ENTRY 14697 20210429 14881469700000001 SUBENT 14697001 20210429 14881469700100001 BIB 11 59 1469700100002 TITLE Aqueous harvesting of 88Zr at a radioactive ion beam 1469700100003 facility for cross section measurements 1469700100004 AUTHOR (J.A.Shusterman,N.D.Scielzo,E.Paige Abel,H.K.Clause, 1469700100005 N.D.Dronchi,W.D.Frey,N.Gharibyan,J.A.Hart, 1469700100006 C.Shaun Loveless,S.R.Mcguinness,L.T.Sutherlin, 1469700100007 K.J.Thomas,S.E.Lapi,J.David Robertson, M.A.Stoyer, 1469700100008 E.B.Norman,G.F.Peaslee,G.W.Severin,D.A.Shaughnessy) 1469700100009 INSTITUTE (1USALRL,1USAMSU,1USADAV,1USAUAL,1USANOT,1USAMIS, 1469700100010 1USAUCX) 1469700100011 (1USAUSA) City University of New York, New York 1469700100012 REFERENCE (J,PR/C,103,024614,2021) 1469700100013 FACILITY (REAC,1USADAV) Part of 88Yr samples were irradiated 1469700100014 using high power TRIGA reactor at McClellan Nuclear 1469700100015 Research Center located in Sacramento, operated by 1469700100016 the University of California, Davis 1469700100017 (REAC,1USAMIS) 88Yr and 88Zr samples were irradiated 1469700100018 at 10MW open pool PWR at the University of Missouri 1469700100019 Research Reactor Center (MURR). 1469700100020 DETECTOR (HPGE) Sample activities was measured using HPGe 1469700100021 detector 1469700100022 METHOD (ACTIV) 1469700100023 MONITOR The monitor foils for the 1-hour irradiation contained 1469700100024 Zr, Fe, and Mo, foils for the 10-hour irradiation 1469700100025 contained only Zr and Fe. Monitor foils were 1469700100026 individually encapsulated in quartz. 1469700100027 (26-FE-0(N,G),,SIG) 1469700100028 (40-ZR-0(N,G),,SIG) 1469700100029 (42-MO-0(N,G),,SIG) 1469700100030 INC-SOURCE At MURR, one set of samples was irradiated for 1 hour 1469700100031 and a second one for 10 hours in the graphite reflector1469700100032 At MNRC, two sets of samples containing 88Zr and Fe, 1469700100033 Zr, and Mo monitor foils were separately encapsulated 1469700100034 in quartz and irradiated for 12 hours in the Neutron 1469700100035 Transmutation Doping location. This location has the 1469700100036 highest ratio of thermal (<0.5 eV) to fast (>1 MeV) 1469700100037 neutrons in the MNRC reactor. One set of samples was 1469700100038 irradiated with a 1-mm-thick cadmium wrapping, to 1469700100039 reduce the thermal flux by two orders of magnitude. 1469700100040 ERR-ANALYS Uncertainties related to sample chemical composition 1469700100041 and yield 1469700100042 (ERR-S,,3.) Counting statistics 1469700100043 (ERR-1) Uncertainty in sample geometry 1469700100044 (ERR-2) HPGe calibration efficiency 1469700100045 (ERR-3,,0.5) Dilution by mass 1469700100046 (ERR-4,0.5,10.) Mass spectrometry 1469700100047 Uncertainties related to neutron flux determination 1469700100048 (ERR-5,0.3,7.4) Monitor mass 1469700100049 (ERR-6,,0.8) Irradiation time 1469700100050 (ERR-7) Sample geometry 1469700100051 (ERR-8) HPGe calibration efficiency 1469700100052 (ERR-9,,2.) Counting statistics 1469700100053 (ERR-10) Thermal cross-section reference data 1469700100054 (ERR-11) Resonance cross-section reference data 1469700100055 Uncertainties associated with final-to-initial 1469700100056 atom ratios 1469700100057 (ERR-12) Sample geometry 1469700100058 (ERR-13) HPGe calibration efficiency 1469700100059 (ERR-14,0.5,4.6) Counting statistics 1469700100060 HISTORY (20210429C) Compiled by S.H. 1469700100061 ENDBIB 59 0 1469700100062 COMMON 8 6 1469700100063 ERR-1 ERR-2 ERR-7 ERR-8 ERR-10 ERR-11 1469700100064 ERR-12 ERR-13 1469700100065 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 1469700100066 PER-CENT PER-CENT 1469700100067 3. 