Sensitivity/uncertainty analyses comparing LR-0 reactor experiments containing FLiBe salt with models for molten-salt-cooled and molten-salt-fueled reactors

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000018" target="_blank" >RIV/26722445:_____/18:N0000018 - isvavai.cz</a>

Result on the web

<a href="http://dx.doi.org/10.1016/j.anucene.2018.05.052" target="_blank" >http://dx.doi.org/10.1016/j.anucene.2018.05.052</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.anucene.2018.05.052" target="_blank" >10.1016/j.anucene.2018.05.052</a>

Result language

angličtina

Original language name

Sensitivity/uncertainty analyses comparing LR-0 reactor experiments containing FLiBe salt with models for molten-salt-cooled and molten-salt-fueled reactors

Original language description

Critical experiments using an insertion zone with FLiBe salt performed at the LR-0 reactor at Research Centre (sic)e(sic) (RC (sic)e(sic)) have been compared to application models for solid-fueled, fluoride-salt-cooled high-temperature reactor (FHR) and liquid-fueled molten salt reactor (MSR) concepts using sensitivity and uncertainty (S/U) analysis techniques. These experiments support FHR and MSR advanced reactor concepts by informing on neutron spectral effects and nuclear data uncertainties related to fluoride salts. The FLiBe salt in the LR-0 experiments is from the Oak Ridge National Laboratory Molten Salt Reactor Experiment and is enriched to greater than 99.99% Li-7. This work is part of a broader collaboration between the United States and the Czech Republic on MSR and FHR technology. Results from the S/U analyses for FHR and MSR models indicated the most significant potential source of eigenvalue bias due to nuclear data within the FLiBe salt is radiative capture in Li-7 Other smaller but potentially significant contributions come from F-19, Li-6, and other Li-7 reactions. Similarity comparisons of the RC (sic)e(sic) LR-0 experiments and FHR and MSR application models indicate that the LR-0 FLiBe experiments could be useful as candidate benchmarks for low-enriched uranium-fueled application models. However, sensitivity differences observed included both spectral effects, due to the LR-0 reactor being moderated by water instead of graphite and fluoride salt, and sensitivity magnitude effects driven by the amount of FLiBe inserted and its location. New experiments with refined designs to increase the volume and importance of salt in the system could provide improved data. Results also demonstrate that salt systems using thorium and/or U-233 fuel will require additional experiments with relevant driver fuels. Increased contributions from the graphite moderator and F-19 and covariance between reactions such as U-233 fission and U-233 radiative capture indicate higher uncertainty contributions from the salt and significant differences in contributions from the fuel species due to underlying uncertainties in their nuclear data.

Czech name

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Czech description

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Type

J_imp - Article in a specialist periodical, which is included in the Web of Science database

CEP classification

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OECD FORD branch

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Project

Result was created during the realization of more than one project. More information in the Projects tab.

Continuities

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year

2018

Confidentiality

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Name of the periodical

Annals of Nuclear Energy

ISSN

0306-4549

e-ISSN

—

Volume of the periodical

120

Issue of the periodical within the volume

October

Country of publishing house

GB - UNITED KINGDOM

Number of pages

4

Pages from-to

319-322

UT code for WoS article

000441485700029

EID of the result in the Scopus database

2-s2.0-85048553612