ENTRY 14538 20190603 14521453800000001 SUBENT 14538001 20190603 14521453800100001 BIB 12 38 1453800100002 TITLE Fission yield measurements from highly enriched 1453800100003 uranium irradiated inside a boron carbide capsule 1453800100004 AUTHOR (L.A.Metz,J.I.Friese,E.C.Finn,L.R.Greenwood, 1453800100005 R.F.Kephart, C.C.Hines,M.D.King,K.M.Henry,D.E.Wall) 1453800100006 INSTITUTE (1USABNW,1USAWSU) 1453800100007 REFERENCE (J,JRN,296,763,2013) 1453800100008 #doi:10.1007/s10967-012-2089-z 1453800100009 #NSR: 2013ME05 1453800100010 FACILITY (REAC,1USAWSU) Experiment performed at 1 MW TRIGA 1453800100011 thermal research reactor at Washington State University1453800100012 DETECTOR (HPGE) Gamma spectra of fission products were 1453800100013 detected using HPGe detectors 1453800100014 METHOD (ACTIV,CHSEP) Activation method was used 1453800100015 INC-SOURCE The thermal sample was irradiated for 322 s in reactor 1453800100016 position E9, outside the reactor core. The non-thermal 1453800100017 sample was irradiated for 200 min in position D8(closer1453800100018 to the core than E9) for exposure to the highest 1453800100019 neutron flux. The non-thermal sample was irradiated in 1453800100020 a natural boron carbide (B4C) capsule, snugly wrapped 1453800100021 in cadmium sheeting (0.020 in. thick) with 1/2 in. 1453800100022 overlap in the circumference. 1453800100023 Two sets of high purity metal wires were used to 1453800100024 characterize neutron fluence and spectrum for each 1453800100025 uranium sample. The experimental measurements and the 1453800100026 MCNP model were used as input into the STAYSL PNNL code1453800100027 that provided an experimentally adjusted neutron 1453800100028 spectra. 1453800100029 INC-SPECT The B4C neutron spectrum was a little harder than a 1453800100030 fast flux reactor, but a bit softer than the COMET 1453800100031 experiment and 235U fission neutron spectrum. 1453800100032 The thermal spectrum of WSU E9 and B4C capsule spectrum1453800100033 is presented in Fig.2 in Rad.Nucl.Chem.,296,763,2013. 1453800100034 SAMPLE (92-U-235,ENR=0.9311)+-0.00007 1453800100035 (92-U-234,ENR=0.00755)+-0.0003 1453800100036 (92-U-236,ENR=0.00314)+-0.00003 1453800100037 (92-U-238,ENR=0.0582)+-0.0003 1453800100038 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties 1453800100039 HISTORY (20190603C) OG. 1453800100040 ENDBIB 38 0 1453800100041 NOCOMMON 0 0 1453800100042 ENDSUBENT 41 0 1453800199999 SUBENT 14538002 20190603 14521453800200001 BIB 3 3 1453800200002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 1453800200003 STATUS (TABLE) Table 2 in Rad. Nucl. Chem.,296,763,2013. 1453800200004 SAMPLE (92-U-235,ENR=0.9311) +-0.00007, 109 mg 235U 1453800200005 ENDBIB 3 0 1453800200006 COMMON 1 3 1453800200007 EN-DUMMY 1453800200008 EV 1453800200009 0.0253 1453800200010 ENDCOMMON 3 0 1453800200011 DATA 4 20 1453800200012 ELEMENT MASS DATA DATA-ERR 1453800200013 NO-DIM NO-DIM PC/FIS PER-CENT 1453800200014 38.0 89.0 4.72E-0 3.1 1453800200015 39.0 91.0 5.55E-0 4.9 1453800200016 40.0 95.0 6.49E-0 3.3 1453800200017 40.0 97.0 6.10E-0 4.8 1453800200018 42.0 99.0 5.96E-0 2.6 1453800200019 44.0 103.0 2.90E-0 4.2 1453800200020 47.0 111.0 1.71E-2 5.5 1453800200021 48.0 115.0 1.16E-2 14.2 1453800200022 49.0 131.0 2.84E-0 2.9 1453800200023 49.0 132.0 4.36E-0 3.4 1453800200024 55.0 136.0 5.46E-3 4.8 1453800200025 55.0 137.0 5.89E-0 3.3 1453800200026 57.0 140.0 6.24E-0 3.3 1453800200027 58.0 141.0 5.76E-0 3.9 1453800200028 58.0 143.0 6.03E-0 2.8 1453800200029 58.0 144.0 5.59E-0 7.7 1453800200030 60.0 147.0 2.29E-0 9.1 1453800200031 62.0 153.0 1.40E-1 3.3 1453800200032 63.0 156.0 1.46E-2 10.0 1453800200033 65.0 161.0 8.60E-5 4.8 1453800200034 ENDDATA 22 0 1453800200035 ENDSUBENT 34 0 1453800299999 SUBENT 14538003 20190603 14521453800300001 BIB 4 5 1453800300002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 1453800300003 STATUS (TABLE) Table 2 in Rad. Nucl. Chem.,296,763,2013. 1453800300004 SAMPLE (92-U-235,ENR=0.9311)+-0.00007, 427 mg 235U 1453800300005 COMMENT Value for EN-MEAN was taken by compiler from 1453800300006 E.C.Finn et al., J.Rad.Nucl.Chem.,306,79,2015. 1453800300007 ENDBIB 5 0 1453800300008 COMMON 1 3 1453800300009 EN-MEAN 1453800300010 KEV 1453800300011 700.0 1453800300012 ENDCOMMON 3 0 1453800300013 DATA 4 20 1453800300014 ELEMENT MASS DATA DATA-ERR 1453800300015 NO-DIM NO-DIM PC/FIS PER-CENT 1453800300016 38.0 89.0 4.42E-0 3.3 1453800300017 39.0 91.0 5.69E-0 12.2 1453800300018 40.0 95.0 6.20E-0 6.2 1453800300019 40.0 97.0 5.99E-0 7.2 1453800300020 42.0 99.0 6.11E-0 6.2 1453800300021 44.0 103.0 3.21E-0 5.7 1453800300022 47.0 111.0 3.66E-2 7.2 1453800300023 48.0 115.0 2.06E-2 1.8 1453800300024 49.0 131.0 3.07E-0 2.2 1453800300025 49.0 132.0 4.66E-0 2.9 1453800300026 55.0 136.0 9.78E-3 4.9 1453800300027 55.0 137.0 6.26E-0 8.2 1453800300028 57.0 140.0 6.06E-0 5.0 1453800300029 58.0 141.0 5.58E-0 8.7 1453800300030 58.0 143.0 5.66E-0 7.0 1453800300031 58.0 144.0 5.26E-0 5.9 1453800300032 60.0 147.0 2.14E-0 6.5 1453800300033 62.0 153.0 1.60E-1 8.9 1453800300034 63.0 156.0 2.12E-2 2.6 1453800300035 65.0 161.0 2.49E-4 6.0 1453800300036 ENDDATA 22 0 1453800300037 ENDSUBENT 36 0 1453800399999 ENDENTRY 3 0 1453899999999