ENTRY 14453 20160414 14171445300000001 SUBENT 14453001 20160414 14171445300100001 BIB 12 27 1445300100002 TITLE Reducing uncertainties for short lived cumulative 1445300100003 fission product yields 1445300100004 AUTHOR (S.Stave,A.Prinke,L.Greenwood,D.Haas,J.T.Burke, 1445300100005 J.J.Ressler,A.P.Tonchev,W.Younes) 1445300100006 INSTITUTE (1USABNW,1USALRL) 1445300100007 REFERENCE (J,JRN,307,2221,2016) 1445300100008 FACILITY (CRASS,1USALRL) The samples were irradiated in the 1445300100009 Godiva critical assembly at the Nevada National 1445300100010 Security Site.The assembly was operated in burst mode 1445300100011 to minimize the effects of isotope grow-in and decay 1445300100012 during irradiation. 1445300100013 SAMPLE (92-U-235,ENR=0.9944) Two small samples of enriched 1445300100014 235U in oxide form were sealed in quartz ampules to 1445300100015 contain fission product gasses after irradiation. 1445300100016 Masses of two samples were 8.6+-0.65 mg and 1445300100017 63+-7.2 mg 1445300100018 DETECTOR (HPGE) Detector setup consisted of two broad-energy 1445300100019 germanium (BEGe) detectors each with approximately 1445300100020 65 % relative efficiency. 1445300100021 METHOD (ACTIV) Activation method was used 1445300100022 MONITOR High purity wires of Fe, Ti, Au and Co were 1445300100023 used to determine neutron flux at the saample) 1445300100024 INC-SOURCE Critical 235U assembly. 1445300100025 CORRECTION Data corrected for - dead time 1445300100026 - gamma selfabsorption 1445300100027 - neutron selfabsorption 1445300100028 HISTORY (20160414C) Compiled by S.H. 1445300100029 ENDBIB 27 0 1445300100030 NOCOMMON 0 0 1445300100031 ENDSUBENT 30 0 1445300199999 SUBENT 14453002 20160414 14171445300200001 BIB 4 13 1445300200002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,FIS) 1445300200003 DECAY-DATA ((1.)37-RB-89,909.0SEC) 1445300200004 ((2.)39-Y-93-G,36648.0SEC) 1445300200005 ((3.)50-SN-128-G,3544.2SEC) 1445300200006 ((4.)51-SB-131,1380.0SEC) 1445300200007 ERR-ANALYS (ERR-T) Total uncertainty 1445300200008 (ERR-1) Uncertainty in absolute number of fissions 1445300200009 (ERR-2) Includes statistical uncertainty, uncertainty 1445300200010 in nuclear data and detector efficiency, added1445300200011 in quadrature 1445300200012 (ERR-3) Uncertainty in gamma ray selfabsorption 1445300200013 STATUS (TABLE) Data taken from tab. 3 of the reference 1445300200014 (PRELM) Preliminary data 1445300200015 ENDBIB 13 0 1445300200016 COMMON 2 3 1445300200017 EN-DUMMY ERR-1 1445300200018 MEV PER-CENT 1445300200019 1.5 5.0 1445300200020 ENDCOMMON 3 0 1445300200021 DATA 7 4 1445300200022 ELEMENT MASS DATA ERR-2 ERR-3 ERR-T 1445300200023 DECAY-FLAG 1445300200024 NO-DIM NO-DIM PC/FIS PER-CENT PER-CENT PER-CENT 1445300200025 NO-DIM 1445300200026 37.0 89.0 5.15E-2 2.0 0.2 5.4 1445300200027 1. 1445300200028 39.0 93.0 5.90E-2 7.0 4.0 9.5 1445300200029 2. 1445300200030 50.0 128.0 4.84E-3 5.0 0.7 7.1 1445300200031 3. 1445300200032 51.0 131.0 2.58E-2 3.0 0.3 5.8 1445300200033 4. 1445300200034 ENDDATA 12 0 1445300200035 ENDSUBENT 34 0 1445300299999 ENDENTRY 2 0 1445399999999