ENTRY 14538 20240206 1453800000001 SUBENT 14538001 20240206 20250110 1453800100001 BIB 12 40 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 (20240206A) BP: Corrected 131,132In to 131,132I, or 1453800100041 Z=49 to 53 in subentries 2,3. 1453800100042 ENDBIB 40 0 1453800100043 NOCOMMON 0 0 1453800100044 ENDSUBENT 43 0 1453800199999 SUBENT 14538002 20240206 20250110 1453800200001 BIB 4 6 1453800200002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 1453800200003 STATUS (TABLE,,L.A.Metz+,J,JRN,296,763,2013) 1453800200004 Table 2 in Rad. Nucl. Chem.,296,763,2013. 1453800200005 SAMPLE (92-U-235,ENR=0.9311) +-0.00007, 109 Mg 235U 1453800200006 HISTORY (20240206C) BP: Corrected 131,132In to 131,132I, or 1453800200007 Z=49 to 53. 1453800200008 ENDBIB 6 0 1453800200009 COMMON 1 3 1453800200010 EN-DUMMY 1453800200011 EV 1453800200012 0.0253 1453800200013 ENDCOMMON 3 0 1453800200014 DATA 4 20 1453800200015 ELEMENT MASS DATA DATA-ERR 1453800200016 NO-DIM NO-DIM PC/FIS PER-CENT 1453800200017 38.0 89.0 4.72E-0 3.1 1453800200018 39.0 91.0 5.55E-0 4.9 1453800200019 40.0 95.0 6.49E-0 3.3 1453800200020 40.0 97.0 6.10E-0 4.8 1453800200021 42.0 99.0 5.96E-0 2.6 1453800200022 44.0 103.0 2.90E-0 4.2 1453800200023 47.0 111.0 1.71E-2 5.5 1453800200024 48.0 115.0 1.16E-2 14.2 1453800200025 53.0 131.0 2.84E-0 2.9 1453800200026 53.0 132.0 4.36E-0 3.4 1453800200027 55.0 136.0 5.46E-3 4.8 1453800200028 55.0 137.0 5.89E-0 3.3 1453800200029 57.0 140.0 6.24E-0 3.3 1453800200030 58.0 141.0 5.76E-0 3.9 1453800200031 58.0 143.0 6.03E-0 2.8 1453800200032 58.0 144.0 5.59E-0 7.7 1453800200033 60.0 147.0 2.29E-0 9.1 1453800200034 62.0 153.0 1.40E-1 3.3 1453800200035 63.0 156.0 1.46E-2 10.0 1453800200036 65.0 161.0 8.60E-5 4.8 1453800200037 ENDDATA 22 0 1453800200038 ENDSUBENT 37 0 1453800299999 SUBENT 14538003 20240206 20250110 1453800300001 BIB 5 8 1453800300002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 1453800300003 STATUS (TABLE,,L.A.Metz+,J,JRN,296,763,2013) 1453800300004 Table 2 in Rad. Nucl. Chem.,296,763,2013. 1453800300005 SAMPLE (92-U-235,ENR=0.9311)+-0.00007, 427 Mg 235U 1453800300006 COMMENT Value for en-mean was taken by compiler from 1453800300007 E.C.Finn et al., J.Rad.Nucl.Chem.,306,79,2015. 1453800300008 HISTORY (20240206C) BP: Corrected 131,132In to 131,132I, or 1453800300009 Z=49 to 53. 1453800300010 ENDBIB 8 0 1453800300011 COMMON 1 3 1453800300012 EN-MEAN 1453800300013 KEV 1453800300014 700.0 1453800300015 ENDCOMMON 3 0 1453800300016 DATA 4 20 1453800300017 ELEMENT MASS DATA DATA-ERR 1453800300018 NO-DIM NO-DIM PC/FIS PER-CENT 1453800300019 38.0 89.0 4.42E-0 3.3 1453800300020 39.0 91.0 5.69E-0 12.2 1453800300021 40.0 95.0 6.20E-0 6.2 1453800300022 40.0 97.0 5.99E-0 7.2 1453800300023 42.0 99.0 6.11E-0 6.2 1453800300024 44.0 103.0 3.21E-0 5.7 1453800300025 47.0 111.0 3.66E-2 7.2 1453800300026 48.0 115.0 2.06E-2 1.8 1453800300027 53.0 131.0 3.07E-0 2.2 1453800300028 53.0 132.0 4.66E-0 2.9 1453800300029 55.0 136.0 9.78E-3 4.9 1453800300030 55.0 137.0 6.26E-0 8.2 1453800300031 57.0 140.0 6.06E-0 5.0 1453800300032 58.0 141.0 5.58E-0 8.7 1453800300033 58.0 143.0 5.66E-0 7.0 1453800300034 58.0 144.0 5.26E-0 5.9 1453800300035 60.0 147.0 2.14E-0 6.5 1453800300036 62.0 153.0 1.60E-1 8.9 1453800300037 63.0 156.0 2.12E-2 2.6 1453800300038 65.0 161.0 2.49E-4 6.0 1453800300039 ENDDATA 22 0 1453800300040 ENDSUBENT 39 0 1453800399999 ENDENTRY 3 0 1453899999999