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Joint tests at INL and CEA of a transient hot wire needle probe for in-pile thermal conductivity measurement

机译:瞬态热线针探针的InL和CEA的联合试验,用于桩内导热率测量

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Thermal conductivity is a key property that must be known for proper design, testing, and deployment of new fuels and structural materials in nuclear reactors. Thermal conductivity is highly dependent on the physical structure, chemical composition, and the state of the material. Typically, thermal conductivity changes that occur during irradiation are currently measured out-of-pile using a "cook and look" approach. But repeatedly removing samples from a test reactor to make measurements is expensive, has the potential to disturb phenomena of interest, and only provides understanding of the sample's end state when each measurement is made. There are also limited thermo-physical property data available for advanced fuels; and such data are needed for simulation codes, the development of next generation reactors, and advanced fuels for existing nuclear plants. Being able to quickly characterize fuel thermal conductivity during irradiation can improve the fidelity of data, reduce costs of post-irradiation examinations, increase understanding of how fuels behave under irradiation, and confirm or improve existing thermal conductivity measurement techniques. This paper discusses efforts to develop and evaluate an innovative in-pile thermal conductivity sensor based on the transient hot wire thermal conductivity method (THWM), using a single needle probe (NP) containing a line heat source and thermocouple embedded in the fuel. The sensor that has been designed and manufactured by the Idaho National Laboratory (INL) includes a unique combination of materials, geometry, and fabrication techniques that make the hot wire method suitable for in-pile applications. In particular, efforts were made to minimize the influence of the sensor and maximize fuel hot-wire heating. The probe has a thermocouple-like construction with high temperature resistant materials that remain ductile while resisting transmutation and materials interactions. THWM-NP prototypes were fabricated for bot- room temperature proof-of-concept evaluations and high temperature testing. Evaluations have been performed jointly by the INL and the French Alternative Energies and Atomic Energy Commission (CEA), both in Idaho Falls (USA) and in Cadarache (France), in the framework of a collaborative program for instrumentation of Material Testing Reactors. Initial tests were conducted on samples with a large range of thermal conductivities and temperatures ranging from 20 ??C to 600 ??C. Particularly, tests were recently performed on a sample having thermal conductivity and dimensions similar to UO2 and MOX nuclear fuels, in order to validate the ability of this sensor to operate for in-pile characterization of Light Water Reactors fuels. The results of the tests already completed at INL and CEA indicate that the Transient Hot Wire Needle Probe offers an enhanced method for in-pile detection of thermal conductivity.
机译:热导率是必须进行适当的设计,测试和新燃料和核反应堆结构材料的部署被称为一个关键属性。热导率是高度依赖于物理结构,化学组成,并且该材料的状态。通常,照射过程中发生的热导率的变化当前测量外的桩使用“煮和外观”的方法。但是从反复试验反应堆取出样品进行测量是昂贵的,有兴趣干扰现象的潜力,并且只提供了解样品的最终状态时每个测量。也有限制可用于先进的燃料热物理特性的数据;并且需要对模拟代码,下一代反应堆的发展,并为现有核电站先进燃料这样的数据。照射时能够快速表征燃料的热导率可以提高数据的保真度,降低照射后的考试成本,增加的燃料照射下的行为的理解,并确认或改进现有的导热系数测量技术。本文讨论的努力,开发和评估基于瞬态热丝热导法(THWM)一种创新的在桩热导率传感器,使用含有线热源的单针探针(NP)和热电偶嵌在燃料。已经由爱达荷国家实验室(INL)设计和制造该传感器包括的,使适合在桩应用的热丝法的材料,几何形状,和制造技术的独特结合。特别地,已作出努力,以最小化传感器和最大化燃料热丝加热的影响。该探头具有一热电偶状结构与维持延性,同时抵抗嬗变和材料的相互作用耐高温材料。 THWM-NP原型制造用于bot-室验证的概念温度评价和高温测试。经过评估,被INL和法国替代能源与原子能委员会(CEA),无论是在爱达荷瀑布(美国)和在卡达拉舍(法国)联合进行的,在材料试验反应堆仪器仪表的合作方案的框架。初始测试是用一个大范围的热导率和温度范围从20 24 C 600 24 C的样品上进行的。特别是,试验最近在具有热传导性和尺寸类似于UO2和MOX核燃料的样品进行的,以验证该传感器用于在桩轻水反应堆燃料的特性工作的能力。在INL和CEA已经完成测试的结果表明,瞬态热丝针探头提供了一种强有力的方法在桩检测的热导率。

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