1.1 本规程涵盖了监测轻水慢化核动力反应堆容器中铁素体材料机械性能的辐射诱导变化的监测程序的设计程序。本实践中未特别考虑标称设计输出为300 MWe或以下的新型先进轻水小型模块化反应堆设计。本规程包括监督计划设计的最低要求、要包括的容器材料的选择以及材料评估的初始时间表。 1.2 本规程适用于预测最大快中子注量的所有轻水慢化核动力反应堆容器( E >1 MeV）超过1 × 10 21 中子/米 2. (1 × 10 17 牛顿/厘米 2. )在铁素体钢反应堆容器的内表面。 1.3 本规程未提供在设计寿命后监测辐射引起的特性变化的具体程序。 实践 E2215 解决了在设计寿命期间和之后撤销计划的变更。 1.4 以国际单位制表示的数值应视为标准。括号中给出的值仅供参考。 注1: 轻水慢化核动力反应堆容器监督计划的要求越来越复杂，因此有必要将这些要求分为三个相关标准。实践 E185 描述了监督计划设计的最低要求。实践 E2215 描述了从反应堆容器中取出的监测舱的测试和评估程序。指导 E636 为进行其他机械测试提供指导。对实践的许多重大修改的总结 E185 由于其原始发行包含在 附录X2 . 注2: 本规程仅适用于本规程生效日期后设计和建造的反应堆容器监督计划的规划和设计。 规程E185的早期版本适用于早期的反应堆容器。看见 附录X2 . 1.5 本国际标准是根据世界贸易组织技术性贸易壁垒（TBT）委员会发布的《关于制定国际标准、指南和建议的原则的决定》中确立的国际公认标准化原则制定的。 ====意义和用途====== 4.1 在轻水慢化核动力反应堆的设计中，考虑了中子辐射对压力容器钢的影响预测。在反应堆容器的整个使用寿命期间，通常会对系统运行参数进行更改，以考虑辐射影响。由于反应堆容器钢行为的可变性，有必要制定一项监督计划，以监测长期腐蚀引起的实际容器材料性能的变化- 反应堆容器中子辐射和温度环境的长期暴露。本规程描述了在规划和实施监督测试计划时应考虑的标准，并指出了应采取的预防措施，以确保:( 1. )胶囊暴露可能与腰带线暴露有关( 2. )为监督计划选择的材料是最有可能限制反应堆容器运行的材料的样本，以及( 3. )试样类型适用于评估反应堆容器的辐射影响。 4.2 指南 E482 和 E853 描述一种估算反应堆容器监测计划中获得的中子暴露量的方法。监管机构或其他来源可能会描述不同的方法。 4.3 除了用于该反应堆容器的特定材料外，给定反应堆容器的监督计划的设计必须考虑类似材料的现有数据体。 此类数据的数量以及暴露条件和材料特性的相似性将决定其预测辐射效应的适用性。

1.1 This practice covers procedures for designing a surveillance program for monitoring the radiation-induced changes in the mechanical properties of ferritic materials in light-water moderated nuclear power reactor vessels. New advanced light-water small modular reactor designs with a nominal design output of 300 MWe or less have not been specifically considered in this practice. This practice includes the minimum requirements for the design of a surveillance program, selection of vessel material to be included, and the initial schedule for evaluation of materials. 1.2 This practice was developed for all light-water moderated nuclear power reactor vessels for which the predicted maximum fast neutron fluence ( E > 1 MeV) exceeds 1 × 10 21 neutrons/m 2 (1 × 10 17 n/cm 2 ) at the inside surface of the ferritic steel reactor vessel. 1.3 This practice does not provide specific procedures for monitoring the radiation induced changes in properties beyond the design life. Practice E2215 addresses changes to the withdrawal schedule during and beyond the design life. 1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. Note 1: The increased complexity of the requirements for a light-water moderated nuclear power reactor vessel surveillance program has necessitated the separation of the requirements into three related standards. Practice E185 describes the minimum requirements for design of a surveillance program. Practice E2215 describes the procedures for testing and evaluation of surveillance capsules removed from a reactor vessel. Guide E636 provides guidance for conducting additional mechanical tests. A summary of the many major revisions to Practice E185 since its original issuance is contained in Appendix X2 . Note 2: This practice applies only to the planning and design of surveillance programs for reactor vessels designed and built after the effective date of this practice. Previous versions of Practice E185 apply to earlier reactor vessels. See Appendix X2 . 1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. ====== Significance And Use ====== 4.1 Predictions of neutron radiation effects on pressure vessel steels are considered in the design of light-water moderated nuclear power reactors. Changes in system operating parameters often are made throughout the service life of the reactor vessel to account for radiation effects. Due to the variability in the behavior of reactor vessel steels, a surveillance program is warranted to monitor changes in the properties of actual vessel materials caused by long-term exposure to the neutron radiation and temperature environment of the reactor vessel. This practice describes the criteria that should be considered in planning and implementing surveillance test programs and points out precautions that should be taken to ensure that: ( 1 ) capsule exposures can be related to beltline exposures, ( 2 ) materials selected for the surveillance program are samples of those materials most likely to limit the operation of the reactor vessel, and ( 3 ) the test specimen types are appropriate for the evaluation of radiation effects on the reactor vessel. 4.2 Guides E482 and E853 describe a methodology for estimation of neutron exposure obtained for reactor vessel surveillance programs. Regulators or other sources may describe different methods. 4.3 The design of a surveillance program for a given reactor vessel must consider the existing body of data on similar materials in addition to the specific materials used for that reactor vessel. The amount of such data and the similarity of exposure conditions and material characteristics will determine their applicability for predicting radiation effects.