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  • CSA N285.8 : 2015

    Superseded A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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    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    Superseded date:  18-07-2020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

    Publisher:  Canadian Standards Association

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    Table of Contents - (Show below) - (Hide below)

    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

    Abstract - (Show below) - (Hide below)

    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.


    General Product Information - (Show below) - (Hide below)

    Development Note French Edition issued on 01-03-2018. (03/2018) This standard is revised in October 2019
    Document Type Standard
    Product Note This standard is revised in October 2019
    Publisher Canadian Standards Association
    Status Superseded
    Superseded By
    Supersedes

    Standards Referenced By This Book - (Show below) - (Hide below)

    CSA N285.0 : 2006 GENERAL REQUIREMENTS FOR PRESSURE-RETAINING SYSTEMS AND COMPONENTS IN CANDU NUCLEAR POWER PLANTS
    N285.4-14 Periodic inspection of CANDU nuclear power plant components
    N291-15 Requirements for safety-related structures for 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

    Standards Referencing This Book - (Show below) - (Hide below)

    ASME PV CODE 3 NCA DIV 1&2 : 2017 BPVC Section III-Rules for Constructions of Nuclear Facility Components BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - GENERAL REQUIREMENTS FOR DIVISION 1 AND DIVISION 2
    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 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
    ASME PV CODE SET : 2017 BOILER AND PRESSURE VESSEL CODE - COMPLETE SET
    ASME PV CODE 3 NF DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - SUPPORTS
    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 DIV 5 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - HIGH TEMPERATURE REACTORS
    ASME PV CODE 3 NG DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CORE SUPPORT STRUCTURES
    ASME PV CODE 3 NC DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS 2 COMPONENTS
    N285.4-14 Periodic inspection of CANDU nuclear power plant 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 ND DIV 1 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS 3 COMPONENTS
    ASME PV CODE 3 DIV 3 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CONTAINMENT SYSTEMS FOR TRANSPORTATION AND STORAGE OF SPENT NUCLEAR FUEL AND HIGH-LEVEL RADIOACTIVE MATERIAL
    ASME PV CODE 11 : 2017 BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS
    ASME PV CODE 3 NH DIV 1 : 2015 BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS 1 COMPONENTS IN ELEVATED TEMPERATURE SERVICE
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