Simulation of a NuScale core design with the CASL VERA code

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F21%3A00345792" target="_blank" >RIV/68407700:21340/21:00345792 - isvavai.cz</a>

Result on the web

<a href="https://doi.org/10.1016/j.nucengdes.2020.110956" target="_blank" >https://doi.org/10.1016/j.nucengdes.2020.110956</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.nucengdes.2020.110956" target="_blank" >10.1016/j.nucengdes.2020.110956</a>

Result language

angličtina

Original language name

Simulation of a NuScale core design with the CASL VERA code

Original language description

Three-dimensional (3D) full-core calculations are an integral part of fuel reload design for today’s light water reactors (LWRs). The current approaches are typically based on the nodal diffusion codes that calculate criticality state points and power distributions as a function of burnup. The CASL VERA (Consortium for Advanced Simulation of Light Water Reactors, Virtual Environment for Reactor Applications) code represents one of the latest advancements in 3D full-core calculation analysis based on transport theory methods employing the Method of Characteristics (MOC) and coupled multi-physics. In this article, a publicly released version of the NuScale reactor core is analysed with the VERA code (version 3.9 and 4.1) and contrasted against some static Serpent and Polaris based simulations. The analysis shows an excellent agreement for the lattice-level calculations as well as with some of the 3D full-core models. However, larger deviations were found in cases with heavy reflector models, whereby the reflector composition was found to impact the differences between the VERA and Serpent results. In this analysis, it was determined that greater than 90% stainless steel content in the heavy reflector leads to higher deviations between the VERA results and the Serpent results. The burnup calculations showed that the presence of the heavy reflector extends the cycle length and also leads to a flatter power distribution in the core, which can generally be interpreted as more efficient.

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

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OECD FORD branch

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

Project

<a href="/en/project/EF16_013%2F0001790" target="_blank" >EF16_013/0001790: Strengthening and development of research at Czech Technical University in Prague with the use of research infrastructure VR?1 Training Reactor for research activities</a><br>

Continuities

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year

2021

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

371

Issue of the periodical within the volume

110956

Country of publishing house

NL - THE KINGDOM OF THE NETHERLANDS

Number of pages

9

Pages from-to

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UT code for WoS article

000604781300007

EID of the result in the Scopus database

2-s2.0-85097091168