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AFCEN RCC-MR : 2007

Superseded
Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

DESIGN AND CONSTRUCTION RULES FOR MECHANICAL COMPONENTS OF NUCLEAR INSTALLATIONS APPLICABLE TO HIGH TEMPERATURE STRUCTURES AND TO THE ITER VACUUM VESSEL
Superseded date

05-06-2016

Published date

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)
DocumentType
Standard
PublisherName
French Association for the Design, Construction and Operating Supervision of the Equipment for Electronuclear Boilers
Status
Superseded
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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