ENTRY 14657 20200824 14721465700000001 SUBENT 14657001 20200824 14721465700100001 BIB 12 28 1465700100002 TITLE The 89Y(n,g) reaction: Radiative cross sections and 1465700100003 the decay of 90mY 1465700100004 AUTHOR (K.S.Krane) 1465700100005 INSTITUTE (1USAORU) 1465700100006 REFERENCE (J,ARI,163,109191,2020) 1465700100007 FACILITY (REAC,1USAORU) Experiment performed at the Oregon 1465700100008 State University TRIGA reactor. 1465700100009 SAMPLE Metal foils of Y with 99.9% purity and thickness of 1465700100010 0.1 mm 1465700100011 DETECTOR (HPGE) The gamma rays were observed with a high- 1465700100012 purity Ge detector with nominal volume of 169 cm3, 1465700100013 efficiency of 35-40% compared with NaI at 1332 keV, 1465700100014 resolution of 1.7-1.8 keV at 1332 keV). 1465700100015 METHOD (ACTIV) Activation method was used 1465700100016 INC-SOURCE (REAC) Four different irradiation stations were used 1465700100017 in this experiment 1465700100018 Site Thermal epith.flux 1465700100019 n/cm2/s n/cm2/s 1465700100020 1. Thermal column 8.E+10 2.E+8 1465700100021 2. Two in core irradiation sites 4.3E+12 3.9E+11 1465700100022 3. Cd lined site in central core 1.2E+12 0 1465700100023 4. Pneumatic transport 8.3E+12 3.3E+11 1465700100024 DECAY-DATA (39-Y-90-M,3.178HR,DG,202.539,1.000, 1465700100025 DG,479.532,0.924, 1465700100026 DG,682.03,0.0032) 1465700100027 Decay data determined by author. 1465700100028 CORRECTION Coincidence summing corrections were made 1465700100029 HISTORY (20200824C) Compiled by S.H. 1465700100030 ENDBIB 28 0 1465700100031 NOCOMMON 0 0 1465700100032 ENDSUBENT 31 0 1465700199999 SUBENT 14657002 20200824 14721465700200001 BIB 7 15 1465700200002 REACTION (39-Y-89(N,G)39-Y-90-M,,SIG,,MXW) 1465700200003 ERR-ANALYS (ERR-S) Statistical uncertainty 1465700200004 (ERR-1)Systematic uncertainty in sample mass 1465700200005 (ERR-2,0.5,0.7) Systematic uncertainty in absolute 1465700200006 gamma ray intensities 1465700200007 (ERR-T) Total uncertainty 1465700200008 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 1465700200009 Au as a dilute alloy (0.134%) in aluminum metal foil 1465700200010 MONIT-REF (V1002484,S.F.Mughabghab,B,NEUT.RES,,,2006) 1465700200011 FLAG (1.) Irradiation in thermal column 1465700200012 (2.) Irradiation in pneumatic rabbit 1465700200013 (3.) Irradiation in outer core 1465700200014 CORRECTION Correction for contribution of epithermal neutrons was 1465700200015 made using resonance integral measured in this work. 1465700200016 STATUS (TABLE) Data taken from text p.4 of the reference 1465700200017 ENDBIB 15 0 1465700200018 COMMON 3 3 1465700200019 ERR-S ERR-1 MONIT 1465700200020 PER-CENT PER-CENT B 1465700200021 0.5 0.5 98.65 1465700200022 ENDCOMMON 3 0 1465700200023 DATA 4 3 1465700200024 EN-DUMMY DATA ERR-T FLAG 1465700200025 EV B B NO-DIM 1465700200026 0.0253 1.02 0.01 1. 1465700200027 0.0253 0.98 0.02 2. 1465700200028 0.0253 1.06 0.03 3. 1465700200029 ENDDATA 5 0 1465700200030 ENDSUBENT 29 0 1465700299999 SUBENT 14657003 20200824 14721465700300001 BIB 6 10 1465700300002 REACTION (39-Y-89(N,G)39-Y-90-M,,RI) 1465700300003 ERR-ANALYS (ERR-S,1.0,1.5) Statistical uncertainty 1465700300004 (ERR-1,0.5,1.)Systematic uncertainty in sample mass 1465700300005 (ERR-2) Systematic uncertainty in Au resonance integral1465700300006 (ERR-T) Total uncertainty 1465700300007 STATUS (TABLE) Data taken from text p.4 of the reference 1465700300008 MONITOR (79-AU-197(N,G)79-AU-198,,RI) 1465700300009 MONIT-REF (V1002484,S.F.Mughabghab,B,NEUT.RES,,,2006) 1465700300010 FLAG (1.) Irradiation in Cd lined central core 1465700300011 (2.) Irradiation in pneumatic rabbit 1465700300012 ENDBIB 10 0 1465700300013 COMMON 2 3 1465700300014 ERR-2 MONIT 1465700300015 PER-CENT B 1465700300016 1.8 1550. 1465700300017 ENDCOMMON 3 0 1465700300018 DATA 4 2 1465700300019 EN-MIN DATA ERR-T FLAG 1465700300020 EV MB MB NO-DIM 1465700300021 0.5 7.82 0.19 1. 1465700300022 0.5 7.35 0.15 2. 1465700300023 ENDDATA 4 0 1465700300024 ENDSUBENT 23 0 1465700399999 ENDENTRY 3 0 1465799999999