Overview
ABSTRACT
The development of new reactor concepts (Generation IV or fusion reactors) is a major challenge of the coming decades. These new reactors bring new challenges (environments, loads) and development of new innovative materials and associated technologies. The transition from an experimental to an industrial dimension of these concepts can be accelerated by incorporating these developments into a standardization approach. It requires to work on technical documentations – design and fabrication codes, standards (so called technical references) used by the industry. This article aims to present how this work has been and is being carried out on the main materials used for innovative nuclear installations in France through an industrial standard, RCC-MRx code.
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Read the articleAUTHORS
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Cécile PETESCH: Research engineer - Commissariat à l'énergie atomique et aux énergies alternatives, Centre de Saclay, France
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Martine BLAT YRIEIX: Research engineer - EDF R&D, Materials and Component Mechanics Department, Les Renardières, France
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Jérôme GARNIER: Research engineer - Commissariat à l'énergie atomique et aux énergies alternatives, Centre de Saclay, France
INTRODUCTION
The development of new techniques and technologies depends to a large extent on the ability of materials to perform satisfactorily in use and in service. This is particularly true in the nuclear power industry, where high levels of safety, reliability and longevity are essential.
The aim of this article is to present the main materials used in innovative nuclear installations, which have been valorized through an industrial standard, the RCC-MRx code published by AFCEN. The installations concerned are those currently covered by the code's scope of application, namely sodium-cooled fast reactors (RNR-Na), experimental reactors such as the Jules Horowitz reactor (RJH) and fusion installations. It should be noted that the RCC-MRx is the counterpart of another code, the RCC-M, also published by AFCEN, and dedicated to the design of mechanical components for pressurized water reactors.
The article is in two parts:
firstly, a description of the main structural materials introduced into the RCC-MRx repository, based on feedback from the design and construction of the above-mentioned reactors;
secondly, the process used to codify them.
From these three different types of installation, it is clear that the approach used to codify a material needs to be adapted, depending on the material's experience in the target environment.
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KEYWORDS
fast neutrons reactor | ITER | RCC-MRx | Jules Horowitz Reactor
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- Metallic materials — Tensile test — Part 1: Room temperature test method. - EN ISO 6892-1 - 2019
- Metallic materials — Tensile test — Part 2: Elevated temperature test method. - EN ISO 6892-2 - 2018
- Méthode de dérivation des valeurs minimales de la limite conventionnelle d'élasticité des aciers à températures élevées. - EN 10314 - 2016
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