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CSA N285.6 SERIES : 2005

Superseded
Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

View Superseded by
superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

MATERIAL STANDARDS FOR REACTOR COMPONENTS FOR CANDU NUCLEAR POWER PLANTS
Available format(s)

Hardcopy , PDF

Superseded date

06-01-2008

Language(s)

English

Published date

01-01-2005

Technical Committee on CANDU Nuclear Power Plant Systems
and Components
Subcommittee on Material Standards for Reactor Components
for CANDU Nuclear Power Plants
Preface
N285.6.1-05, Pressure tubes for use in CANDU fuel channels
1 Scope
2 Reference publications
3 Definitions
4 General requirements
5 Ingot and ingot composition requirements
6 Extrusion requirements
7 Tube requirements
N285.6.2-05, Seamless zirconium alloy tubing for reactivity
             control units
1 Scope
2 Reference publications
3 Manufacturing requirements
4 Composition requirements
5 Inspections
N285.6.3-05, Annealed seamless zirconium alloy tubing for
             liquid injection shutdown system (LISS) nozzles
1 Scope
2 Reference publications
3 General requirements
4 Composition requirements
5 Inspections (LISS) nozzles)
N285.6.4-05, Thin-walled, large-diameter zirconium alloy
             tubing
1 Scope
2 Reference publications
3 General requirements
4 Composition requirements
5 Processing requirements
   5.1 General
   5.2 Seam-welded processing
       5.2.1 Material for seam-welded processing
       5.2.2 Processing of strip material
   5.3 Seamless processing
6 Final surface condition of the seam-welded and seamless
   tubes
   6.1 Calandria tube surfaces
   6.2 Reactivity tubes
7 Inspections
N285.6.6-05, Non-destructive examination criteria for
             zirconium alloys
1 Scope
2 Reference publications
3 NDE personnel qualification
   3.1 General
   3.2 Certification
   3.3 Eye test requirements
   3.4 Documentation control
4 Visual inspection standards
   4.1 Standard V-1 (for small tubes)
       4.1.1 Application
       4.1.2 Requirements
       4.1.3 Acceptance criteria
   4.2 Standard V-2 (for large-diameter tubes)
       4.2.1 Application
       4.2.2 Requirements
       4.2.3 Acceptance criteria
   4.3 Standard V-3
   4.4 Standard V-4 (for pressure tubes)
       4.4.1 Application
       4.4.2 Requirements
       4.4.3 Acceptance criteria
5 Radiographic standards
   5.1 Standard R-1 (for seam welds in large-diameter tubes)
   5.2 Acceptance standards
6 Liquid-penetrant standards
   6.1 Standard LP-1 (for seam welds in large-diameter tubes)
       6.1.1 Application
       6.1.2 Requirements
       6.1.3 Acceptance standards
   6.2 Standard LP-2
   6.3 Standard LP-3 (for seamless tubes for liquid injection
       shutdown system (LISS) nozzles)
       6.3.1 Application
       6.3.2 Requirements
       6.3.3 Acceptance standards
7 Ultrasonic standards
   7.1 Standard UT-1 (for seamless tubing)
       7.1.1 Application
       7.1.2 Requirements
       7.1.3 Acceptance criteria
   7.2 Standard UT-2
   7.3 Standard UT-3
   7.4 Standard UT-4
   7.5 Standard UT-5 (for pressure tubes)
       7.5.1 Application
       7.5.2 Requirements
       7.5.3 Acceptance criteria
   7.6 Standard UT-6 (for large-diameter tubes)
       7.6.1 Application
       7.6.2 Requirements
       7.6.3 Acceptance criteria
8 Eddy current standards - Standard EC-1 (for pressure
   tubes)
   8.1 Application
   8.2 Requirements
   8.3 Acceptance criteria
N285.6.7-05, Zirconium alloy design data
1 Scope
2 Reference publications
3 General
Tables
N285.6.8-05, Martensitic stainless steel for fuel-channel
             end fittings
1 Scope
2 Reference publications
3 Definitions
4 Manufacturing requirements
   4.1 Melting process
   4.2 Forging process
   4.3 Heat treatment
5 Chemical composition
6 Mechanical properties
   6.1 Prolongations for tests
   6.2 Tension tests
       6.2.1 Tensile properties
       6.2.2 Method for tensile testing
       6.2.3 Number of tests
       6.2.4 Test location and orientation
   6.3 Impact test
       6.3.1 Impact properties
       6.3.2 Number of tests, location, and orientation
       6.3.3 Method
       6.3.4 Test temperature
   6.4 Re-test
7 Macroetch test
   7.1 Material homogeneity
   7.2 Samples
   7.3 Examination procedure
   7.4 Acceptance criteria
8 Ultrasonic examination
9 Quality of work
   9.1 Quality of blanks
   9.2 Repair by welding
10 Certification
11 Product marking
Annexes
A (normative) - Design data recommended for end fitting
                material
Tables
N285.6.9-05, Materials for supports for pressure-retaining
             items
1 Scope
2 Reference publications
3 General requirements
4 Materials
5 Welding
6 Examination
7 Certification
Tables
N285.6.10-05, Nickel-based alloy wire for fuel-channel
              spacers
1 Scope
2 Reference publications
3 Wire requirements
N285.6.11-05, Zirconium alloy wire
1 Scope
2 Reference publications
3 Material requirements

