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N285.6 SERIES-05

Material Standards for Reactor Components for CANDU Nuclear Power Plants

SKU: 2417662 Published by CSA Group Publication Year 2005 84 pages Withdrawn

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Preface/Scope

This is the second edition of the CSA N285.6 Series, Material standards for reactor components for CANDU nuclear power plants.

It supersedes the first edition published in 1988. This Standard is written in SI (metric) units.

N285.6.1-05 Pressure tubes for use in CANDU fuel channels

Scope

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

N285.6.2-05 Seamless zirconium alloy tubing for reactivity control units

Scope

This Standard outlines the requirements for the fabrication and properties of seamless zirconium alloy tubing, Grades R60802 and R60804, with diameter to wall thickness ratios less than 80. This tubing is used for reactivity control units in CANDU reactors.

N285.6.3-05 Annealed seamless zirconium alloy tubing for liquid injection shutdown system (LISS) nozzles

Scope

This Standard outlines the requirements for the fabrication and properties of seamless zirconium-tin alloy tubing, Grade R60802 or R60804, which is suitable for use in liquid injection shutdown system (LISS) nozzles located in the moderator water in the core of a CANDU reactor.

N285.6.4-05 Thin-walled, large-diameter zirconium alloy tubing

Scope

This Standard outlines the requirements for the fabrication and properties of thin-walled, large diameter tubing made from zirconi um-tin alloys, Grade R60802 or R60804. This tubing can be used as calandria tubes and as tubes for reactivity control units in a CANDU reactor, and may be processed in the seamless or seam-welded condition. Note: Thin-walled, large diameter tubing has a diameter to wall thickness ratio greater than 50.

N285.6.6-05 Non-destructive examination criteria for zirconium alloys

Scope

This Standard outlines the requirements for non-destructive examinations (NDEs) of zirconium alloy components during manufacturing. The NDE methods include visual, radiographic, liquid-penetrant, ultrasonic, and eddy current techniques. Other Standards may be used, provided that they satisfy the requirements of the CSA N285.6 Series.

N285.6.7-05 Zirconium alloy design data

Scope

This Standard provides the physical and mechanical property data to be used for design purposes for the zirconium alloy components defined in the CSA N285.6 Series of standards.

N285.6.8-05 Martensitic stainless steel for fuel-channel end fittings

Scope

1.1 This Standard outlines the requirements for martensitic stainless steel forged blanks for the fuel-channel end fittings of a CANDU reactor.

N285.6.9-05 Materials for supports for pressure-retaining items

Scope

This Standard covers the material for the support of pressure-retaining items in CANDU nuclear power plants. The materials covered are in addition to the materials permitted by the ASME Boiler and Pressure Vessel Code (BPVC), Section III, NF-2000 and Code Cases.

N285.6.10-05 Nickel-based alloy wire for fuel-channel spacers

Scope

This Standard outlines the requirements for the nickel-based alloy (UNS N07750) wire used to form spacers for use between the pressure tubes and calandria tubes in the fuel channels in a CANDU reactor.

N285.6.11-05 Zirconium alloy wire

Scope

This Standard outlines the requirements for wires made from zirconium-tin alloy Grade R60802 or R60804 used in the welding of zirconium components and in the manufacture of the spacers that are installed between pressure tubes and calandria tubes in the fuel channels in a CANDU reactor.

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N285.6 SERIES-05

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