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Summary of thermocouple performance during advanced gas reactor fuel irradiation experiments in the advanced test reactor and out-of-pile thermocouple testing in support of such experiments

机译:在高级测试反应堆中进行的高级气体反应堆燃料辐照实验期间的热电偶性能摘要以及支持此类实验的堆外热电偶测试

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High temperature gas reactor experiments create unique challenges for thermocouple-based temperature measurements. As a result of the interaction with neutrons, the thermoelements of the thermocouples undergo transmutation, which produces a time-dependent change in composition and, as a consequence, a time-dependent drift of the thermocouple signal. This drift is particularly severe for high temperature platinum-rhodium thermocouples (Types S, R, and B) and tungsten-rhenium thermocouples (Type C). For lower temperature applications, previous experiences with Type K thermocouples in nuclear reactors have shown that they are affected by neutron irradiation only to a limited extent. Similarly, Type N thermocouples are expected to be only slightly affected by neutron fluence. Currently, the use of these nickel-based thermocouples is limited when the temperature exceeds 1000??C due to drift related to phenomena other than nuclear irradiation. High rates of open-circuit failure are also typical. Over the past 10 years, three long-term Advanced Gas Reactor experiments have been conducted with measured temperatures ranging from 700??C???1200??C. A variety of standard Type N and specialty thermocouple designs have been used in these experiments with mixed results. A brief summary of thermocouple performance in these experiments is provided. Most recently, out-of-pile testing has been conducted on a variety of Type N thermocouple designs at the following (nominal) temperatures and durations: 1150??C and 1200??C for 2,000 hours at each temperature, followed by 200 hours at 1250??C and 200 hours at 1300??C. The standard Type N design utilizes high purity, crushed MgO insulation and an Inconel 600 sheath. Several variations on the standard Type N design were tested, including a Haynes 214 alloy sheath, spinel (MgAl2O4) insulation instead of MgO, a customized sheath developed at the University of Cambridge, and finally a loose assembly thermocouple with hard-fired alumina insula- ion and a molybdenum sheath. The most current version of the High Temperature Irradiation Resistant Thermocouple, based on molybdenumiobium alloys and developed at Idaho National Laboratory, was also tested.
机译:高温气体反应器实验对基于热电偶的温度测量提出了独特的挑战。作为与中子相互作用的结果,热电偶的热电偶发生trans变,这会导致成分随时间的变化,从而导致热电偶信号随时间的漂移。对于高温铂铑热电偶(S,R和B型)和钨-热电偶(C型),这种漂移尤为严重。对于较低温度的应用,以前在核反应堆中使用K型热电偶的经验表明,它们仅在有限程度上受到中子辐照的影响。同样,N型热电偶仅会受到中子注量的轻微影响。当前,当温度超过1000℃时,由于与核辐射以外的现象有关的漂移,这些镍基热电偶的使用受到限制。高开路故障率也是典型的。在过去的十年中,已经进行了三个长期的先进气体反应器实验,测量的温度范围为700℃C 1200℃。在这些实验中,已经使用了多种标准的N型标准和特殊的热电偶设计,但结果却不尽相同。提供了这些实验中热电偶性能的简要概述。最近,在以下(标称)温度和持续时间下,对各种N型热电偶设计进行了桩外试验:在每个温度下1150?C和1200?C进行2,000小时,然后进行200小时在1250℃和1300℃下200小时。标准的N型设计采用高纯度,压碎的MgO绝缘材料和Inconel 600护套。测试了标准N型设计的几种变体,包括Haynes 214合金护套,尖晶石(MgAl2O4)代替MgO的绝缘层,剑桥大学开发的定制护套,最后是带有硬质氧化铝​​绝缘层的松散组装热电偶,离子和钼护套。还测试了爱达荷州国家实验室开发的基于钼/铌合金的最新版本的耐高温辐射热电偶。

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