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

Kód výsledku v 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>

Výsledek na webu

<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>

Jazyk výsledku

angličtina

Název v původním jazyce

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

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

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

Popis výsledku anglicky

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.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

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

Projekt

Výsledek vznikl pri realizaci vícero projektů. Více informací v záložce Projekty.

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)<br>I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2019

Kód důvěrnosti údajů

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

Název periodika

Journal of Nuclear Engineering and Radiation Science

ISSN

2332-8983

e-ISSN

2332-8975

Svazek periodika

5

Číslo periodika v rámci svazku

3

Stát vydavatele periodika

US - Spojené státy americké

Počet stran výsledku

8

Strana od-do

1-8

Kód UT WoS článku

000470245100015

EID výsledku v databázi Scopus

2-s2.0-85070820456