Review of experimental database to support nuclear power plant safety analyses in SGTR and LOCA domains
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F23%3AN0000020" target="_blank" >RIV/46356088:_____/23:N0000020 - isvavai.cz</a>
Výsledek na webu
<a href="https://www.sciencedirect.com/science/article/pii/S0306454923003201" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0306454923003201</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.anucene.2023.110001" target="_blank" >10.1016/j.anucene.2023.110001</a>
Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Review of experimental database to support nuclear power plant safety analyses in SGTR and LOCA domains
Popis výsledku v původním jazyce
In the framework of the EU R2CA project the available experimental databases were reviewed to support nuclear power plant safety analyses in SGTR and LOCA domains. The review focused on the phenomena related to fuel failure, fission products release from the fuel rods and activity transport up to the environment. Furthermore, it was shown that the phenomena were covered by different scale facilities and different experimental procedures for several reactor designs and materials. Among the tests several separate effect tests and integral tests are listed and some NPP measurements were also included. It was concluded that the reviewed database, which includes more than forty experimental programmes and measurement series can be considered as a reliable basis to support the development and validation of numerical models for SGTR and LOCA safety analyses.
Název v anglickém jazyce
Review of experimental database to support nuclear power plant safety analyses in SGTR and LOCA domains
Popis výsledku anglicky
In the framework of the EU R2CA project the available experimental databases were reviewed to support nuclear power plant safety analyses in SGTR and LOCA domains. The review focused on the phenomena related to fuel failure, fission products release from the fuel rods and activity transport up to the environment. Furthermore, it was shown that the phenomena were covered by different scale facilities and different experimental procedures for several reactor designs and materials. Among the tests several separate effect tests and integral tests are listed and some NPP measurements were also included. It was concluded that the reviewed database, which includes more than forty experimental programmes and measurement series can be considered as a reliable basis to support the development and validation of numerical models for SGTR and LOCA safety analyses.
Klasifikace
Druh
J<sub>imp</sub> - Článek v periodiku v databázi Web of Science
CEP obor
—
OECD FORD obor
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Návaznosti výsledku
Projekt
—
Návaznosti
R - Projekt Ramcoveho programu EK
Ostatní
Rok uplatnění
2023
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název periodika
Annals of Nuclear Energy
ISSN
0306-4549
e-ISSN
1873-2100
Svazek periodika
193
Číslo periodika v rámci svazku
December
Stát vydavatele periodika
GB - Spojené království Velké Británie a Severního Irska
Počet stran výsledku
12
Strana od-do
1-12
Kód UT WoS článku
001047340300001
EID výsledku v databázi Scopus
2-s2.0-85165619179