Work

Analysis of Rod Ejection Accident in a Research Reactor by the Coupled Technique

Year: 2009

Type: conference-paper

Abstract: This paper investigates the possibility to extend standard computer tools and methods, commonly used in the safety technology of nuclear power reactors, to research reactor safety analysis. A 3-D Neutron Kinetics Thermal-Hydraulic code (3D-NKTH), based on coupling PARCS and RELAP5/3.3 codes, was developed for a standard Material Test Reactor (MTR). The assessment of the model has been performed by comparison of steady state calculations against conventional diffusion codes and Monte Carlo code results. The model is applied for the analysis of a rod ejection accident. The comparison of the 3D-NKTH code, with conventional conservative research reactor tools showed that 3D-NKTH provided a more realistic course of the accident and did not require to define hot channel parameters. This approach could also open new frontiers in the safety analysis of research reactor such as setting realistic safety margin and adequate limits and operation conditions for optimal utilization of research reactors.

Source: The Proceedings of the International Conference on Nuclear Engineering (ICONE)

DOI: 10.1115/icone17-75211

Authors: Tewfik Hamidouche, El Khider Si-Ahmed, Anis Bousbia-Salah, Jack Legrand

Institutions: Centre de Recherche Nucléaire d’Alger, University of Sciences and Technology Houari Boumediene, University of Pisa, Centre National de la Recherche Scientifique, Laboratoire de Génie des Procédés – Environnement – Agro-alimentaire, Université de Nantes, Nantes Université

Language: English

Topic: Nuclear Engineering Thermal-Hydraulics

Subfield: Nuclear Energy and Engineering

Field: Energy

Domain: Physical Sciences

Open Access status: diamond

Funder: International Atomic Energy Agency

OpenAlex ID: W2074094561

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