 0.53 0.0319 0.0011 4156600300059 5.1 0.2 20.26 0.31 0.141 0.005 4156600300060 5.1 0.2 5.62 0.13 0.159 0.007 4156600300061 5.1 0.2 2.10 0.05 0.446 0.009 4156600300062 5.1 0.2 0.559 0.027 0.181 0.008 4156600300063 5.1 0.2 0.214 0.011 0.0413 0.0021 4156600300064 ENDDATA 44 0 4156600300065 ENDSUBENT 64 0 4156600399999 SUBENT 41566004 20131130 41624156600400001 BIB 5 15 4156600400002 REACTION ((90-TH-232(N,F),DL/GRP,NU)/(90-TH-232(N,F),DL,NU)) 4156600400003 Relative abundances of delayed neutrons in 8-groups 4156600400004 model presentation. 4156600400005 SAMPLE No information. 4156600400006 ADD-RES Average half-life of delayed neutron precursors: 4156600400007 EN, MeV HL, sec 4156600400008 3.2 6.65+-0.12 4156600400009 3.8 6.77+-0.12 4156600400010 4.2 6.72+-0.12 4156600400011 4.5 6.58+-0.12 4156600400012 4.7 6.64+-0.12 4156600400013 4.9 6.66+-0.12 4156600400014 5.1 6.44+-0.14 4156600400015 ERR-ANALYS (DATA-ERR) Errors are not specified 4156600400016 STATUS (TABLE) Table IV of R,INDC(NDS)-0646,2013 Appendix. 4156600400017 ENDBIB 15 0 4156600400018 NOCOMMON 0 0 4156600400019 DATA 5 56 4156600400020 EN EN-ERR HL DATA DATA-ERR 4156600400021 MEV MEV SEC NO-DIM NO-DIM 4156600400022 3.2 0.2 55.6 0.029 0.001 4156600400023 3.2 0.2 24.5 0.078 0.003 4156600400024 3.2 0.2 16.3 0.081 0.003 4156600400025 3.2 0.2 5.21 0.121 0.005 4156600400026 3.2 0.2 2.37 0.406 0.010 4156600400027 3.2 0.2 1.04 0.133 0.006 4156600400028 3.2 0.2 0.424 0.115 0.005 4156600400029 3.2 0.2 0.195 0.036 0.002 4156600400030 3.8 0.1 55.6 0.029 0.001 4156600400031 3.8 0.1 24.5 0.713 0.003 4156600400032 3.8 0.1 16.3 0.095 0.003 4156600400033 3.8 0.1 5.21 0.136 0.006 4156600400034 3.8 0.1 2.37 0.394 0.010 4156600400035 3.8 0.1 1.04 0.142 0.007 4156600400036 3.8 0.1 0.424 0.099 0.005 4156600400037 3.8 0.1 0.195 0.033 0.001 4156600400038 4.2 0.2 55.6 0.027 0.001 4156600400039 4.2 0.2 24.5 0.079 0.003 4156600400040 4.2 0.2 16.3 0.085 0.003 4156600400041 4.2 0.2 5.21 0.148 0.006 4156600400042 4.2 0.2 2.37 0.382 0.010 4156600400043 4.2 0.2 1.04 0.150 0.007 4156600400044 4.2 0.2 0.424 0.097 0.004 4156600400045 4.2 0.2 0.195 0.032 0.001 4156600400046 4.5 0.2 55.6 0.028 0.001 4156600400047 4.5 0.2 24.5 0.073 0.003 4156600400048 4.5 0.2 16.3 0.087 0.003 4156600400049 4.5 0.2 5.21 0.123 0.005 4156600400050 4.5 0.2 2.37 0.390 0.010 4156600400051 4.5 0.2 1.04 0.177 0.008 4156600400052 4.5 0.2 0.424 0.090 0.004 4156600400053 4.5 0.2 0.195 0.031 0.001 4156600400054 4.7 0.2 55.6 0.029 0.001 4156600400055 4.7 0.2 24.5 0.073 0.003 4156600400056 4.7 0.2 16.3 0.089 0.003 4156600400057 4.7 0.2 5.21 0.128 0.005 4156600400058 4.7 0.2 2.37 0.384 0.010 4156600400059 4.7 0.2 1.04 0.178 0.008 4156600400060 4.7 0.2 0.424 0.087 0.004 4156600400061 4.7 0.2 0.195 0.031 0.001 4156600400062 4.9 0.2 55.6 0.029 0.001 4156600400063 4.9 0.2 24.5 0.068 0.003 4156600400064 4.9 0.2 16.3 0.098 0.003 4156600400065 4.9 0.2 5.21 0.118 0.005 4156600400066 4.9 0.2 2.37 0.404 0.010 4156600400067 4.9 0.2 1.04 0.161 0.007 4156600400068 4.9 0.2 0.424 0.089 0.004 4156600400069 4.9 0.2 0.195 0.033 0.001 4156600400070 5.1 0.2 55.6 0.028 0.001 4156600400071 5.1 0.2 24.5 0.070 0.002 4156600400072 5.1 0.2 16.3 0.084 0.002 4156600400073 5.1 0.2 5.21 0.143 0.003 4156600400074 5.1 0.2 2.37 0.354 0.005 4156600400075 5.1 0.2 1.04 0.169 0.004 4156600400076 5.1 0.2 0.424 0.115 0.003 4156600400077 5.1 0.2 0.195 0.038 0.001 4156600400078 ENDDATA 58 0 4156600400079 ENDSUBENT 78 0 4156600499999 ENDENTRY 4 0 4156699999999