ENTRY 41300 20210414 41954130000000001 SUBENT 41300001 20210414 41954130000100001 BIB 12 46 4130000100002 TITLE Measurements of the energy dependence of the relative 4130000100003 delayed neutron yields related to individual 4130000100004 precursors from neutron-induced fission of 237Np 4130000100005 AUTHOR (S.G.Isaev,V.M.Piksaykin,L.E.Kazakov,M.Z.Tarasko) 4130000100006 INSTITUTE (4RUSFEI) 4130000100007 REFERENCE (J,YK,,(1),17,1998) Main reference,data are given. 4130000100008 In English. 4130000100009 FACILITY (VDG) Electrostatic accelerator KG-2.5 4130000100010 DETECTOR (D4PI) Boron counter SNM-11 as assemblage of 4130000100011 30 counters distributed in polyethylene moderator - 4130000100012 for neutron detection. Energy dependence of detector 4130000100013 efficiency is calculated by Monte-Carlo method 4130000100014 (SOLST) Semiconductor surface-barrier detector for 4130000100015 Cf-252 fission events detection 4130000100016 (FISCH) Fission chamber for Np-237 fission events 4130000100017 detection 4130000100018 (PROPC) He-3 counter for neutron flux monitoring 4130000100019 INC-SOURCE (P-T) 4130000100020 (D-D) 4130000100021 MONITOR (98-CF-252(0,F),PR,NU) 4130000100022 (92-U-235(N,F),DL,NU) 4130000100023 METHOD (ACTIV) Cyclic irradiation and measurement 4130000100024 ERR-ANALYS (ERR-T) Total error 4130000100025 (ERR-S) Error due to fission counting statistics of 4130000100026 Np-237 4130000100027 (ERR-1) Error due to fission chamber deposit mass of 4130000100028 Np-237 4130000100029 (ERR-2) Error due to extrapolation to zero bias for 4130000100030 Np-237 4130000100031 (ERR-3) Error due to sample mass of Np-237 4130000100032 (ERR-4) Error due to delayed neutron counting 4130000100033 statistical error for Np 4130000100034 (ERR-5) Error due to background (two chamber geometry 4130000100035 for Np-237 4130000100036 (ERR-6) Statistical error caused by delayed neutrons 4130000100037 counts to fission fragments counts ratio 4130000100038 COMMENT This work was made under RFBR research grant 4130000100039 #96-02-17439. 4130000100040 HISTORY (19980925C) + + Compiled at the CJD + + 4130000100041 (19990319A) * * Corrected at CJD. 4130000100042 4-digit dates introduced 4130000100043 (20140721A) M.M. Upper -> lower case correction. 4130000100044 BIB information was updated. 4130000100045 Correction according to memo CP-D/777. 4130000100046 (20191112U) Ref. YK was corrected. 4130000100047 (20210414A) REACTION in Subent 002 was corrected 4130000100048 ENDBIB 46 0 4130000100049 COMMON 8 6 4130000100050 E-LVL ERR-S ERR-1 ERR-2 ERR-3 ERR-4 4130000100051 ERR-5 ERR-6 4130000100052 EV PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4130000100053 PER-CENT PER-CENT 4130000100054 0. 0.01 0.7 0.6 0.05 0.01 4130000100055 0.1 0.6 4130000100056 ENDCOMMON 6 0 4130000100057 ENDSUBENT 56 0 4130000199999 SUBENT 41300002 20210414 41954130000200001 BIB 6 43 4130000200002 REACTION ((93-NP-237(N,F),DL/GRP,NU)/ 4130000200003 (93-NP-237(N,F),DL,NU)) Relative 4130000200004 delayed neutrons yield from 8 individual precursors 4130000200005 and 4 groups of precursors. 4130000200006 SAMPLE NpO(2) oxide powder, density 7 g/cm3, packed in 4130000200007 stainless-steel capsule placed in titanium container. 4130000200008 Sample weight is 2.2810 gram 4130000200009 DECAY-DATA Individual precursors: 4130000200010 (35-BR-87,55.69SEC) 4130000200011 (35-BR-88,16.3SEC) 4130000200012 (35-BR-89,4.38SEC) 4130000200013 (35-BR-91,0.542SEC) 4130000200014 (36-KR-93,1.289SEC) 4130000200015 (37-RB-94,2.76SEC) 4130000200016 (37-RB-95,0.384SEC) 4130000200017 (53-I-137,24.5SEC) 4130000200018 Precursors combined in groups with effective HL: 4130000200019 6.37SEC : 4130000200020 (53-I-138,6.46SEC) 4130000200021 (37-RB-93,5.93SEC) 4130000200022 2.09SEC : 4130000200023 (53-I-139,2.3SEC) 4130000200024 (33-AS-85,2.08SEC) 4130000200025 (39-Y-98-M,2.0SEC) 4130000200026 0.195SEC : 4130000200027 (37-RB-96,0.203SEC) 4130000200028 (37-RB-97,0.17SEC) 4130000200029 0.942SEC : 4130000200030 (55-CS-144,1.002SEC) 4130000200031 (53-I-140,0.86SEC) 4130000200032 ERR-ANALYS (EN-ERR) Standard deviations in incident neutron energy4130000200033 STATUS (TABLE) Data from Table 2 of YK,,(1),17,1998 4130000200034 (COREL,41322002) 6-group data 4130000200035 HISTORY (19990319A) Reaction coding changed 4130000200036 (20140721A) GRP code was deleted from SF5 of REACTION 4130000200037 according to comment of N.Otsuka (NDS,IAEA). 