arrow
Return

RELAP5-3D System Thermal-Hydraulics Code Adequacy for MYRRHA Safety Analyses

delete2026-02-01
delete0
PRE
AI
T
Tewfik Hamidouche *
F
Fernandez, Rafael
DOI:10.1080/00295450.2025.2603571delete
deleteOriginal
deleteOriginal request for help
deleteShare
deleteSave
Abstract

Abstract

En 中文
RELAP5-3D is a widely used system thermal-hydraulic (STH) code for safety analysis of light water reactors. It has been extended to 26 other working fluids, including lead and lead-bismuth (LBE), enabling its application in the design and safety of advanced reactors such as the MYRRHA reactor, which uses molten LBE as its primary coolant. This justifies its selection as a main STH code for MYRRHA safety analysis. However, to anticipate its acceptance for the facility licensing, a thorough verification and validation (V&V) of the code is essential. This paper presents the methodology developed for the RELAP5-3D code V&V in the context of MYRRHA safety analyses. The code is assessed, focusing on important phenomena that determine the evolution of the key figure of merit (FoM) for design basis accidents, that is, the cladding behavior. A validation matrix has been established which includes separate test effects and integral test effects facilities, including scaled facilities. Selected results are presented and important phenomena for the FoM which require code enhancement are highlighted.
Keywords:
RELAP5-3D
LBE
LFR
STH code
MYRRHA
verification and validation
figure of merit

Journal

N
Nuclear Technology
IF:
2
Papers:
231
Citations:
4.2K

Organization

B
belgian nuclear research centre (sck cen)
Scholars:
1.2K
Papers: 1.1K
Citations: 0