Comparison of fast neutron spectra in graphite and FLINA salt inserted in well-defined core assembled in LR-0 reactor

Author(s)
Košťál, Michal; Veškrna, Martin; Cvachovec, František; Jánský, Bohumil; Novák, Evžen; ... Show more
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Comparison of fast neutron spectra in graphite and FLINA salt inserted in well-defined core assembled in LR-0 reactor
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Abstract
The present paper aims to compare the calculated and measured spectra after insertion of candidate materials for the Molten salt reactor/Fluoride cooled high temperature reactor system concept into the LR-0 reactor. The calculation is realized with MCNP6 code using ENDF/B-VII.0, JEFF-3.1, JENDL-3.3, JENDL-4, ROSFOND-2010 and CENDL-3.1 nuclear data libraries. Additionally, comparisons between the slowing down power of each media were performed. The slowing down properties are important parameters affecting the thickness of moderator media in a reactor.
Date issued
2015-05
URI
http://hdl.handle.net/1721.1/111160
Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Journal
Annals of Nuclear Energy
Publisher
Elsevier
Citation
Košťál, Michal et al. “Comparison of Fast Neutron Spectra in Graphite and FLINA Salt Inserted in Well-Defined Core Assembled in LR-0 Reactor.” Annals of Nuclear Energy 83 (September 2015): 216–225 © 2015 Elsevier Ltd
Version: Original manuscript
ISSN
0306-4549
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