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Standard Guide for Use of Melt Wire Temperature Monitors for Reactor Vessel Surveillance 反应堆容器监控用熔化线温度监测器的使用标准指南
发布日期: 2023-01-01
1.1 本指南描述了熔化线温度监测器的应用及其在轻水动力反应堆反应堆容器监控中的应用 1985年 和 215年 . 1.2 本指南的目的是推荐选择和使用普通熔丝技术,其中不同合金的熔化温度和成分之间的对应关系用作被动温度监测器。为监测材料的选择和校准提供了指南; 显示器和容器的设计、制造和组装;辐照后检查;结果的解释;以及不确定性的估计。 1.3 以国际单位制表示的值应视为标准值。括号中给出的值是英寸-磅单位的数学转换,仅供参考,不被视为标准值。 1.4 本标准并不旨在解决与其使用相关的所有安全问题(如有)。本标准的使用者有责任在使用前建立适当的安全、健康和环境实践,并确定监管限制的适用性。 (参见 注1 .) 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《国际标准、指南和建议制定原则决定》中确立的国际公认标准化原则制定的。 =====意义和用途====== 3.1 根据规程,温度监测器用于监测舱 215年 以估计监视样本照射温度的最大值。 需要温度监测器来提供监测样本过热超过预期温度的证据。由于过热会导致监测样本中子辐射损伤量的减少,这种过热可能导致监测样本的测量特性发生变化,从而导致对反应堆容器材料损伤的不保守预测。 3.2 过热时辐射损伤的减少程度取决于材料的成分和温度下的时间。 指导 E900型 提供了用于量化温度效应的公认方法。由于熔化线监测器的证据没有显示过热持续时间超过监测器熔化所指示的预期温度,因此不能仅根据温度监测器来量化过热事件的重要性。过热指示确实用于提醒用户数据,以进一步评估监视舱的辐照温度暴露历史。 3.3 本指南包含在主矩阵中 E706型 这涉及用于轻水反应堆容器材料辐照监测的若干标准。其主要目的是扩大实践的要求 1985年 在监控程序的温度监测器的设计中。它也可以与Practice一起使用 215年 以评估辐照后测试测量。
1.1 This guide describes the application of melt wire temperature monitors and their use for reactor vessel surveillance of light-water power reactors as called for in Practices E185 and E2215 . 1.2 The purpose of this guide is to recommend the selection and use of the common melt wire technique where the correspondence between melting temperature and composition of different alloys is used as a passive temperature monitor. Guidelines are provided for the selection and calibration of monitor materials; design, fabrication, and assembly of monitor and container; post-irradiation examinations; interpretation of the results; and estimation of uncertainties. 1.3 The values stated in SI units are to be regarded as standard. The values given in parentheses are mathematical conversions to inch-pound units that are provided for information only and are not considered standard. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. (See Note 1 .) 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 ====== 3.1 Temperature monitors are used in surveillance capsules in accordance with Practice E2215 to estimate the maximum value of the surveillance specimen irradiation temperature. Temperature monitors are needed to give evidence of overheating of surveillance specimens beyond the expected temperature. Because overheating causes a reduction in the amount of neutron radiation damage to the surveillance specimens, this overheating could result in a change in the measured properties of the surveillance specimens that would lead to an unconservative prediction of damage to the reactor vessel material. 3.2 The magnitude of the reduction of radiation damage with overheating depends on the composition of the material and time at temperature. Guide E900 provides an accepted method for quantifying the temperature effect. Because the evidence from melt wire monitors gives no indication of the duration of overheating above the expected temperature as indicated by melting of the monitor, the significance of overheating events cannot be quantified on the basis of temperature monitors alone. Indication of overheating does serve to alert the user of the data to further evaluate the irradiation temperature exposure history of the surveillance capsule. 3.3 This guide is included in Master Matrix E706 that relates several standards used for irradiation surveillance of light-water reactor vessel materials. It is intended primarily to amplify the requirements of Practice E185 in the design of temperature monitors for the surveillance program. It may also be used in conjunction with Practice E2215 to evaluate the post-irradiation test measurements.
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归口单位: E10.02
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