The McSAFE project - High-performance Monte Carlo based methods for safety demonstration: From proof of concept to industry applications

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F20%3AN0000064" target="_blank" >RIV/46356088:_____/20:N0000064 - isvavai.cz</a>

Result on the web

<a href="https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_06004.pdf" target="_blank" >https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_06004.pdf</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1051/epjconf/202124706004" target="_blank" >10.1051/epjconf/202124706004</a>

Result language

angličtina

Original language name

The McSAFE project - High-performance Monte Carlo based methods for safety demonstration: From proof of concept to industry applications

Original language description

The increasing use of Monte Carlo methods for core analysis is fostered by the huge and cheap computer power available nowadays e.g. in large HPC. Apart from the classical criticality calculations, the application of Monte Carlo methods for depletion analysis and cross section generation for diffusion and transport core simulators is also expanding. In addition, the development of multi-physics codes by coupling Monte Carlo solvers with thermal hydraulic codes (CFD, subchannel and system thermal hydraulics) to perform full core static core analysis at fuel assembly or pin level has progressed in the last decades. Finally, the extensions of the Monte Carlo codes to describe the behavior of prompt and delay neutrons, control rod movements, etc. has been started some years ago. Recent coupling of dynamic versions of Monte Carlo codes with subchannel codes make possible the analysis of transient e.g. rod ejection accidents and it paves the way for the simulation of any kind of design basis accidents as an alternative option to the use of diffusion and transport based deterministic solvers. The H2020 McSAFE Project is focused on the improvement of methods for depletion considering thermal hydraulic feedbacks, extension of the coupled neutronic/thermal hydraulic codes by the incorporation of a fuel performance solver, the development of dynamic Monte Carlo codes and the development of methods to handle large depletion problems and to reduce the statistical uncertainty. The validation of the multi-physics tools developed within McSAFE will be performed using plant data and unique tests e.g. the SPERT III E REA test. This paper will describe the main developments, solution approaches, and selected results.

Czech name

—

Czech description

—

Type

D - Article in proceedings

CEP classification

—

OECD FORD branch

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

Project

—

Continuities

R - Projekt Ramcoveho programu EK

Publication year

2020

Confidentiality

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

Article name in the collection

International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020

ISBN

978-171382724-5

ISSN

—

e-ISSN

—

Number of pages

8

Pages from-to

943-950

Publisher name

EDP Sciences - Web of Conferences

Place of publication

—

Event location

Cambridge

Event date

Mar 28, 2020

Type of event by nationality

WRD - Celosvětová akce

UT code for WoS article

—