ENTRY 22679 20220102 23072267900000001 SUBENT 22679001 20220102 23072267900100001 BIB 19 67 2267900100002 TITLE Measurement of the thermal neutron capture cross 2267900100003 section and the resonance integral of the 2267900100004 90Sr(n,gamma)91Sr reaction 2267900100005 AUTHOR (S.Nakamura,K.Furutaka,H.Wada,T.Fujii,H.Yamana, 2267900100006 T.Katoh,H.Harada) 2267900100007 INSTITUTE (2JPNJNC) Nakamura, Furutaka, Wada, Katoh, Harada 2267900100008 (2JPNKTO) Fujii, Yamana 2267900100009 (2JPNGMT) GIFU College of Medical Technology 2267900100010 REFERENCE (J,NST,38,1029,2001) Main reference, data are 2267900100011 given 2267900100012 (J,NSTS,2,(1),258,2002) Data given 2267900100013 REL-REF (M,22295001,H.Harada+,J,NST,32,395,1995) Experimental 2267900100014 and details of analysis 2267900100015 FACILITY (REAC,2JPNKTO) Reactor KURRI of Kyoto University 2267900100016 METHOD (ACTIV,GSPEC,SITA) 2267900100017 MONITOR ((MONIT1)27-CO-59(N,G)27-CO-60,,SIG) 2267900100018 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 2267900100019 DECAY-MON (27-CO-60-G,5.271YR,DG,1173.,0.9990, 2267900100020 DG,1332.,0.9998) 2267900100021 (79-AU-198-G,2.695D,DG,412.,0.955) 2267900100022 MONIT-REF (,S.F.Mughabghab+,B,NEUT.CS 1A,,,1981) 2267900100023 DECAY-DATA (38-SR-90,28.8YR) 2267900100024 (38-SR-91,9.63HR,DG,750.,, 2267900100025 DG,1024.) 2267900100026 DETECTOR (HPGE) Efficiency is 90% relative to 7.6*7.6 cm 2267900100027 Na-I(Tl) detector, energy resolution (FWHM) 2267900100028 is 2.1 keV at the 1.33 MeV peak of 60Co. 2267900100029 INC-SPECT Irradiation was fulfilled with and without cadmium 2267900100030 shield 2267900100031 INC-SOURCE (REAC) Irradiation of the target was performed in a 2267900100032 hydraulic transfer tube of Kyoto University 2267900100033 reactor for 10 hours with and without cadmium 2267900100034 capsule 2267900100035 ASSUMED (ASSUM1,27-CO-59(N,G)27-CO-60,,RI,,RNV) E-Min =0.5eV 2267900100036 (ASSUM2,79-AU-197(N,G)79-AU-198,,RI,,RNV) E-Min=0.5eV 2267900100037 SAMPLE 90Sr-Cl2 standardized solution, equivalent to 2267900100038 3.7 x 10**2 kBq was pipetted into the bottom of high- 2267900100039 purity quartz tube 8 mm inner diam, 100 mm length. A 2267900100040 40 kBq 85Sr-Cl2 standardized solution was added in the2267900100041 same manner. After drying of the solution, the quartz 2267900100042 tube was welded under evacuation. The welded tube was 2267900100043 circa 20 mm in length. This tube was put into alumin. 2267900100044 capsule and then housed in the irradiation capsule. 2267900100045 The loss of 85Sr was checked by the radioactivity of 2267900100046 514-keV gamma line emitted from 85Sr 2267900100047 Monitor samples were Co/Al alloy wire 0.381 mm diam, 2267900100048 cobalt content 0,46wt%, and 2267900100049 Au/Al alloy wire 0.510 mm diam, gold content 0.112wt%.2267900100050 STATUS (TABLE) Table 5 of Nucl.Sci.Tech.,38(2001)1029 2267900100051 ERR-ANALYS (ERR-T) Total error 2267900100052 (ERR-1) Error of the gamma-ray efficiency resulting 2267900100053 from the ambiguity of calibration source 2267900100054 (ERR-2) Error due to the measurements of neutron flux 2267900100055 (ERR-3) Error of the activity measurements due to 2267900100056 