Study of graphite reactivity worth on well-defined cores assembled on LR-0 reactor
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Forget_Study of granite.pdf
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Author(s) • • • • • •
Košťál, Michal
Rypar, Vojtěch
Milčák, Ján
Juříček, Vlastimil
Losa, Evžen
Harper, Sterling
Forget, Benoit Robert Yves
Date Issued
November 2015
Journal
Annals of Nuclear Energy
Publisher
Elsevier
Citation
Košťál, Michal et al. “Study of Graphite Reactivity Worth on Well-Defined Cores Assembled on LR-0 Reactor.” Annals of Nuclear Energy 87 (January 2016): 601–611 © 2015 Elsevier Ltd
Version
Author's final manuscript
Abstract
Graphite is an often-used moderating material on the basis of its good moderating power and very low absorption cross section. This small absorption cross section permits the use of natural or low-enriched uranium in graphite moderated reactors. Graphite is now being considered as the moderator for Fluoride-salt-cooled High Temperature Reactors (FHR). The critical moderator level was measured for various graphite block Keywords
LR-0 Graphite
FHR
Reactivity worth measurementconfigurations in an experimental dry assembly of the LR-0 reactor. Comparisons with experiments were performed between Monte Carlo simulation tools for which satisfactory agreement was obtained with the exception of some systematic discrepancies. The larger discrepancies were observed when using the ENDF/B-VII.0 library. To decrease the uncertainties, based on conservative assumptions, relative comparisons were done. The results provided by the different nuclear data libraries are within 3 sigma interval of experimental uncertainties. It has been determined that differences between the results of calculations are caused by variations in the (n,n), (n,n′), (n,g) reactions and also by various angular distributions, while the (n,g) cross section variations play only a minor role for these configurations.
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
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DOI of Published Version
https://doi.org/10.1016/J.ANUCENE.2015.10.010