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CSA N285.8 : 2015

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

TECHNICAL REQUIREMENTS FOR IN-SERVICE EVALUATION OF ZIRCONIUM ALLOY PRESSURE TUBES IN CANDU REACTORS

Available format(s)

Hardcopy , PDF

Superseded date

18-07-2020

Language(s)

English, French

Published date

01-01-2015

€4,405.85
Excluding VAT

Preface
1 Scope
2 Reference publications
3 Definitions, symbols, and abbreviations
4 General requirements
5 Evaluation of pressure tube flaws
6 Evaluation of pressure tube to calandria tube contact
7 Assessment of reactor core
8 Evaluation of material surveillance measurements
Annex A (informative) - Procedures for the evaluation of
        pressure tube flaws
Annex B (informative) - Procedures for the evaluation of
        pressure tube to calandria tube contact
Annex C (informative) - Procedures for the assessment of
        a reactor core
Annex D (informative) - Material properties and derived
        quantities
Annex E (informative) - Notification of in-service
        evaluation form

This Standard specifies the technical requirements for the owner/operator to ensure structural integrity of cold-worked Zr-2.5 wt% Nb alloy pressure tubes in operating CANDU reactors.


DevelopmentNote
French Edition issued on 01-03-2018. (03/2018) This standard is revised in October 2019
DocumentType
Standard
ISBN
978-1-77139-908-1
Pages
261
ProductNote
This standard is revised in October 2019
PublisherName
Canadian Standards Association
Status
Superseded
Supersedes

CSA N285.0 : 2006 GENERAL REQUIREMENTS FOR PRESSURE-RETAINING SYSTEMS AND COMPONENTS IN CANDU NUCLEAR POWER PLANTS
N285.0-17/N285.6 SERIES-17 General requirements for pressure-retaining systems and components in CANDU nuclear power plants / Material Standards for reactor components for CANDU nuclear power plants

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N285.0-12/N285.6 SERIES-12 General requirements for pressure-retaining systems and components in CANDU nuclear power plants/Material Standards for reactor components for CANDU nuclear power plants
ASME PV CODE 3 NC DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS 2 COMPONENTS
ASME PV CODE 3 NB DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS 1 COMPONENTS
ASME PV CODE 3 DIV 2 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CODE FOR CONCRETE CONTAINMENTS
ASME PV CODE 3 NE DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS MC COMPONENTS
ASME PV CODE 3 APP DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - APPENDICES
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