FUEL+ simulation of the HALDEN LOCA test IFA-650.10
Year: 2025
Type: article
Abstract: FUEL+ is a software platform developed by the French Nuclear Safety and Radioprotection Authority (ASNR) with the objective of modelling the behaviour of nuclear fuel in normal, incidental, and accidental operational conditions, as well as during its storage in deactivation pools and its transportation for reprocessing. To achieve this, the platform brings together several simulation codes and notably eases their coupling. It models the main thermomechanical, thermochemical, and thermohydraulic phenomena occurring within and around nuclear fuel and its cladding at the scale of the fuel rod, assembly, or reactor core. This paper presents the simulation with the FUEL+ platform of the HALDEN LOCA test IFA-650.10, including: − A base irradiation calculation of the father rod used to reprocess the rod sample used in the test IFA-650.10 with the FUEL+/FIRST code. − An irradiation calculation of the rod sample in the HALDEN reactor before the LOCA test with the FUEL+/FIRST code. − The LOCA transient calculation itself using the FUEL+/DRACCAR code. − The cladding hydriding evaluation using the FUEL+/SHOWBIZ code coupled to the FUEL+/DRACCAR code. The calculation results are in good agreement with the experimental one, the cladding temperature evolution, burst time and maximal strain being well predicted by the FUEL+/DRACCAR code.
Source: Nuclear Engineering and Design
Authors: T. Glantz, S. Belon, M. Salvo, M. Guemas
Institution: Autorité de sûreté nucléaire et de radioprotection
Language: English
Subfield: Materials Chemistry
Field: Materials Science
Domain: Physical Sciences
Open Access status: hybrid
Estimated APC paid: $2,710
OpenAlex ID: W4413365170