SubChanFlow and VIPRE codes benchmark for VVER-1000

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F24%3AN0000052" target="_blank" >RIV/26722445:_____/24:N0000052 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/46356088:_____/24:N0000020 RIV/86652052:_____/24:N0000020

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S0029549324000384" target="_blank" >https://www.sciencedirect.com/science/article/pii/S0029549324000384</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.nucengdes.2024.112936" target="_blank" >10.1016/j.nucengdes.2024.112936</a>

Jazyk výsledku

angličtina

Název v původním jazyce

SubChanFlow and VIPRE codes benchmark for VVER-1000

Popis výsledku v původním jazyce

Computational codes that simulate steady -states and transients in nuclear reactors are key to supporting the safety of nuclear power plants not only for today's, but also for future projects, such as SMRs. At the same time, they contribute to increasing efficiency by using the project reserves of power plants. Computational tools perform simulation of various physical phenomena of a nuclear reactor. One of the advanced simulation tools are subchannel codes. The subchannel analysis approach is a proven method for the determination of safety criteria margins, resulting in key thermohydraulic parameters of the nuclear reactor, such as the departure from the nucleate boiling ratio. This research simulated a steady state and transient event (loss of flow accident) in the pressurized water reactor VVER-1000, using the codes SubChanFlow 3.5 and VIPRE-01 for one fuel assembly. The results were subsequently compared as a benchmark. Boundary conditions were calculated using data from the VVER-1000 nuclear power plant model in TRACE code. In general, SubChanFlow has been shown to be more conservative than VIPRE and can be used to evaluate and compare future analysis of various transients. Two independent models were developed to simulate the LOFA scenario, taking into account code differences. In general, the differences in the results can be explained by the different approaches of the crossflow models in the subchannel codes. Nevertheless, the departure from nucleate boiling ratio was calculated using the OKB correlation and the results did not exceed the safety limit criteria.

Název v anglickém jazyce

SubChanFlow and VIPRE codes benchmark for VVER-1000

Popis výsledku anglicky

Computational codes that simulate steady -states and transients in nuclear reactors are key to supporting the safety of nuclear power plants not only for today's, but also for future projects, such as SMRs. At the same time, they contribute to increasing efficiency by using the project reserves of power plants. Computational tools perform simulation of various physical phenomena of a nuclear reactor. One of the advanced simulation tools are subchannel codes. The subchannel analysis approach is a proven method for the determination of safety criteria margins, resulting in key thermohydraulic parameters of the nuclear reactor, such as the departure from the nucleate boiling ratio. This research simulated a steady state and transient event (loss of flow accident) in the pressurized water reactor VVER-1000, using the codes SubChanFlow 3.5 and VIPRE-01 for one fuel assembly. The results were subsequently compared as a benchmark. Boundary conditions were calculated using data from the VVER-1000 nuclear power plant model in TRACE code. In general, SubChanFlow has been shown to be more conservative than VIPRE and can be used to evaluate and compare future analysis of various transients. Two independent models were developed to simulate the LOFA scenario, taking into account code differences. In general, the differences in the results can be explained by the different approaches of the crossflow models in the subchannel codes. Nevertheless, the departure from nucleate boiling ratio was calculated using the OKB correlation and the results did not exceed the safety limit criteria.

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

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2024

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

418

Číslo periodika v rámci svazku

March

Stát vydavatele periodika

CH - Švýcarská konfederace

Počet stran výsledku

7

Strana od-do

1-7

Kód UT WoS článku

001170675900001

EID výsledku v databázi Scopus

2-s2.0-85183457456