Abstract
Prior work has demonstrated the use of a natural B4C capsule for spectral-tailoring in a mixed spectrum reactor as an alternate and complementary method to critical assemblies for performing nuclear data measurements at near 235U fission-energy neutron spectrum. Previous fission product measurements showed that the neutron spectrum achievable with natural B4C was not as hard as what can be achieved with critical assemblies. New measurements performed with the Washington State University TRIGA reactor using a B4C capsule 96 % enriched in 10B resulted in a neutron spectrum very similar to a critical assembly and a pure 235U fission spectrum. Fission product yields measured following an irradiation of a sample with this new method and subsequent radiochemical separations are presented here.
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References
Greenwood LR, Wittman R, Pierson BD, Metz LA, Payne RF, Finn EC, Friese JI (2012) Design and testing of a boron carbide capsule for spectral tailoring in mixed-spectrum reactors. J ASTM Int. doi:10.1520/JAI103959
Selby HD, Mac Innes MR, Barr DW, Keksis AL, Meade RA, Burns CJ, Chadwick MB, Wallstrom TC (2010) Fission product data measured at Los Alamos for fission spectrum and thermal neutrons on 239Pu, 235U, 238U. Nucl Data Sheets 111:2891–2922
Chadwick MB, Kawano T, Barr DW, Mac Innes MR, Kahler AC, Graves T, Selby H, Burns CJ, Inkret WC, Keksis AL, Lestone JP, Sierk AJ, Talou P (2010) Fission product yields from fission spectrum n + 239Pu for ENDF/B-VII.1. Nucl Data Sheets 111:2923–2964
Finn EC, Greenwood LR, Wittman R, Pierson BD, Metz LA, Kephart RF, Friese JI (2015) Cumulative fission yields of short-lived isotopes under natural-abundance-boron-carbide-moderated neutron spectrum. J Radioanal Nucl Chem. doi:10.1007/s10967-015-4085-6
Metz LA, Friese JI, Finn EC, Greenwood LR, Kephart RF, Hines CC, King MD, Henry KM, Wall DE (2012) Fission yield measurements from highly enriched uranium irradiated inside a boron carbide capsule. J Radioanal Nucl Chem. doi:10.1007/s10967-012-2089-z
Greenwood LR, Wittman R, Metz LA, Finn EC, Friese JI (2014) Design and testing of a 10B4C capsule for spectral tailoring in mixed-spectrum reactors. Nucl Instrum Methods Phys Res A 743:121–123
Greenwood LR, Johnson CD (2013) User guide for the STAYSL PNNL suite of software tools. PNNL-22253, Pacific Northwest National Laboratory, Richland, Washington
England TR, Rider BF (1994) Evaluation and compilation of fission product yields. LA-UR-94-3106, ENDF-349, Los Alamos National Laboratory, Los Alamos, New Mexico
Acknowledgments
The work was funded by the Office of Defense Nuclear Nonproliferation Research and Development within the U.S. Department of Energy’s National Nuclear Security Administration and by Pacific Northwest National Laboratory which is operated by Battelle Memorial Institute for the U.S. Department of Energy under contract DE-AC05-76RLO1830.
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Metz, L.A., Friese, J.I., Finn, E.C. et al. Fission products measured from highly-enriched uranium irradiated under 10B4C in a research reactor. J Radioanal Nucl Chem 307, 2321–2326 (2016). https://doi.org/10.1007/s10967-015-4437-2
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DOI: https://doi.org/10.1007/s10967-015-4437-2