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Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
TECHNICAL REQUIREMENTS FOR IN-SERVICE EVALUATION OF ZIRCONIUM ALLOY PRESSURE TUBES IN CANDU REACTORS
Hardcopy , PDF
18-07-2020
English, French
01-01-2015
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 |
260
|
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Superseded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 |
ASME PV CODE 3 NF DIV 1 : 2017 | BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - SUPPORTS |
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 ND DIV 1 : 2017 | BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CLASS 3 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 |
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 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 |
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 |
ASME PV CODE SET : 2017 | BOILER AND PRESSURE VESSEL CODE - COMPLETE SET |
ASME PV CODE 11 : 2017 | BOILER AND PRESSURE VESSEL CODE - RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS |
ASME PV CODE 3 NG DIV 1 : 2017 | BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - CORE SUPPORT STRUCTURES |
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