1.1本指南描述了熔丝温度监测器的应用及其在实践E 185中要求的轻水动力反应堆反应堆容器监督中的使用。 1.2本指南的目的是推荐选择和使用普通熔线技术，其中熔化温度和不同合金成分之间的对应关系被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本标准无意解决与其使用相关的所有安全问题（如有）。 本标准的用户有责任在使用前制定适当的安全和健康实践，并确定监管限制的适用性。 （见注1。） ====意义和用途====== 根据规程E 2215，在监测舱中使用温度监测器 验证监测样本辐照温度的估计值。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。由于过热导致监测样本的中子辐射损伤量减少，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非保守预测。 过热辐射损伤的减少程度取决于材料的成分和温度下的时间。指南E 900 提供了一种公认的方法来量化温度效应。由于熔丝监测器的证据没有表明过热持续时间高于监测器熔化所指示的预期温度，因此无法仅根据热监测器来量化过热事件的重要性。过热指示确实有助于提醒用户数据，以进一步评估监测舱的辐照温度暴露历史。 本指南是Master Matrix E 706的IIIE 这涉及用于轻水反应堆容器材料辐照监测的几个标准。 其主要目的是扩大实践E 185的要求 在监控程序的温度监测器设计中。它也可以与规程E 2215一起使用 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 Practice E 185. 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 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 and health practices and determine the applicability of regulatory limitations prior to use. (See Note 1.) ====== Significance And Use ====== Temperature monitors are used in surveillance capsules in accordance with Practice E 2215 to verify the estimated 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. The magnitude of the reduction of radiation damage with overheating depends on the composition of the material and time at temperature. Guide E 900 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 thermal 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. This guide is IIIE of Master Matrix E 706 that relates several standards used for irradiation surveillance of light water reactor vessel materials. It is intended primarily to amplify the requirements of Practice E 185 in the design of temperature monitors for the surveillance program. It may also be used in conjunction with Practice E 2215 to evaluate the post-irradiation test measurements.