CSA N287 2-2008 Material requirements for concrete containment structures for CANDU nuclear power plants (Fifth Edition).pdf

1、N287.2-08(reaffirmed 2013)Material requirements for concrete containment structures for CANDU nuclear power plantsLegal Notice for StandardsCanadian Standards Association (CSA) standards are developed through a consensus standards development process approved by the Standards Council of Canada. This

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17、 make any copies of the contents hereof, and if you do make such copies, you are required to destroy them immediately. Use of this document constitutes your acceptance of the terms and conditions of this Legal Notice.Standards Update ServiceN287.2-08March 2008Title: Material requirements for concret

18、e containment structures for CANDU nuclear power plantsPagination: 55 pages (viii preliminary and 47 text), each dated March 2008To register for e-mail notification about any updates to this publicationgo to shop.csa.caclick on CSA Update ServiceThe List ID that you will need to register for updates

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20、t private sector organization5060 Spectrum Way, Suite 100, Mississauga, Ontario, Canada L4W 5N61-800-463-6727 416-747-4044Visit our Online Store at www.ShopCSA.caN287.2-08Material requirements for concrete containment structures for CANDU nuclear power plantsCSA Standard100%ISBN 978-1-55436-655-2Tec

21、hnical Editor: Senka Krsikapa Canadian Standards Association 2008All rights reserved. No part of this publication may be reproduced in any form whatsoever without the prior permission of the publisher.To purchase CSA Standards and related publications, visit CSAs Online Store at www.ShopCSA.ca or ca

22、ll toll-free 1-800-463-6727 or 416-747-4044.The Canadian Standards Association (CSA) prints its publications on Rolland Enviro100, which contains 100% recycled post-consumer fibre, is EcoLogo and Processed Chlorine Free certified, and was manufactured using biogas energy.March 2008 iiiContents Canad

23、ian Standards AssociationMaterial requirements for concrete containmentstructures for CANDU nuclear power plantsTechnical Committee on Concrete Containment and Safety-Related Structures viPreface viii1Scope 12 Reference publications 13 Definitions 64 General requirements 85 Materials for concrete an

24、d grout 85.1 General requirements 85.2 Materials for concrete 85.2.1 General 85.2.2 Cementitious materials 85.2.3 Mixing water 95.2.4 Aggregates 95.2.5 Admixtures 95.3 Materials for grout 105.3.1 General 105.3.2 Cement 105.3.3 Water 105.3.4 Aggregates 105.3.5 Admixtures 105.3.6 Non-cementitious grou

25、t 105.4 Repair materials 106 Reinforcement 106.1 General 106.2 Tensile tests 106.3 Bend tests 106.4 Certification 116.5 Identification and marking 116.6 Arc-welded splice materials 116.7 Mechanical splice materials 116.8 Performance tests for mechanical splices 126.8.1 General 126.8.2 Static tensile

26、 tests 126.8.3 Static compression tests 136.8.4 Cyclic load tests 136.8.5 Long-term elongation and shortening tests 146.8.6 Test report 147 Pre-stressing systems 157.1 General 157.2 Tendons 157.3 Anchorages, coupling anchorages, and anchorage components 167.3.1 Anchorages and coupling anchorages 167

27、.3.2 Wedge sets 16N287.2-08 Canadian Standards Associationiv March 20087.4 Assembly for performance tests 167.4.1 General 167.4.2 Assembly for performance tests 177.4.3 Static tensile tests 177.4.4 Dynamic tensile tests 177.4.5 Temperature requirements 187.4.6 Test report 187.5 Sheathing 187.6 Corro

28、sion-preventive materials 187.6.1 General 187.6.2 Bonded tendons 187.6.3 Unbonded tendons 198 Non-metallic liner systems and joint sealants 208.1 General 208.2 Compatibility 208.3 Packaging and storage 218.4 Identification 218.5 Tests 218.5.1 General 218.5.2 Liner material 218.5.3 Joint sealant mate

29、rials 238.6 Materials for repair of liners and sealants 259 Metallic parts 259.1 General 259.2 Material selection 259.3 Special requirements 279.4 Delivery 279.5 Examination and repair 279.6 Certification 279.7 Identification 2810 Welding materials 2810.1 General 2810.2 Qualification 2810.3 Tests 28

30、10.3.1 Chemical analysis 2810.3.2 Tensile and impact tests 2910.4 Marking, identification, and storage 2911 Organic materials 2911.1 General 2911.2 Tests 3011.2.1 Properties before heat aging 3011.2.2 Properties after heat aging 3011.2.3 Performance tests after heat aging 3011.2.4 Radiation resistan

31、ce 3012 Anchorage systems 3012.1 General 3012.2 Material selection 3012.3 Test requirements 3112.3.1 General 31 Canadian Standards AssociationMaterial requirements for concrete containmentstructures for CANDU nuclear power plantsMarch 2008 v12.3.2 Static tensile test 3212.3.3 Static shear test 3212.

