Design and construction rules for mechanical components of high-temperature, experimental and fusion nuclear installations: the RCC-MRx Code last edition

The very last edition of the RCC-MRx Code (Design and Construction Rules for Mechanical Components in high-temperature structures, experimental reactors and fusion reactors) was published end of 2018 by AFCEN, the French Association for the rules governing the Design, Construction and Operating Supe...

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Autores principales:	Jorge Enrique MUÑOZ GARCIA, Cécile PÉTESCH, Thierry LEBARBÉ, Dominique BONNE, Claude PASCAL, Martine BLAT
Formato:	article
Lenguaje:	EN
Publicado:	The Japan Society of Mechanical Engineers 2020
Materias:	codes and standards rcc-mrx code design research reactors high temperature structures fusion nuclear installations Mechanical engineering and machinery TJ1-1570
Acceso en línea:	https://doaj.org/article/6b63dd8c733e49df877cb58ca3236d39
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spelling	oai:doaj.org-article:6b63dd8c733e49df877cb58ca3236d392021-11-29T05:59:27ZDesign and construction rules for mechanical components of high-temperature, experimental and fusion nuclear installations: the RCC-MRx Code last edition2187-974510.1299/mej.20-00052https://doaj.org/article/6b63dd8c733e49df877cb58ca3236d392020-07-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/7/4/7_20-00052/_pdf/-char/enhttps://doaj.org/toc/2187-9745The very last edition of the RCC-MRx Code (Design and Construction Rules for Mechanical Components in high-temperature structures, experimental reactors and fusion reactors) was published end of 2018 by AFCEN, the French Association for the rules governing the Design, Construction and Operating Supervision of the Equipment Items for Nuclear installations. The RCC-MRx Code is a consistent set of technical rules to be applied on the design of research reactors (derived from the last edition ever of RCC-MX Code in 2008, code especially developed for the Jules Horowitz Reactor (JHR)), on high temperature structures (derived from the last edition ever of RCC-MR Code in 2007, code devoted to high temperature reactors, the ITER Vacuum Vessel and to the French Fast Breeder Reactors) and on Fusion reactors. The scope of the RCC-MRx Code is restricted to mechanical components of high temperature structures, Sodium Fast Reactors (SFR), Research Reactors and Fusion Reactors (ITER/DEMO), but the RCC-MRx Code can also be used for mechanical components of other types of nuclear installations, as the European Spallation Source Target (ESS) for example. This paper is presenting the content and organization of the last edition, the RCC-MRx Code 2018, and the recently incorporated feedback from users, such as ITER project, JHR (Jules Horowitz Reactor) in France, ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) project in France, PFBR project (Prototype Fast Breeder Reactor) developed by IGCAR (Indira Gandhi Centre for Atomic Research) in India, and MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) project in Belgium.Jorge Enrique MUÑOZ GARCIACécile PÉTESCHThierry LEBARBÉDominique BONNEClaude PASCALMartine BLATThe Japan Society of Mechanical Engineersarticlecodes and standardsrcc-mrx codedesignresearch reactorshigh temperature structuresfusionnuclear installationsMechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 7, Iss 4, Pp 20-00052-20-00052 (2020)
institution	DOAJ
collection	DOAJ
language	EN
topic	codes and standards rcc-mrx code design research reactors high temperature structures fusion nuclear installations Mechanical engineering and machinery TJ1-1570
spellingShingle	codes and standards rcc-mrx code design research reactors high temperature structures fusion nuclear installations Mechanical engineering and machinery TJ1-1570 Jorge Enrique MUÑOZ GARCIA Cécile PÉTESCH Thierry LEBARBÉ Dominique BONNE Claude PASCAL Martine BLAT Design and construction rules for mechanical components of high-temperature, experimental and fusion nuclear installations: the RCC-MRx Code last edition
description	The very last edition of the RCC-MRx Code (Design and Construction Rules for Mechanical Components in high-temperature structures, experimental reactors and fusion reactors) was published end of 2018 by AFCEN, the French Association for the rules governing the Design, Construction and Operating Supervision of the Equipment Items for Nuclear installations. The RCC-MRx Code is a consistent set of technical rules to be applied on the design of research reactors (derived from the last edition ever of RCC-MX Code in 2008, code especially developed for the Jules Horowitz Reactor (JHR)), on high temperature structures (derived from the last edition ever of RCC-MR Code in 2007, code devoted to high temperature reactors, the ITER Vacuum Vessel and to the French Fast Breeder Reactors) and on Fusion reactors. The scope of the RCC-MRx Code is restricted to mechanical components of high temperature structures, Sodium Fast Reactors (SFR), Research Reactors and Fusion Reactors (ITER/DEMO), but the RCC-MRx Code can also be used for mechanical components of other types of nuclear installations, as the European Spallation Source Target (ESS) for example. This paper is presenting the content and organization of the last edition, the RCC-MRx Code 2018, and the recently incorporated feedback from users, such as ITER project, JHR (Jules Horowitz Reactor) in France, ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) project in France, PFBR project (Prototype Fast Breeder Reactor) developed by IGCAR (Indira Gandhi Centre for Atomic Research) in India, and MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) project in Belgium.
format	article
author	Jorge Enrique MUÑOZ GARCIA Cécile PÉTESCH Thierry LEBARBÉ Dominique BONNE Claude PASCAL Martine BLAT
author_facet	Jorge Enrique MUÑOZ GARCIA Cécile PÉTESCH Thierry LEBARBÉ Dominique BONNE Claude PASCAL Martine BLAT
author_sort	Jorge Enrique MUÑOZ GARCIA
title	Design and construction rules for mechanical components of high-temperature, experimental and fusion nuclear installations: the RCC-MRx Code last edition
title_short	Design and construction rules for mechanical components of high-temperature, experimental and fusion nuclear installations: the RCC-MRx Code last edition
title_full	Design and construction rules for mechanical components of high-temperature, experimental and fusion nuclear installations: the RCC-MRx Code last edition
title_fullStr	Design and construction rules for mechanical components of high-temperature, experimental and fusion nuclear installations: the RCC-MRx Code last edition
title_full_unstemmed	Design and construction rules for mechanical components of high-temperature, experimental and fusion nuclear installations: the RCC-MRx Code last edition
title_sort	design and construction rules for mechanical components of high-temperature, experimental and fusion nuclear installations: the rcc-mrx code last edition
publisher	The Japan Society of Mechanical Engineers
publishDate	2020
url	https://doaj.org/article/6b63dd8c733e49df877cb58ca3236d39
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Design and construction rules for mechanical components of high-temperature, experimental and fusion nuclear installations: the RCC-MRx Code last edition

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