LOFA and LOUHS analysis on the energy well SMR using TRACE code
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F24%3A00371706" target="_blank" >RIV/68407700:21220/24:00371706 - isvavai.cz</a>
Result on the web
<a href="https://doi.org/10.1016/j.pnucene.2024.105054" target="_blank" >https://doi.org/10.1016/j.pnucene.2024.105054</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.pnucene.2024.105054" target="_blank" >10.1016/j.pnucene.2024.105054</a>
Alternative languages
Result language
angličtina
Original language name
LOFA and LOUHS analysis on the energy well SMR using TRACE code
Original language description
The removal of decay heat is the key to the management of nuclear reactor accidents. For a concept of a small modular reactor Energy Well (EW), some of the most severe possible accidents would be loss of flow (LOFA) and also LOFA with the loss of ultimate heat sink (LOUHS). EW is a fluoride salt-cooled high-temperature reactor (FHR) with TRISO microparticles fuel in carbon matrix, molten salt FLiBe as a coolant and a graphite moderator. Some of its key features are a seven-year fuel cycle with fuel exchange off-site, easy transportability, and power plant modularity, all of which makes it an interesting contender among the energy sources of the near future. In order to assess the temperatures in key points of the EW primary circuit during the aforementioned accident scenarios, the EW model in thermohydraulic code TRACE was adjusted and scenarios with the trip of one through six pumps were modelled for both LOFA and LOFA with LOUHS. The point was to investigate whether any of these scenarios would cause failure of the primary circuit components, such as the fuel cladding, reactor vessel, or the surrounding concrete. None of the safety criteria were exceeded.
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - 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);
Result continuities
Project
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Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Others
Publication year
2024
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Name of the periodical
Progress in Nuclear Energy
ISSN
0149-1970
e-ISSN
1878-4224
Volume of the periodical
169
Issue of the periodical within the volume
4
Country of publishing house
US - UNITED STATES
Number of pages
7
Pages from-to
1-7
UT code for WoS article
001169935000001
EID of the result in the Scopus database
2-s2.0-85184779117