ENTRY 22843 20161111 22552284300000001 SUBENT 22843001 20161111 22552284300100001 BIB 14 64 2284300100002 TITLE Measurement of the effective capture cross section 2284300100003 of 238Np for thermal neutrons 2284300100004 AUTHOR (H.Harada, S.Nakamura, T.Fujii, H.Yamana) 2284300100005 INSTITUTE (2JPNJAE) Harada, Nakamura 2284300100006 (2JPNKTO) Fujii, Yamana 2284300100007 REFERENCE (J,NST,41,(1),1,200401) Main reference, data given 2284300100008 (S,JAERI-C-2005-03,121,2005) 2284300100009 REL-REF (O,22872001,H.Harada+,S,JAERI-C-2005-03,121,2005) 2284300100010 Data for Np-237 measured by TOF method. 2284300100011 (O,22872001,H.Harada+,S,JAERI-C-2005-03,121,2005) 2284300100012 Data for Np-237 measured by gamma-spectroscopy . 2284300100013 FACILITY (REAC,2JPNKTO) Thermal neutron flux research reactor 2284300100014 at the Kyoto University 2284300100015 DETECTOR (HPGE) High purity n-type germanium detector with BGO. 2284300100016 (Bi4-Ge3-O12 ) detector to measure a weak gamma rays 2284300100017 from 239-Np 2284300100018 .The peak detector efficiency was 90% at 1.33 MeV gamma2284300100019 energy relative to a 7.6 cm diameter 7.6 cm long Na-I 2284300100020 detector 2284300100021 SAMPLE .Sample of Np-238 was obtained by a double irradiation 2284300100022 of 237Np sample through 237Np(N,gamma)238Np(N,g)239Np 2284300100023 mixture containing 238Np was welded in the tube 8 mm 2284300100024 outer diam, 25 mm length 2284300100025 .Gold sample is Au-Al wire alloy, Au 0.112 wt%, 0.51 mm2284300100026 diameter 2284300100027 .Cobalt sample is Co-Al wire alloy, Co 0.46 wt%, 2284300100028 0.381 mm diameter 2284300100029 METHOD (ACTIV,GSPEC) 2284300100030 (SITA) Single target irradiation 2284300100031 MONITOR ((MONIT1)79-AU-197(N,G)79-AU-198,,SIG) 2284300100032 ((MONIT2)27-CO-59(N,G)27-CO-60,,SIG) 2284300100033 DECAY-MON (79-AU-198-G,2.695D,DG,412.,0.9558) 2284300100034 Self-absorption coefficient 0.995 2284300100035 (27-CO-60-G,5.271YR,DG,1173.,0.9985, 2284300100036 DG,1333.,0.999826) 2284300100037 Self-absorption coefficient 0.998 for both gamma-lines.2284300100038 ANALYSIS Using the data on both SIG-0 and S0 for Co and Au and 2284300100039 the results of reaction rates R for Co and Au, the 2284300100040 values of flux and r*sqrt(T/T0) at the irradiation 2284300100041 position were determined. 2284300100042 Formulas used: 2284300100043 SIG-eff=SIG-0*(1+r*sqrt(T=T0)*S0), 2284300100044 S0=(2/sqrt(PI))*(I0r/SIG-0), 2284300100045 I0r=I0 - 0.45*SIG-0 , 2284300100046 where SIG-0 - CS at thermal point, see MONITOR 2284300100047 I0 - resonance integral. 2284300100048 Co-59 - S0=37.18+-0.06, Au-198 - S0=17.22+-0.32 were 2284300100049 obtained. 2284300100050 ERR-ANALYS (ERR-T) Total error 2284300100051 (ERR-S) Statistical 2284300100052 (ERR-1) Error in the gamma ray detection efficiency 2284300100053 resulting from the ambiguity of the calibratio2284300100054 source intensity 2284300100055 (ERR-2) Error in the measurement of the induced 2284300100056 activity 2284300100057 (ERR-3) Error in the measurement of the neutron flux 2284300100058 (ERR-HL) Error resulting from the errors of the 2284300100059 half-lives of 238Np and 239Np 2284300100060 HISTORY (20040805C) JOS 2284300100061 (20040805U) Monitor codes corrected, EN-NRM added-SM 2284300100062 (20161111A) M.M. Ref. S,JAERI-C-2005-03,121,2005 was 2284300100063 added. BIB information was updated. 2284300100064 ANALYSIS, STATUS were added. 2284300100065 ERR-HL -> HL-ERR . 2284300100066 ENDBIB 64 0 2284300100067 COMMON 10 6 2284300100068 EN-NRM ERR-S ERR-1 ERR-2 ERR-3 HL-ERR 2284300100069 MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 2284300100070 EV PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2284300100071 B B B B 2284300100072 2.53E-02 3.8 2.4 1.1 2.0 0.12284300100073 98.65 0.09 37.18 0.06 2284300100074 ENDCOMMON 6 0 2284300100075 ENDSUBENT 74 0 2284300199999 SUBENT 22843002 20161111 22552284300200001 BIB 5 12 2284300200002 REACTION (93-NP-238(N,G)93-NP-239,,SIG,,MXW) 2284300200003 INC-SPECT Thermal neutron spectrum, mean energy supposed 2284300200004 0.0253 eV . Epithermal index r*sqrt(T/T0)=0.03+-0.001.2284300200005 Neutron flux (1.01+-0.01)*10**14 n/(cm2*s). 2284300200006 DECAY-DATA (93-NP-238,2.117D,DG,984.5,0.2519) 2284300200007 HL=2.117+-0.002 d , intensity 25.19+-0.21 % 2284300200008 (93-NP-239,2.3565D,DG,277.6,0.1444) 2284300200009 HL=2.3565+-0.0004 d , intensity 14.44+-0.10 % 2284300200010 ASSUMED (ASSUM,93-NP-239(N,G)93-NP-240,,SIG) 2284300200011 SIG-O for Np-239 at thermal point 2284300200012 STATUS (TABLE) Table 3 of J,NST,41,(1),1,2004 2284300200013 Text, page 123, of S,JAERI-C-2005-03,121,2005 2284300200014 ENDBIB 12 0 2284300200015 NOCOMMON 0 0 2284300200016 DATA 4 1 2284300200017 EN-DUMMY DATA ERR-T ASSUM 2284300200018 EV B B B 2284300200019 0.0253 479. 24. 37.0 2284300200020 ENDDATA 3 0 2284300200021 ENDSUBENT 20 0 2284300299999 ENDENTRY 2 0 2284399999999