序言这是CSA N287的第六版。2、核电站混凝土安全壳结构的材料要求。它取代了2008年、1991年、1982年、1977年和1976年出版的之前版本，标题为CANDU核电厂混凝土安全壳结构的材料要求。它反映了加拿大的监管要求、加拿大核工业的运营经验和国际惯例。本标准最初是为CANDU反应堆编写的，但可用于其他适用的混凝土安全壳结构。 为了反映这一点，标题已经更改。在这一版本中，有许多技术、编辑和格式上的变化；最重要的变化如下:–术语已通过修改定义来澄清，以与通用定义和其他核标准保持一致对混凝土和水泥的要求已经修改对用于安全壳边界内外表面的非金属衬里系统、涂层系统和接缝密封剂的测试要求进行了修改修订了锚栓试验的要求。 注:CANDU（加拿大氘铀）是加拿大原子能有限公司（AECL）的注册商标。本标准规定了混凝土安全壳结构所用材料的要求。本标准是N287系列标准的一部分，该系列标准规定了核电厂混凝土安全壳结构的要求。这些标准的制定是为了回应加拿大与核结构相关的公用事业和行业对适用于核电厂混凝土安全壳结构设计、施工和测试的标准的需求。 CSA N系列标准为核设施和活动的管理提供了一套相互关联的要求。CSA N286为管理层提供全面指导，以制定和实施健全的管理实践和控制措施，而CSA集团的其他核标准则提供支持管理体系的技术要求和指导。本标准与CSA N286一致，不重复CSA N286的一般要求；然而，它可能会为这些需求提供更具体的指导。CSA N287系列标准由八个标准组成。 每个标准的目标总结如下:–CSA N287。1，核电厂混凝土安全壳结构的一般要求，规定了核电厂混凝土安全壳结构的设计、施工、测试、调试、运行检查和测试的一般要求，并针对业主、设计师、制造商、制造商和施工人员；——CSA N287。2、核电厂混凝土安全壳结构的材料要求，规定了混凝土安全壳结构所用材料的要求； –CSA N287。3，核电厂混凝土安全壳结构的设计要求，规定了混凝土安全壳结构的设计要求CSA N287。CANDU核电厂混凝土安全壳结构的施工、制造和安装要求，规定了CANDU核电厂混凝土安全壳结构的施工、制造和安装要求；——CSA N287。5、核电厂混凝土安全壳结构的检查和测试要求，规定了适用于参与核电厂混凝土安全壳结构施工、制造或安装的任何组织的工作的检查和测试要求； –CSA N287。6，核电厂混凝土安全壳结构的运行前验证和泄漏率测试要求，规定了在首次临界之前，通过演示证明混凝土安全壳结构的设计和施工在质量和性能方面令人满意的要求，如达到CSA N287的规定要求所示。6包括试运行泄漏率目标；——CSA N287。7，《核电厂混凝土安全壳结构在役检查和试验要求》规定了统一要求，通过系统和定期检查，结构和泄漏- 通过达到CSA N287的规定要求，可以评估混凝土安全壳结构的紧密完整性。7包括运行泄漏率目标；和–CSA N287。8，《核电厂混凝土安全壳结构老化管理》，为核电厂混凝土安全壳结构提供老化管理要求，并针对业主/运营商、设计师、制造商、制造商和施工人员。本标准的使用者应注意，加拿大核设施的设计、制造、施工、调试、运行和退役应遵守《核安全控制法》及其法规的规定。 加拿大核安全委员会可对本标准中规定的要求提出附加要求。范围1。1本标准规定了混凝土安全壳结构所用材料的要求，包括但不限于以下结构和非结构构件:a）混凝土；b） 钢筋（预应力和非预应力）；c） 钢（例如衬里、预埋件、锚）；d） 非金属衬里和涂层系统；和e）接缝密封剂。注:有关安全相关结构的材料要求，请参考CSA N291。 1.2本标准适用于现有和新建核电站。除非AHJ同意，否则本标准的要求不适用于现有核电厂。1.3本标准与以下适用标准配合使用:a）CSA N287。1，概述了核电站混凝土安全壳结构的一般要求；b）CSA N287。8，概述了核电站混凝土安全壳结构的老化管理要求。1.4在本标准中，“应”用于表示要求，即:。 e、 ，用户必须满足的条款，以符合标准；“应该”用于表示建议或建议但不需要的建议；“可”用于表示一个选项或在标准范围内允许的选项。注释随附条款不包括要求或替代要求；随附条款的注释的目的是将解释性或信息性材料与文本分开。表和图的注释被视为表或图的一部分，可以作为要求编写。 附件被指定为规范性（强制性）或信息性（非强制性）以定义其应用。1.5在本标准中，“应考虑”或“应考虑”是指用户评估影响并记录任何决定。注:示例可能不包括任何操作、操作程序或设计特征。

PrefaceThis is the sixth edition of CSA N287.2, Material requirements for concrete containment structures for nuclear power plants. It supersedes the previous editions published in 2008, 1991, 1982, 1977, and 1976 under the title Material requirements for concrete containment structures for CANDU nuclear power plants. It reflects Canadian regulatory requirements, operating experience of the Canadian nuclear industry, and international practices. The standard was originally written for CANDU reactors but can be used for other concrete containment structures as applicable. The title has been changed to reflect this. There have been many technical, editorial, and formatting changes throughout this edition; the most significant changes are as follows: – Terminology has been clarified by modifying definitions to align with common definitions and other nuclear standards. – Requirements for the concrete and cement have been modified. – Testing requirements for non-metallic liner systems, coating systems, and joint sealant applied to the inner and outer surface of containment boundary have been modified. – Requirements for anchors bolt testing have been revised. Note: CANDU (CANada Deuterium Uranium) is a registered trademark of Atomic Energy of Canada Limited (AECL). This Standard provides requirements for materials used for concrete containment structures. This Standard is part of N287 Series of Standard, which provide the requirements for concrete containment structures for 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 standards applicable to the design, construction, and testing of concrete containment structures for nuclear power plants. The CSA N-Series Standards provide an interlinked set of requirements for the management of nuclear facilities and activities. CSA N286 provides overall direction to management to develop and implement sound management practices and controls, while the other CSA Group nuclear Standards provide technical requirements and guidance that support the management system. This standard works in harmony with CSA N286 and does not duplicate the generic requirements of CSA N286; however, it might provide more specific direction for those requirements. The CSA N287 Series of Standards consists of eight Standards. The objectives of each Standard are summarized as follows: – CSA N287.1, General requirements for concrete containment structures for nuclear power plants, specifies general requirements for the design, construction, testing, commissioning, and in-service examination