1.1本规程涵盖了监测轻水慢化核动力反应堆容器带线中铁素体材料机械性能的辐射诱导变化的监督计划设计程序。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 >1兆电子伏）超过1 x 10 17 牛顿/厘米 2. （1 x 10 21 牛顿/米 2. )在反应堆容器的内表面。 1.3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E 185的早期版本适用于早期的反应堆容器。 1.4本规程未提供监测设计寿命外辐射引起的特性变化的具体程序，但所述程序可为制定此类监测计划提供指导。 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。规程E 185描述了监督计划的最低要求。实施规程E 2215，“轻水慢化核动力反应堆容器监测舱评估的标准实施规程”描述了从现行或以前版本的实施规程E 185中定义的监测计划中移除的监测舱的测试和评估程序。 另一个补充现有轻水慢化核动力反应堆容器监督计划的标准指南正在编制中。附录X1总结了自最初发布以来对实施规程E 185的许多主要修订。 ====意义和用途====== 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，以监测因长期暴露于反应堆容器的中子辐射和温度环境而导致的实际容器材料性能的变化。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. )试验结果有助于评估反应堆容器的辐射影响。 指南E 482中定义了用于估算反应堆容器监测计划获得的中子暴露量的方法 这为评估反应堆容器的设计和未来状况奠定了基础。 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 the beltline of light-water moderated nuclear power reactor vessels. This practice includes the minimum requirements for the design of a surveillance program, selection of vessel material to be included, and a 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) at the end of the design lifetime (EOL) exceeds 1 x 10 17 n/cm 2 (1 x 10 21 n/m 2 ) at the inside surface of the reactor vessel. 1.3 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 E 185 apply to earlier reactor vessels. 1.4 This practice does not provide specific procedures for monitoring the radiation induced changes in properties beyond the design life, but the procedure described may provide guidance for developing such a surveillance program. 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 E 185 describes the minimum requirements for a surveillance program. Practice E 2215, "Standard Practice for the Evaluation of Surveillance Capsules from Light-Water Moderated Nuclear Power Reactor Vessels" describes the procedures for testing and evaluation of surveillance capsules removed from a surveillance program as defined in the current or previous editions of Practice E 185. Another standard guide for supplementing existing light-water moderated nuclear power reactor vessel surveillance programs is under preparation. A summary of the many major revisions to Practice E 185 since its original issuance is contained in Appendix X1. ====== Significance And Use ====== 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 tests yield results useful for the evaluation of radiation effects on the reactor vessel. The methodology to be used in estimation of neutron exposure obtained for reactor vessel surveillance programs is defined in Guide E 482 , which establishes the bases to be used to evaluate both the design and future condition of the reactor vessel. 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.