All

What are you looking for?

All
Projects
Results
Organizations

Quick search

  • Projects supported by TA ČR
  • Excellent projects
  • Projects with the highest public support
  • Current projects

Smart search

  • That is how I find a specific +word
  • That is how I leave the -word out of the results
  • “That is how I can find the whole phrase”

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

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database

  • CEP classification

  • OECD FORD branch

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

Result continuities

  • Project

  • 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