32、3.4 Seismic qualification tests 3312.3.5 Reliability testing for post-installed mechanical anchors 3312.4 Test reports 33AnnexesA (informative) Test method to determine air leakage 36B (informative) Test method to determine pull-off adhesion 38C (informative) Test methods for seismic qualification o

33、f embedded anchors and post-installed mechanical anchors 39D (informative) Failure modes of anchors under tension and shear loading 46Tables1 Properties before heat aging 342 Properties after heat aging 343 Performance tests after heat aging 34Figures1 Delta ferrite content 35N287.2-08 Canadian Stan

34、dards Associationvi March 2008Technical Committee on Concrete Containment and Safety-Related StructuresT.S. Aziz Atomic Energy of Canada Limited,Mississauga, OntarioChairD.J. Armchuk Bruce Power,Tiverton, OntarioVice-ChairA. Blahoianu Canadian Nuclear Safety Commission (CNSC),Ottawa, OntarioVice-Cha

35、irJ.P.D. Brock RCM Technologies Canada Corp.,Pickering, OntarioK.M. Chaudhry Canadian Nuclear Safety Commission,Ottawa, OntarioAssociateR. Cullen Kinectrics Inc.,Toronto, OntarioR.J. El Frenn DYWIDAG-Systems International, Canada, Ltd.,Gormley, OntarioL. Gartley Hilti (Canada) Limited,Mississauga, O

36、ntarioA. Ghobarah McMaster University,Hamilton, OntarioX.M. Han SNC-Lavalin Nuclear Inc.,Oakville, OntarioJ.D. Hanna Bruce Power, Tiverton, OntarioAssociateJ. Li DYWIDAG-Systems International, Canada, Ltd.,Gormley, OntarioAssociateR.J. McGrath Cement Association of Canada (CAC),Ottawa, OntarioI. Mil

37、man Atomic Energy of Canada Limited,Mississauga, OntarioAssociateJ.S. Mok Canadian Nuclear Safety Commission (CNSC),Ottawa, OntarioAssociateT. Moore City of Pickering,Pickering, Ontario Canadian Standards AssociationMaterial requirements for concrete containmentstructures for CANDU nuclear power pla

38、ntsMarch 2008 viiM.S. Nashid Kinectrics Inc.,Toronto, OntarioAssociateP. Ostrowski Ontario Power Generation Inc.,Pickering, OntarioS. Picard Hydro-Qubec,Bcancour, QubecG. Roberts NB Power Nuclear Corp.,Lepreau, New BrunswickS. van Rassel Dayton Superior Co.,Toronto, OntarioF.J. Vecchio University of

39、 Toronto,Toronto, OntarioS. Krsikapa Canadian Standards Association,Mississauga, OntarioProject ManagerIn addition to the members of the Technical Committee, the following people made valuable contributions to the development and publication of this Standard:H.P.J. Lee Nuclear Safety Solutions Limit

40、ed,Toronto, OntarioJ. Neller SNC-Lavalin Nuclear Inc.,Mississauga, OntarioN287.2-08 Canadian Standards Associationviii March 2008PrefaceThis is the fifth edition of CSA N287.2, Material requirements for concrete containment structures for CANDUnuclear power plants. It supersedes the previous edition

41、s published in 1991, 1982, 1977, and 1976.Note: CANDU (CANada Deuterium Uranium) is a registered trademark of Atomic Energy of Canada Limited (AECL).This Standard provides requirements for materials used in concrete containment structures. Together with the other CSA N287 Standards, it provides the

42、requirements for concrete containment structures for CANDU nuclear power plants. These Standards were initiated in response to the recognition by the utilities and industries concerned with nuclear structures in Canada of a need for consistent standards for the design, construction, and testing of c

43、oncrete containment structures for CANDU nuclear power plants.Users of this Standard are reminded that the design, manufacture, construction, commissioning, operation, and decommissioning of nuclear facilities in Canada are subject to the provisions of the Nuclear Safety Control Act and its Regulati

44、ons. Additional requirements to those specified in this Standard could be imposed by the Canadian Nuclear Safety Commission.This Standard was prepared by the Technical Committee on Concrete Containment and Safety-Related Structures, under the jurisdiction of the Strategic Steering Committee on Nucle

45、ar Standards, and has been formally approved by the Technical Committee.March 2008Notes: (1) Use of the singular does not exclude the plural (and vice versa) when the sense allows.(2) Although the intended primary application of this Standard is stated in its Scope, it is important to note that it r

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