ENTRY 21582 20120120 Y0082158200000001 SUBENT 21582001 20120120 Y0082158200100001 BIB 19 71 2158200100002 INSTITUTE (2JPNJAE) 2158200100003 REFERENCE (J,NST,16,(8),546,197908) 2158200100004 AUTHOR (K.Nishimura, S.Ogawa, T.Tsutiya) 2158200100005 TITLE -Reactor neutron capture cross section of 60.3 2158200100006 day Sb-124.- 2158200100007 FACILITY (REAC,2JPNJAE) Reactor JRR-3. 2158200100008 INC-SOURCE (REAC ) Reactor neutrons. 2158200100009 INC-SPECT -Thermal Maxwellian neutron spectrum from 2158200100010 reactor 6.E+12 n/cm**2/sec (nominal). 2158200100011 Thermal neutron flux obtained by Co was 2158200100012 (4.92+-0.38)*10**12 n/cm**2/sec at sample position. 2158200100013 SAMPLE - 1.2 cm diameter, 4 cm long, encapsulated tightly in 2158200100014 an Al case. After cooling,for counting the sample was 2158200100015 shaped to a size of about 1 mm diam and thickness. 2158200100016 The weight was 2.02 mg. 2158200100017 Cobalt impurity included in antimony sample. 2158200100018 METHOD (ACTIV) 283.5 h irradiation of natural Sb, followed 2158200100019 by 3.50 years cooling time. The ratio of the 2158200100020 Sb-124 and Sb-125 decay gamma activities 2158200100021 gives the necessary information to obtain the 2158200100022 (N,G) cross section of Sb-124 from other data. 2158200100023 (GSPEC) Gamma-ray spectrum measurement during 2158200100024 259.732 sec (about 3 days). 2158200100025 DETECTOR (GELI ) 50 cc coaxial Ge(Li)-detector at 5 cm from 2158200100026 sample surface. For gamma-ray spectrum measurement 2158200100027 MONITOR (27-CO-59(N,G)27-CO-60,,SIG,,MXW) 2158200100028 MONIT-REF ((MONIT),S.F.Mughabghab+,R,BNL-325,1973) 2158200100029 ASSUMED (ASSUM1,51-SB-125(N,G)51-SB-126,,SIG,,MXW) Average 2158200100030 value of theoretically estimated values 0.97b and 10.b2158200100031 reported in P,AAEC/TM-619,1972 and R,AECL-3037,1969 . 2158200100032 (ASSUM2,51-SB-123(N,G)51-SB-124,,SIG,,MXW/AV) 2158200100033 PART-DET (DG ) Decay gammas. 2158200100034 STATUS -Text, NST,16,8,546. 2158200100035 REL-REF (A,,R.L.Auble,J,NDS,7,465,1972) 2158200100036 (A,,F.E.Bertrand,J,NDS,10,91,1973) 2158200100037 References for decay data of Sb-125, Sb-124. 2158200100038 Half-lives from the Chart of the Nuclides, 2158200100039 Y.Yoshizawa+, 1977, JAERI. 2158200100040 (A,,E.Clayton,P,AAEC/TM-619,1972) Reference for ASSUM1.2158200100041 (A,,W.H.Walker,R,AECL-3037,1969) Reference for ASSUM1. 2158200100042 (A,,S.F.Mughabghab+,R,BNL-325,1973) 3-rd ed. 2158200100043 ERR-ANALYS Uncertainty in the cross section estimated from : 2158200100044 (ERR-1) Error in the activity ratio 7.5 %, 2158200100045 (ERR-2) Error in the neutron flux determination 7.8 % .2158200100046 The error in the activities ratio results from : 2158200100047 (ERR-3) Error in the photopeak efficiency 5.% 2158200100048 (ERR-4) Error in the gamma ray intensity in the decay 2158200100049 5.6 % . 2158200100050 The error in the flux measurement contains : 2158200100051 (ERR-5) Error from Co-60 activity 5.2 %, 2158200100052 (ERR-6) Error from epithermal activation correction 3%,2158200100053 (ERR-7) Error in determination of number of Co-59 2158200100054 atoms 5.%. 