ALLEGRO Gas-cooled Fast Reactor (GFR) demonstrator thermal hydraulic benchmark

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F19%3AN0000016" target="_blank" >RIV/46356088:_____/19:N0000016 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S0029549318310033" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0029549318310033</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.nucengdes.2019.02.006" target="_blank" >10.1016/j.nucengdes.2019.02.006</a>

Jazyk výsledku

angličtina

Název v původním jazyce

ALLEGRO Gas-cooled Fast Reactor (GFR) demonstrator thermal hydraulic benchmark

Popis výsledku v původním jazyce

The European gas cooled fast reactor (GFR) demonstrator, ALLEGRO, is currently being developed by Czech Republic, France, Hungary, Slovakia and Poland. The primary aim of ALLEGRO is to demonstrate the helium-cooled fast reactor technology and to test the new ceramic refractory fuel of the industrial version of the gas-cooled fast reactor, which has an envisaged thermal power of 2400 MW. The development of ALLEGRO highly relies on Thermal Hydraulic (TH) codes which were primarily developed for two-phase flow modelling of pressurized and boiling water reactors, and which are currently being adapted for new generation reactors using gas or liquid metal coolant. In this paper we present CATHARE2, RELAP5-3D and MELCOR code to code benchmark carried out for the 75 MWth ALLEGRO reactor. During our work, first an ALLEGRO database for TH analyses was elaborated based on previous European projects. In the second step a detailed TH benchmark specification was prepared in order to help the TH model development as a third step. Fourthly, each participant calculated their own steady states and subsequently we identified several model distortions. In the final step we carried out transient calculations for 3-inch Loss Of Coolant Accident (LOCA) and total Station Blackout (SBO) initiating events. In general, the results show that there is a good agreement in the simulation results of the different codes, but further experimental code validations are proposed using helium-cooled experimental facilities, namely the S-ALLEGRO being built in Czech Republic and the STU (Slovak University of Technology) loop operated in Slovakia.

Název v anglickém jazyce

ALLEGRO Gas-cooled Fast Reactor (GFR) demonstrator thermal hydraulic benchmark

Popis výsledku anglicky

The European gas cooled fast reactor (GFR) demonstrator, ALLEGRO, is currently being developed by Czech Republic, France, Hungary, Slovakia and Poland. The primary aim of ALLEGRO is to demonstrate the helium-cooled fast reactor technology and to test the new ceramic refractory fuel of the industrial version of the gas-cooled fast reactor, which has an envisaged thermal power of 2400 MW. The development of ALLEGRO highly relies on Thermal Hydraulic (TH) codes which were primarily developed for two-phase flow modelling of pressurized and boiling water reactors, and which are currently being adapted for new generation reactors using gas or liquid metal coolant. In this paper we present CATHARE2, RELAP5-3D and MELCOR code to code benchmark carried out for the 75 MWth ALLEGRO reactor. During our work, first an ALLEGRO database for TH analyses was elaborated based on previous European projects. In the second step a detailed TH benchmark specification was prepared in order to help the TH model development as a third step. Fourthly, each participant calculated their own steady states and subsequently we identified several model distortions. In the final step we carried out transient calculations for 3-inch Loss Of Coolant Accident (LOCA) and total Station Blackout (SBO) initiating events. In general, the results show that there is a good agreement in the simulation results of the different codes, but further experimental code validations are proposed using helium-cooled experimental facilities, namely the S-ALLEGRO being built in Czech Republic and the STU (Slovak University of Technology) loop operated in Slovakia.

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

—

Návaznosti

R - Projekt Ramcoveho programu EK

Rok uplatnění

2019

Kód důvěrnosti údajů

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

Název periodika

Nuclear Engineering and Design

ISSN

0029-5493

e-ISSN

1872-759X

Svazek periodika

345

Číslo periodika v rámci svazku

April

Stát vydavatele periodika

CH - Švýcarská konfederace

Počet stran výsledku

15

Strana od-do

47-61

Kód UT WoS článku

000460659300006

EID výsledku v databázi Scopus

2-s2.0-85061755603