ENTRY 22833 20190418 22782283300000001 SUBENT 22833001 20190418 22782283300100001 BIB 16 63 2283300100002 TITLE Measurements of thermal neutron capture cross section 2283300100003 and resonance integral of the 109Ag(n,gamma)110mAg 2283300100004 reaction 2283300100005 AUTHOR (S.Nakamura,H.Wada,O.Shcherbakov,K.Furutaka, H.Harada, 2283300100006 T.Katoh) 2283300100007 INSTITUTE (2JPNJNC) S.Nakamura, H.Wada, O.Shcherbakov, 2283300100008 K.Furutaka, H.Harada, T.Katoh; Japan Nuclear 2283300100009 Cycle Development Institute 2283300100010 (2JPNGMT) Katoh 2283300100011 REFERENCE (J,NST,40,119,2003) Main reference, data and 2283300100012 error structure are given 2283300100013 REL-REF (M,22295001,H.Harada+,J,NST,32,395,1995) Experimental 2283300100014 and details of analysis 2283300100015 FACILITY (REAC,2JPNYOK) Rikkyo University reactor 2283300100016 METHOD (ACTIV) Activation 2283300100017 (SITA) Single-target irradiation 2283300100018 (GSPEC) 2283300100019 DETECTOR (HPGE) Detector performance is characterized by the 2283300100020 relative efficiency of 90% to a 7.6 cm thick 2283300100021 and 7.6 cm in diameter Na-I(Tl) detector and 2283300100022 an energy resolution 2.1 KeV full width at 2283300100023 half-maximum at the 1.33 MeV peak of 60Co 2283300100024 MONITOR ((MONIT1)27-CO-59(N,G)27-CO-60,,SIG) 2283300100025 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 2283300100026 DECAY-MON (27-CO-60-G,5.271YR,DG,1173.,0.9990, 2283300100027 DG,1333.,0.9998) 2283300100028 (79-AU-198-G,2.695D,DG,412.,0.955) 2283300100029 DECAY-DATA (47-AG-110-M,,DG) 2283300100030 INC-SPECT .Samples were irradiated with and without cadmium 2283300100031 shield. Because 59Co and 197Al have different sensi- 2283300100032 tivities to thermal and epithermal neutrons, monitor 2283300100033 wires allow to determine the thermal and epithermal 2283300100034 fractions of neutron flux 2283300100035 SAMPLE .Monitor samples are cobalt/aluminium and gold/ 2283300100036 aluminium wires which were used to monitor neutron 2283300100037 flux at the target positions 2283300100038 -Co/Al alloy(Co 0.46wt%, 0,381 mm in diameter), 2283300100039 Au/Al alloy (Au-0.112wt%,0,510 mm diam) 2283300100040 .Metallic silver foil. The irradiation of the sample 2283300100041 was performed in a hydraulic transfer tube of Kyoto 2283300100042 University reactor with and without cadmium capsule 2283300100043 ERR-ANALYS (ERR-T) Total error composed of particular ones 2283300100044 given below 2283300100045 (ERR-S,,0.5) Max stat. error for the gamma-ray 2283300100046 measurement of the holmium samples 2283300100047 (ERR-1) Error of the gamma-ray full energy peak 2283300100048 efficiency resulting from the uncertainty of 2283300100049 the calibration source 2283300100050 (ERR-2) Error of the detection efficiency of the 2283300100051 detector due to the ambiguity of the geomet- 2283300100052 rical setting of the targets 2283300100053 (ERR-3) Error in the measurement of the neutron flux 2283300100054 (ERR-4) Error due to the variation of the neutron 2283300100055 flux 2283300100056 (ERR-5) Error in the absolute intensity of gamma-rays2283300100057 (ERR-6) Error in the measurements of example weights 2283300100058 (ERR-7,,1.) Max stat. Error for the gamma-ray 2283300100059 measurement of the monitor wires 2283300100060 STATUS (TABLE) Data are taken from Nucl.Sci.Tech.40(2003)119 2283300100061 HISTORY (20040625C) Compiled, J.O.S. 2283300100062 (20061124U) Reference corrected 2283300100063 (20190418U) SD: NST,32,395 moved to REL-REF. 2283300100064 ERR-ANALYS updated. 2283300100065 ENDBIB 63 0 2283300100066 COMMON 10 6 2283300100067 MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR ERR-1 ERR-2 2283300100068 ERR-3 ERR-4 ERR-5 ERR-6 2283300100069 B B B B PER-CENT PER-CENT 2283300100070 PER-CENT PER-CENT PER-CENT PER-CENT 2283300100071 37.18 0.06 98.65 0.09 3. 1.52283300100072 2.4 1.5 21. 0.2 2283300100073 ENDCOMMON 6 0 2283300100074 ENDSUBENT 73 0 2283300199999 SUBENT 22833002 20040625 00002283300200001 BIB 1 1 2283300200002 REACTION (47-AG-109(N,G)47-AG-110-M,,SIG) 2283300200003 ENDBIB 1 0 2283300200004 NOCOMMON 0 0 2283300200005 DATA 3 1 2283300200006 EN DATA ERR-T 2283300200007 EV B B 2283300200008 2.53E-02 4.12 0.10 2283300200009 ENDDATA 3 0 2283300200010 ENDSUBENT 9 0 2283300299999 SUBENT 22833003 20040625 00002283300300001 BIB 1 1 2283300300002 REACTION (47-AG-109(N,G)47-AG-110-M,,RI) 2283300300003 ENDBIB 1 0 2283300300004 NOCOMMON 0 0 2283300300005 DATA 3 1 2283300300006 EN-MEAN DATA ERR-T 2283300300007 EV B B 2283300300008 0.5 E+00 67.9 3.1 2283300300009 ENDDATA 3 0 2283300300010 ENDSUBENT 9 0 2283300399999 ENDENTRY 3 0 2283399999999