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Assessment of the TRACE code for the he-cooled systems simulation capability against some He-FUS3 experimental measurements

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F19%3AN0000017" target="_blank" >RIV/26722445:_____/19:N0000017 - isvavai.cz</a>

  • Result on the web

    <a href="https://asmedigitalcollection.asme.org/nuclearengineering/article-abstract/5/3/030914/725871/Assessment-of-the-TRACE-Code-for-the-He-Cooled?redirectedFrom=fulltext" target="_blank" >https://asmedigitalcollection.asme.org/nuclearengineering/article-abstract/5/3/030914/725871/Assessment-of-the-TRACE-Code-for-the-He-Cooled?redirectedFrom=fulltext</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1115/1.4043377" target="_blank" >10.1115/1.4043377</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Assessment of the TRACE code for the he-cooled systems simulation capability against some He-FUS3 experimental measurements

  • Original language description

    This paper focuses on the TRACE code assessment for helium-cooled systems thermal-hydraulic analysis. In the frame of the GoFastR (gas cooled fast reactor) European Collaborative Project, ENEA has offered some selected experimental data for the organization of a benchmark exercise aimed at the validation of the system and CFD codes for the gas reactor transient analyses. One of the Research Center Rez teams participated in it with a CFD code application. Now, the experimental data are used in order to assess the TRACE code for the ongoing high-temperature helium loop (HTHL-2) licensing process. The results of the TRACE calculations agreed very well with the experimental measurements (often within the experimental uncertainties) data provided by the He-FUS3 facility, indicating that the code, despite developed for water coolant applications, if an appropriately tuned input is adopted, it can also be suitable for reasonably accurate gas technology thermo-hydraulic simulations.

  • 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

    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)<br>I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Others

  • Publication year

    2019

  • Confidentiality

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

Data specific for result type

  • Name of the periodical

    Journal of Nuclear Engineering and Radiation Science

  • ISSN

    2332-8983

  • e-ISSN

    2332-8975

  • Volume of the periodical

    5

  • Issue of the periodical within the volume

    3

  • Country of publishing house

    US - UNITED STATES

  • Number of pages

    8

  • Pages from-to

    1-8

  • UT code for WoS article

    000470245100015

  • EID of the result in the Scopus database

    2-s2.0-85070820456