error of the 91Sr half-life 2267900100057 (ERR-4) Error of the activity measurement due to 2267900100058 uncertainty of emission probability of 1024 KeV 2267900100059 gamma line 2267900100060 (ERR-5) Error die to the measurement of the specific 2267900100061 activity of 90Sr 2267900100062 (ERR-6) Error due to measurement of target weight 2267900100063 HISTORY (20020802C) + + Compiled by S.M. 2267900100064 (20040324A) . . Correlations specified 2267900100065 (20040327U) Monitor codes corrected -SM 2267900100066 (20131202A) Reaction code corrected in Subents 2,4. 2267900100067 (20190418U) SD: NST,32,395 moved to REL-REF. 2267900100068 (20220102A) SD: Corrections in Subent 004. 2267900100069 ENDBIB 67 0 2267900100070 COMMON 11 6 2267900100071 EN-NRM MONIT1 ASSUM1 MONIT2 ASSUM2 ERR-1 2267900100072 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2267900100073 EV B B B B PER-CENT 2267900100074 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2267900100075 2.53E-02 37.18 052.27 98.65 1505. 2.32267900100076 9.1 1.2 6.89 0.88 0.03 2267900100077 ENDCOMMON 6 0 2267900100078 ENDSUBENT 77 0 2267900199999 SUBENT 22679002 20131202 22382267900200001 BIB 4 6 2267900200002 REACTION (38-SR-90(N,G)38-SR-91,,SIG) 2267900200003 REL-REF (D,22279002,H.Harada+,J,NST,31,173,1994) 2267900200004 STATUS (COREL,22638003) 2267900200005 HISTORY (20040324A) Link to 22687 deleted 2267900200006 (20040327U) Last checking has been done. 2267900200007 (20131202A) SD: Delete SF8=MXW (2200 m/s xsec. given) 2267900200008 ENDBIB 6 0 2267900200009 NOCOMMON 0 0 2267900200010 DATA 3 1 2267900200011 EN DATA ERR-T 2267900200012 EV MB MB 2267900200013 2.53E-02 10.1 1.3 2267900200014 ENDDATA 3 0 2267900200015 ENDSUBENT 14 0 2267900299999 SUBENT 22679003 20040327 00002267900300001 BIB 2 3 2267900300002 REACTION ((38-SR-90(N,G)38-SR-91,,RI,,RNV/FCT)// 2267900300003 (38-SR-90(N,G)38-SR-91,,SIG,,MXW)) Times (2./Sqrt(pi)) 2267900300004 STATUS .From table 5 of main reference 2267900300005 ENDBIB 3 0 2267900300006 COMMON 2 3 2267900300007 EN-MIN-NM EN-DN 2267900300008 EV EV 2267900300009 0.5 0.0253 2267900300010 ENDCOMMON 3 0 2267900300011 DATA 2 1 2267900300012 DATA ERR-T 2267900300013 NO-DIM NO-DIM 2267900300014 11.1 1. 2267900300015 ENDDATA 3 0 2267900300016 ENDSUBENT 15 0 2267900399999 SUBENT 22679004 20220102 23072267900400001 BIB 5 13 2267900400002 REACTION (38-SR-90(N,G)38-SR-91,,RI) 2267900400003 ANALYSIS Full resonance integral derived from sigma and 2267900400004 I-res/rnv 2267900400005 REL-REF (D,,H.Harada+,J,NST,31,173,1994) 2267900400006 STATUS (DEP,22679002) 2267900400007 (DEP,22679003) 2267900400008 HISTORY (20040324U) Link to 22687 deleted. 2267900400009 Data value corrected 2267900400010 (20040327U) Last checking has been done. 2267900400011 (20131202A) SD: SF9=DERIV deleted (typical derivation 2267900400012 of RI) 2267900400013 (20220102A) SD: Value and data units corrected. 2267900400014 ANALYSIS added. 2267900400015 ENDBIB 13 0 2267900400016 NOCOMMON 0 0 2267900400017 DATA 3 1 2267900400018 EN-MIN DATA ERR-T 2267900400019 EV MB MB 2267900400020 0.5 104. 16. 2267900400021 ENDDATA 3 0 2267900400022 ENDSUBENT 21 0 2267900499999 ENDENTRY 4 0 2267999999999