Outlines the requirements for the fabrication and properties of seamless zirconium-2.5 wt% niobium (Zr-2.5Nb) alloy pressure tubes for use in fuel channels in CANDU reactors.

DocumentType
Standard
Pages
84
PublisherName
Canadian Standards Association
Status
Superseded
SupersededBy
Supersedes

CSA N285.0 : 2006 GENERAL REQUIREMENTS FOR PRESSURE-RETAINING SYSTEMS AND COMPONENTS IN CANDU NUCLEAR POWER PLANTS
CSA N285.5 : 2013 PERIODIC INSPECTION OF CANDU NUCLEAR POWER PLANT CONTAINMENT COMPONENTS
CSA N290.1 : 2013 REQUIREMENTS FOR THE SHUTDOWN SYSTEMS OF CANDU NUCLEAR POWER PLANTS
CSA N294 : 2009 DECOMMISSIONING OF FACILITIES CONTAINING NUCLEAR SUBSTANCES
CSA N289.1 : 2008 GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS
N289.1-08 (R2013) General requirements for seismic design and qualification of CANDU nuclear power plants
CSA N289.1 : 2008 : INC : UPD 1 : 2014: R201300 GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS
CSA N289.1 : 2008 : INC : UPD 1 : 2015 : R201300 GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS
CSA N294 : 2009 : FR DECOMMISSIONING OF FACILITIES CONTAINING NUCLEAR SUBSTANCES
CSA N294 : 2009 : INC : UPD 1 : 2014 DECOMMISSIONING OF FACILITIES CONTAINING NUCLEAR SUBSTANCES
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
N285.4-14 Periodic inspection of CANDU nuclear power plant components
CSA N294 : 2009 : R2014 DECOMMISSIONING OF FACILITIES CONTAINING NUCLEAR SUBSTANCES
CSA N285.2 : 0 REQUIREMENTS FOR CLASS 1C, 2C AND 3C PRESSURE-RETAINING COMPONENTS AND SUPPORTS IN CANDU NUCLEAR POWER PLANTS

CSA N285.0 : 2006 GENERAL REQUIREMENTS FOR PRESSURE-RETAINING SYSTEMS AND COMPONENTS IN CANDU NUCLEAR POWER PLANTS
CSA G40.20 G40.21 : 2013 GENERAL REQUIREMENTS FOR ROLLED OR WELDED STRUCTURAL QUALITY STEEL/STRUCTURAL QUALITY STEEL
SAE AMS 5698 : 2013 NICKEL ALLOY, CORROSION AND HEAT-RESISTANT, WIRE, 72NI - 15.5CR - 0.95CB - 2.5TI - 0.70AL - 7.0FE, NO. 1 TEMPER, PRECIPITATION HARDENABLE
ASTM E 381 : 2017 : REDLINE Standard Method of Macroetch Testing Steel Bars, Billets, Blooms, and Forgings
CGSB 48.9712 : 2014 NON-DESTRUCTIVE TESTING - QUALIFICATION AND CERTIFICATION OF PERSONNEL
ASTM B 352/B352M : 2017 : REDLINE Standard Specification for Zirconium and Zirconium Alloy Sheet, Strip, and Plate for Nuclear Application

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