4130000200038 HALF-LIFE values were moved in DECAY-DATA. 4130000200039 (20191112U) IND was added in reaction denominator 4130000200040 (20210414A) REACTION was corrected: 4130000200041 )ELEM/MASS,DL,NU) -> ),DL/GRP,NU)( first term); 4130000200042 DL/IND -> DL (second term). 4130000200043 ELEMENT, MASS, ISOMER were deleted from DATA block, 4130000200044 they are given in DECAY-DATA for specified half-life. 4130000200045 ENDBIB 43 0 4130000200046 NOCOMMON 0 0 4130000200047 DATA 5 60 4130000200048 EN EN-ERR HL DATA ERR-T 4130000200049 MEV MEV SEC NO-DIM NO-DIM 4130000200050 0.586 0.078 0.195 0.022 0.004 4130000200051 0.586 0.078 0.384 0.073 0.017 4130000200052 0.586 0.078 0.542 0.018 0.003 4130000200053 0.586 0.078 0.942 0.013 0.002 4130000200054 0.586 0.078 1.289 0.0044 0.0008 4130000200055 0.586 0.078 2.09 0.257 0.012 4130000200056 0.586 0.078 2.76 0.129 0.012 4130000200057 0.586 0.078 4.38 0.090 0.007 4130000200058 0.586 0.078 6.37 0.075 0.004 4130000200059 0.586 0.078 16.3 0.105 0.005 4130000200060 0.586 0.078 24.5 0.185 0.006 4130000200061 0.586 0.078 55.69 0.030 0.001 4130000200062 1.008 0.099 0.195 0.023 0.004 4130000200063 1.008 0.099 0.384 0.077 0.017 4130000200064 1.008 0.099 0.542 0.019 0.004 4130000200065 1.008 0.099 0.942 0.013 0.002 4130000200066 1.008 0.099 1.289 0.0046 0.0008 4130000200067 1.008 0.099 2.09 0.257 0.011 4130000200068 1.008 0.099 2.76 0.129 0.012 4130000200069 1.008 0.099 4.38 0.092 0.007 4130000200070 1.008 0.099 6.37 0.079 0.003 4130000200071 1.008 0.099 16.3 0.101 0.005 4130000200072 1.008 0.099 24.5 0.176 0.005 4130000200073 1.008 0.099 55.69 0.031 0.001 4130000200074 3.745 0.144 0.195 0.026 0.005 4130000200075 3.745 0.144 0.384 0.091 0.020 4130000200076 3.745 0.144 0.542 0.021 0.004 4130000200077 3.745 0.144 0.942 0.015 0.003 4130000200078 3.745 0.144 1.289 0.0052 0.0009 4130000200079 3.745 0.144 2.09 0.261 0.011 4130000200080 3.745 0.144 2.76 0.130 0.012 4130000200081 3.745 0.144 4.38 0.094 0.007 4130000200082 3.745 0.144 6.37 0.083 0.003 4130000200083 3.745 0.144 16.3 0.085 0.004 4130000200084 3.745 0.144 24.5 0.153 0.005 4130000200085 3.745 0.144 55.69 0.035 0.001 4130000200086 4.196 0.169 0.195 0.029 0.005 4130000200087 4.196 0.169 0.384 0.088 0.020 4130000200088 4.196 0.169 0.542 0.024 0.005 4130000200089 4.196 0.169 0.942 0.017 0.003 4130000200090 4.196 0.169 1.289 0.0059 0.0011 4130000200091 4.196 0.169 2.09 0.254 0.011 4130000200092 4.196 0.169 2.76 0.140 0.013 4130000200093 4.196 0.169 4.38 0.095 0.007 4130000200094 4.196 0.169 6.37 0.070 0.003 4130000200095 4.196 0.169 16.3 0.112 0.005 4130000200096 4.196 0.169 24.5 0.126 0.004 4130000200097 4.196 0.169 55.69 0.040 0.001 4130000200098 4.719 0.205 0.195 0.027 0.005 4130000200099 4.719 0.205 0.384 0.088 0.020 4130000200100 4.719 0.205 0.542 0.022 0.004 4130000200101 4.719 0.205 0.942 0.015 0.003 4130000200102 4.719 0.205 1.289 0.0054 0.000 4130000200103 4.719 0.205 2.09 0.259 0.011 4130000200104 4.719 0.205 2.76 0.136 0.012 4130000200105 4.719 0.205 4.38 0.098 0.007 4130000200106 4.719 0.205 6.37 0.083 0.003 4130000200107 4.719 0.205 16.3 0.088 0.005 4130000200108 4.719 0.205 24.5 0.141 0.005 4130000200109 4.719 0.205 55.69 0.037 0.001 4130000200110 ENDDATA 62 0 4130000200111 ENDSUBENT 110 0 4130000299999 ENDENTRY 2 0 4130099999999