AFCEN RCC-MR : 2007
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by
DESIGN AND CONSTRUCTION RULES FOR MECHANICAL COMPONENTS OF NUCLEAR INSTALLATIONS APPLICABLE TO HIGH TEMPERATURE STRUCTURES AND TO THE ITER VACUUM VESSEL
05-06-2016
12-01-2013
SECTION 1 - NUCLEAR INSTALLATION COMPONENTS
SECTION 2 - MATERIALS
SECTION 3 - EXAMINATION METHODS
SECTION 4 - WELDING
SECTION 5 - FABRICATION
Applicable by Manufacturer or Supplier for components, particularly components considered to be important in terms of nuclear safety. Initially developed for Sodium Fast Reactors (SFR), applicable for structures operating under high temperature but it can also be used for the design of other nuclear facilities such as the ITER vacuum vessel. The use of the RCC-MR design and construction code in the context of contractual relations between customer and supplier is based on a list of components to which the code applies.
| DevelopmentNote |
Incorporated into AFCEN RCC-MRX, but remains Active & Available. (10/2015)
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| DocumentType |
Standard
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| PublisherName |
French Association for the Design, Construction and Operating Supervision of the Equipment for Electronuclear Boilers
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| Status |
Superseded
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| SupersededBy |
| ASME STP-NU-039 : 2012 | CREEP AND CREEP-FATIGUE CRACK GROWTH AT STRUCTURAL DISCONTINUITIES AND WELDS |
| ASME STP-NU-041 : 2011 | UPDATE AND IMPROVE SUBSECTION NH - ALTERNATIVE SIMPLIFIED CREEP-FATIGUE DESIGN METHODS |
| ASME STP-PT-070 : 2014 | Design Guidelines for the Effects of Creep, Fatigue & Creep-Fatigue Interaction with Design-By-Analysis and Nondestructive Inspection Acceptance Criteria (STP-PT-070 - 2014) |
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