2158200100055 CORRECTION At neutron flux determination the factors of correction2158200100056 for diminution of Co-59 and Co-60 during irradiation - 2158200100057 0.997 (estimated from irradiation time 283.5 h) and 2158200100058 for epithermal activation of Co-59 - 1.02 (obtained by 2158200100059 using cadmium ratio 52 for Co, calculated from cadmium 2158200100060 ratio 7.5 for Au at the irradiation hole of JRR-3). 2158200100061 HISTORY (19800613C) G.C. 2158200100062 (19800718E) 2158200100063 (19840106U) A.P.T. JAPAN code changed to JPN 2158200100064 (19840106E) 2158200100065 (20080730U) M.M. BIB information was added. 2158200100066 Free text was corrected to be "human-readable". 2158200100067 Format misprint in DECAY-MON was corrected. 2158200100068 Dates were corrected for 4-digits year. 2158200100069 Errors were added in COMMON. MISC1, MISC2 were added. 2158200100070 DATA was changed into DATA-MAX in according to 2158200100071 authors' comment in Chapter 2. Discussions. 2158200100072 (20120120A) NDS(VZ): REL-REF: ND/B->NDS 2158200100073 ENDBIB 71 0 2158200100074 COMMON 12 6 2158200100075 EN-DUMMY MONIT MONIT-ERR ASSUM2 ASSUM1 ERR-1 2158200100076 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 ERR-7 2158200100077 EV B B B B PER-CENT 2158200100078 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2158200100079 2.5000E-02 3.7200E+01 2.0000E-01 4.3300E+00 5.5000E+00 7.5 2158200100080 7.8 5. 5.6 5.2 3. 5. 2158200100081 ENDCOMMON 6 0 2158200100082 ENDSUBENT 81 0 2158200199999 SUBENT 21582002 20080730 22022158200200001 BIB 8 28 2158200200002 REACTION (51-SB-124(N,G)51-SB-125,,SIG,,MXW) 2158200200003 DECAY-DATA (51-SB-125,2.77YR,DG,428.,0.298) 2158200200004 (51-SB-124-G,60.3D,DG,1691.,0.484) 2158200200005 DECAY-MON (27-CO-60,5.272YR,DG,1173.,,DG,1333.) 2158200200006 Photo-peak of 1.333 MeV Co-60 was used for thermal 2158200200007 neutron flux determination. Photo-peak yield 4683 2158200200008 counts, photo-peak efficiency 9.6E-4 for 1.33 MeV 2158200200009 gamma-ray. 2158200200010 ANALYSIS Photo-peak yields ratio of Sb-125 to Sb-124 was used 2158200200011 to estimate the effective thermal neutron capture 2158200200012 cross section of Sb-124. Values of detector efficiency2158200200013 3.4E-03 and 8.6E-4 were used for 428-keV and 1.691-MeV2158200200014 gamma-rays, respectively.Photo-peak yields in spectrum2158200200015 were 121824 and 18695 counts for 428 keV and 1.691 MeV2158200200016 gammas, respectively. 2158200200017 MISC-COL (MISC1) Activities Ratio of Co-125 to Co-124. 2158200200018 (MISC2) Error of MISC1. 2158200200019 COMMENT Of authors. Antimony sample was activated in the 2158200200020 irradiation hole of JRR-3.No irradiation covered with 2158200200021 cadmium was carried out. Obtained result gives the 2158200200022 reactor neutron capture cross section, that is not 2158200200023 thermal but effective (including epithermal) neutron 2158200200024 capture cross section. It is therefore considered that2158200200025 the present cross section value is a maximum value for 2158200200026 the thermal neutron capture cross section of Sb-124. 2158200200027 STATUS -Text,NST,16,8,546- in Abstract, page 550 in text. 2158200200028 HISTORY (19800613C) G.C. 2158200200029 (19800718E) 2158200200030 ENDBIB 28 0 2158200200031 NOCOMMON 0 0 2158200200032 DATA 5 1 2158200200033 DATA-MAX +DATA-ERR -DATA-ERR MISC1 MISC2 2158200200034 B B B NO-DIM NO-DIM 2158200200035 17.4 2.8 2.5 2.67 0.20 2158200200036 ENDDATA 3 0 2158200200037 ENDSUBENT 36 0 2158200299999 ENDENTRY 2 0 2158299999999