ENTRY 22769 20151215 22462276900000001 SUBENT 22769001 20151215 22462276900100001 BIB 15 50 2276900100002 TITLE Measurement of the resonance integral for the 2276900100003 In-115(n,gamma)In-116 reaction 2276900100004 AUTHOR (Y.Yoon, S.Lee, T.Ro, S.Yamamoto, K.Kobayashi) 2276900100005 INSTITUTE (2JPNKTO) Yamamoto, Kobayashi - Research Reactor 2276900100006 Institute of Kyoto University, experimental site. 2276900100007 (3KORDAU) Yoon, Ro, Lee 2276900100008 REFERENCE (J,KPS,44,809,2004) Main reference 2276900100009 FACILITY (REAC,2JPNKTO) The Kyoto University reactor KURRI 2276900100010 METHOD (ACTIV) Activation. Parameters used in analysis: 2276900100011 In-116 Au-198 2276900100012 Irradiation time (sec) 1800 1800 2276900100013 Cooling time (sec) 18300 112000 2276900100014 Measuring time (sec) 1130 8400 2276900100015 (STTA) Stack target irradiation 2276900100016 DETECTOR (HPGE) 5.5 cm in length * 5.6 cm in diameter. 2276900100017 The performance of the HPGE detector was 2276900100018 characterized by a relative efficiency of 34% for 2276900100019 a 7.6 cm * 7.6 cm NaI(Tl) detector. 2276900100020 INC-SPECT -1/E epithermal spectrum for hydraulic tube facility. 2276900100021 where neutron irradiation of targets was performed 2276900100022 Samples were irradiated with cadmium shield. 2276900100023 PART-DET (G) 2276900100024 MONITOR ((MONIT)79-AU-197(N,G)79-AU-198,,RI) 2276900100025 Gold-aluminum alloy wire was used for monitoring of 2276900100026 neutron flux. 2276900100027 DECAY-MON (79-AU-198-G,2.696D,DG,411.,0.955) 2276900100028 SAMPLE An In-115/Al alloy foil, atomic weight indium is 2276900100029 114.82, net weight of the sample in the Al alloy 2276900100030 is 0.0025 g, isotopic composition In-115 is 95.7% and 2276900100031 In-113 is 4.3%, size of sample is 5.0*5.0*0.3 mm. 2276900100032 Gold monitor sample is Au/Al alloy wire, gold atomic 2276900100033 weight is 196.97, net weight of the sample in the Al- 2276900100034 alloy is 0.000136 g, size of sample is 30mm length * 2276900100035 0.510 mm in diameter. 2276900100036 ERR-ANALYS (MONIT-ERR) Monitor error 2276900100037 (ERR-S) Error to the statistical counts is 0.8% for 2276900100038 indium 2276900100039 (ERR-1) Error in the gamma-ray detection efficiency 2276900100040 resulting from the ambiguity of the calibration source2276900100041 intensity is 2.3%. 2276900100042 (ERR-2) Error in the neutron flux measurement is 2.7%. 2276900100043 (ERR-3) Error in the measurement of the sample weight 2276900100044 is 0.1%. 2276900100045 (ERR-4) Error in the geometrical factor for irradiation2276900100046 of the sample is 0.1%. 2276900100047 (ERR-5) Error to the statistical counts is 1.3% for Au 2276900100048 STATUS (TABLE) Table 4 from KPS,44,809,2004 2276900100049 HISTORY (20060705C) + + Compiled by S.M.,... + + 2276900100050 (20061009A) Last corrections have been done. 2276900100051 (20151215A) SD: DECAY-DATA corrected in Subent 002. 2276900100052 ENDBIB 50 0 2276900100053 COMMON 8 6 2276900100054 MONIT MONIT-ERR ERR-S ERR-1 ERR-2 ERR-3 2276900100055 ERR-4 ERR-5 2276900100056 B B PER-CENT PER-CENT PER-CENT PER-CENT 2276900100057 PER-CENT PER-CENT 2276900100058 1550. 28. 0.8 2.3 2.7 0.12276900100059 0.1 1.3 2276900100060 ENDCOMMON 6 0 2276900100061 ENDSUBENT 60 0 2276900199999 SUBENT 22769002 20151215 22462276900200001 BIB 7 10 2276900200002 REACTION (49-IN-115(N,G)49-IN-116-M1+M2,,RI) 2276900200003 ANALYSIS The resonance integral was obtained by normalizing 2276900200004 the measured data to the resonance integral of the 2276900200005 Au-197(n,gamma)Au-198 reaction. 2276900200006 DECAY-DATA (49-IN-116-M1,54.1MIN,DG,416.,0.292) 2276900200007 ASSUMED (ASSUM,49-IN-0(N,G),,SIG,,MXW) Subent 22802002 2276900200008 REL-REF (A,22802004,Y.Yoon+,J,ANE,29,1157,200210) 2276900200009 ERR-ANALYS (DATA-ERR) The error as reported by authors 2276900200010 HISTORY (20151215A) SD: In-116-> In-116m1 in DECAY-DATA; 2276900200011 SF4=In-116 -> In-116m1+m2 in REACTION code. 2276900200012 ENDBIB 10 0 2276900200013 NOCOMMON 0 0 2276900200014 DATA 5 1 2276900200015 EN-MIN DATA DATA-ERR ASSUM ASSUM-ERR 2276900200016 EV B B B B 2276900200017 0.5 3275.4 134.2 199.6 5.6 2276900200018 ENDDATA 3 0 2276900200019 ENDSUBENT 18 0 2276900299999 ENDENTRY 2 0 2276999999999