and testing of concrete containment structures for nuclear power plants and is directed to the owners, designers, manufacturers, fabricators, and constructors; – CSA N287.2, Material requirements for concrete containment structures for nuclear power plants, specifies requirements for materials used for concrete containment structures; – CSA N287.3, Design requirements for concrete containment structures for nuclear power plants, specifies requirements for the design of concrete containment structures; – CSA N287.4, Construction, fabrication, and installation requirements for concrete containment structures for CANDU nuclear power plants, specifies construction, fabrication, and installation requirements for concrete containment structures for CANDU nuclear power plants; – CSA N287.5, Examination and testing requirements for concrete containment structures for nuclear power plants, specifies examination and testing requirements that apply to the work of any organization participating in the construction, fabrication, or installation of concrete containment structures for nuclear power plants; – CSA N287.6, Pre-operational proof and leakage rate testing requirements for concrete containment structures for nuclear power plants, specifies requirements for proof by demonstration, before first criticality, that the design and construction of a concrete containment structure are satisfactory with respect to quality and performance as demonstrated by achieving the specified requirements of CSA N287.6 including commissioning leakage rate target; – CSA N287.7, In-service examination and testing requirements for concrete containment structures for nuclear power plants, specifies uniform requirements whereby, through systematic and periodic examination, the structural and leak-tight integrity of concrete containment structures can be assessed as demonstrated by achieving the specified requirements of CSA N287.7 including the operational leakage rate target; and – CSA N287.8, Aging management for concrete containment structures for nuclear power plants, provides aging management requirements for concrete containment structures for nuclear power plants and is directed to the owners/operators, designers, manufacturers, fabricators, and constructors. 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 Regulations. Additional requirements to those specified in this Standard could be imposed by the Canadian Nuclear Safety Commission.Scope1.1 This Standard provides requirements for the materials used for concrete containment structures, which include, but are not limited to, the following structural and non-structural elements: a) concrete; b) reinforcement (pre-stressed and non-pre-stressed); c) steel (e.g., liner, embedded parts, anchors); d) non-metallic liners and coating systems; and e) joint sealants. Note: For material requirements for safety-related structures, refer to CSA N291. 1.2 This Standard is applicable to existing and new nuclear power plants. It is not the intent that the requirements of this Standard be applied retroactively to existing nuclear power plants, unless as agreed to by the AHJ. 1.3 This Standard is used in concert with the following standards, as applicable: a) CSA N287.1, which outlines general requirements for concrete containment structures for nuclear power plants; and b) CSA N287.8, which outlines aging management requirements for concrete containment structures for nuclear power plants. 1.4 In this Standard, "shall" is used to express a requirement, i.e., a provision that the user is obliged to satisfy in order to comply with the Standard; "should" is used to express a recommendation or that which is advised but not required; and "may" is used to express an option or that which is permissible within the limits of the Standard. Notes accompanying clauses do not include requirements or alternative requirements; the purpose of a note accompanying a clause is to separate from the text explanatory or informative material. Notes to tables and figures are considered part of the table or figure and may be written as requirements. Annexes are designated normative (mandatory) or informative (non-mandatory) to define their application. 1.5 In this Standard, "shall be considered" or "shall consider" means that the user evaluates the impact and documents any decisions. Note: Examples can include no action, operating procedures, or design features.