ENTRY 41318 20110604 41534131800000001 SUBENT 41318001 20110604 41534131800100001 BIB 13 43 4131800100002 TITLE Measurement of the ratio of the average Np-237 capture 4131800100003 cross-section to the Pu-239 fission cross-section in 4131800100004 two BFS critical assemblies 4131800100005 AUTHOR (V.A.Dulin) 4131800100006 INSTITUTE (4RUSFEI) 4131800100007 REFERENCE (J,AE,84,(6),541,199806) Main reference, data are given4131800100008 (J,AE/T,84,(6),407,1998) Engl.translation of J,AE,84 . 4131800100009 #doi:10.1007/BF02413902 4131800100010 FACILITY (REAC) Fast critical assembly BFS-1 with different 4131800100011 modifications of reactor core 4131800100012 MONITOR .Absolute measurements 4131800100013 METHOD (ACTIV) 4131800100014 DETECTOR (FISCH) For fission cross-section measurements 4131800100015 (GELI) For n-gamma cs measurements 4131800100016 For calibration - standard sources of absolute activity4131800100017 with 1.2-1.4% uncertainty were used. 4131800100018 Lead layer of 12.1 mm thickness to decrease 4131800100019 gamma-counting rate. 4131800100020 Without Pb - absolute efficiency was defined by Cs-137,4131800100021 Co-60, Eu-152 (779, 964 keV) and was straight line in 4131800100022 double-logarithmic scale. With Pb - efficiency was 4131800100023 almost independent from energy. 4131800100024 DECAY-DATA (93-NP-238,2.118D,DG,984.0,0.278, 4131800100025 DG,1027.0,0.300) 4131800100026 0.278+-0.009; 0.300+-0.008 4131800100027 (94-PU-239,24110.0YR) 4131800100028 SAMPLE .Pu-239 sample as thin film on the fission chamber 4131800100029 electrode, quantity of Pu-239 is (1.954+-.016)E-7 4131800100030 mole, Pu-240 admixture is 0.13+-0.03 % 4131800100031 .Np sample as oxide disk of Np-O2, Diameter 7 mm,mass 4131800100032 24-30 milligram. 4131800100033 ERR-ANALYS (ERR-T) Total error. 4131800100034 (ERR-S,0.4,0.7) Statistical uncertainty of detector 4131800100035 efficiency measurement. 4131800100036 (ERR-1) Uncertainty of Np-238 gamma lines absolute 4131800100037 efficiency measurement. 4131800100038 CORRECTION For neutron self-absorption in samples. 4131800100039 HISTORY (19990111C) + + Compiled at the CJD + + 4131800100040 (20110704A) M.M. Upper -> lower case correction. 4131800100041 Ref.J,AE/T was added. 4131800100042 Authors' names I.V.Mikhaylov,A.M.Tsibulya were deleted4131800100043 as not given in the article. 4131800100044 BIB information was added. 4131800100045 ENDBIB 43 0 4131800100046 COMMON 1 3 4131800100047 ERR-1 4131800100048 PER-CENT 4131800100049 2. 4131800100050 ENDCOMMON 3 0 4131800100051 ENDSUBENT 50 0 4131800199999 SUBENT 41318002 20110604 41534131800200001 BIB 4 19 4131800200002 REACTION 1((93-NP-237(N,G)93-NP-238,,SIG,,SPA)/ 4131800200003 (94-PU-239(N,F),,SIG,,SPA)) averaged over broad 4131800200004 neutron spectrum of BFS 71-2. 4131800200005 2((93-NP-237(N,G)93-NP-238,,SIG,,SPA)/ 4131800200006 (94-PU-239(N,F),,SIG,,SPA)) Averaged over broad 4131800200007 neutron spectrum of BFS 73-1 4131800200008 3((93-NP-237(N,G)93-NP-238,,SIG,,SPA)/ 4131800200009 (94-PU-239(N,F),,SIG,,SPA)) Averaged over broad 4131800200010 neutron spectrum of BFS 73-1 4131800200011 ANALYSIS 1.Reactor with oxide core, relative measurements, 4131800200012 BNAB thermal constants were used. 4131800200013 2.Reactor with metallic core and sodium heat-transfer 4131800200014 agent, relative measurements, 4131800200015 BNAB thermal constants were used. 4131800200016 Defined as (0.546*0.214)/0.207=0.563 . 4131800200017 3.Reactor with metallic core and sodium heat-transfer 4131800200018 agent, absolute measurements 4131800200019 INC-SPECT .Neutron spectrum of the fast reactor's active core 4131800200020 STATUS (TABLE) Table 5 of J,AE,84,(6),541,1998. 4131800200021 ENDBIB 19 0 4131800200022 COMMON 1 3 4131800200023 EN-DUMMY 4131800200024 EV 4131800200025 1.000E+06 4131800200026 ENDCOMMON 3 0 4131800200027 DATA 6 1 4131800200028 DATA 1ERR-T 1DATA 2ERR-T 2DATA 3ERR-T 34131800200029 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 4131800200030 0.584 0.19 0.563 0.018 0.546 0.025 4131800200031 ENDDATA 3 0 4131800200032 ENDSUBENT 31 0 4131800299999 SUBENT 41318003 20110604 41534131800300001 BIB 3 5 4131800300002 REACTION ((93-NP-237(N,G)93-NP-238,,SIG,,MXW)/ 4131800300003 (94-PU-239(N,F),,SIG,,MXW)) Averaged thermal 4131800300004 neutron spectrum of BFS 73-1, thermal column. 4131800300005 INC-SPECT .Thermal column of the fast reactor 4131800300006 STATUS (TABLE) Table 4 of J,AE,84,(6),541,1998. 4131800300007 ENDBIB 5 0 4131800300008 NOCOMMON 0 0 4131800300009 DATA 3 1 4131800300010 EN-DUMMY DATA ERR-T 4131800300011 EV NO-DIM NO-DIM 4131800300012 2.5300E-02 0.207 0.010 4131800300013 ENDDATA 3 0 4131800300014 ENDSUBENT 13 0 4131800399999 ENDENTRY 3 0 4131899999999