SubChanFlow and VIPRE codes benchmark for VVER-1000

Result code in 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>

Alternative codes found

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

Result on the web

<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>

Result language

angličtina

Original language name

SubChanFlow and VIPRE codes benchmark for VVER-1000

Original language description

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.

Czech name

—

Czech description

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Type

J_imp - 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);

Project

—

Continuities

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Publication year

2024

Confidentiality

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

Name of the periodical

Nuclear Engineering and Design

ISSN

0029-5493

e-ISSN

1872-759X

Volume of the periodical

418

Issue of the periodical within the volume

March

Country of publishing house

CH - SWITZERLAND

Number of pages

7

Pages from-to

1-7

UT code for WoS article

001170675900001

EID of the result in the Scopus database

2-s2.0-85183457456