1. 3. 1. 5.6 8.8 1469700100068 6. 1. 1469700100069 ENDCOMMON 6 0 1469700100070 ENDSUBENT 69 0 1469700199999 SUBENT 14697002 20210429 14881469700200001 BIB 5 16 1469700200002 REACTION (40-ZR-88(N,G)40-ZR-89-G,M+,SIG) 1469700200003 DECAY-DATA (40-ZR-89-G,3.267D,DG,909.15,0.9904) 1469700200004 SAMPLE 88Zr was produced by projectile fragmentation of 1469700200005 140 MeV/A 92Mo primary beam at NSLS. 88ZR fragments 1469700200006 were separated by A1900 projectile fragment separator 1469700200007 and collected in water target irradiation cell. Water 1469700200008 target was then radiochemically processed and 1469700200009 concentrated as the final Zr stock containing 7 mu-Ci 1469700200010 of 88Zr and 1.1 mu-Ci of 88Y resulting from 88Zr 1469700200011 decay, and detectable amounts of 85Sr and 83Rb. 1469700200012 Two 88Y targets were prepared by pipetting Zr stock 1469700200013 into 4 mm/6 mm diameter Suprasil quartz tubes, dried 1469700200014 and sealed. 1469700200015 ERR-ANALYS (ERR-T) Total uncertainty 1469700200016 STATUS (TABLE) Data taken from text, p.9 of the 1469700200017 reference 1469700200018 ENDBIB 16 0 1469700200019 NOCOMMON 0 0 1469700200020 DATA 3 1 1469700200021 EN-DUMMY DATA ERR-T 1469700200022 EV B B 1469700200023 0.025 8.81E+5 0.63E+5 1469700200024 ENDDATA 3 0 1469700200025 ENDSUBENT 24 0 1469700299999 SUBENT 14697003 20210429 14881469700300001 BIB 4 5 1469700300002 REACTION (40-ZR-88(N,G)40-ZR-89-G,M+,RI) 1469700300003 DECAY-DATA (40-ZR-89-G,3.267D,DG,909.15,0.9904) 1469700300004 ERR-ANALYS (ERR-T) Total uncertainty 1469700300005 STATUS (TABLE) Data taken from text, p.9 of the 1469700300006 reference 1469700300007 ENDBIB 5 0 1469700300008 NOCOMMON 0 0 1469700300009 DATA 3 1 1469700300010 EN-MIN DATA ERR-T 1469700300011 EV B B 1469700300012 0.025 2.53E+6 0.28E+6 1469700300013 ENDDATA 3 0 1469700300014 ENDSUBENT 13 0 1469700399999 SUBENT 14697004 20210429 14881469700400001 BIB 4 18 1469700400002 REACTION (39-Y-88(N,G)39-Y-89,,SIG) 1469700400003 SAMPLE (39-Y-88,ENR=0.96) 88Y was produced by projectile 1469700400004 fragmentation of 140 MeV/A 92Mo primary beam at NSLS, 1469700400005 fragments were separated by A1900 projectile fragment 1469700400006 separator and collected in water target irradiation 1469700400007 cell. Water target was then radiochemically processed 1469700400008 and concentrated as the final Y stock containing 0.9 1469700400009 mu-Ci of 88Y 0.3 mu-Ci of 85Sr, and 0.02 mu-Ci of 1469700400010 83Rb and no detectable 88Zr. Two 88Y targets were 1469700400011 prepared by pipetting Y stock into 4 mm/6 mm diameter 1469700400012 Suprasil quartz tubes, dried and sealed 1469700400013 METHOD Since reaction product 89Y is stable, 1469700400014 the upper limit for thermal neutron capture 1469700400015 cross section for 88Y was determined from 1469700400016 the disappearance of 88Y by measurement of 1469700400017 88Y activity before and after irradiation. 1469700400018 STATUS (TABLE) Data taken from text, p.10 of the 1469700400019 reference 1469700400020 ENDBIB 18 0 1469700400021 NOCOMMON 0 0 1469700400022 DATA 2 1 1469700400023 EN-DUMMY DATA-MAX 1469700400024 EV B 1469700400025 0.025 1.8E+4 1469700400026 ENDDATA 3 0 1469700400027 ENDSUBENT 26 0 1469700499999 ENDENTRY 4 0 1469799999999