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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:瞬态热线探针在INL和CEA的联合测试,用于桩内热导率测量

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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:导热系数是在核反应堆中正确设计,测试和部署新燃料和结构材料所必须知道的关键属性。导热率高度依赖于物理结构,化学成分和材料状态。通常,当前使用“烹饪和外观”方法在堆外测量辐射期间发生的热导率变化。但是从测试反应器中反复取出样品进行测量很昂贵,有可能干扰感兴趣的现象,并且仅在进行每次测量时才了解样品的最终状态。对于高级燃料,热物理性质数据也很有限。这些数据对于仿真代码,下一代反应堆的开发以及现有核电站的先进燃料都是必需的。能够在辐射过程中快速表征燃料的导热系数可以提高数据的保真度,降低辐照后检查的成本,增进对燃料在辐照下的行为的了解,并确认或改进现有的导热系数测量技术。本文讨论了开发和评估基于瞬态热线热导率方法(THWM)的创新的桩内热导率传感器的工作,该传感器使用包含管线热源和嵌入燃料中的热电偶的单针探针(NP)。由爱达荷州国家实验室(INL)设计和制造的传感器包括材料,几何形状和制造技术的独特组合,使热线法适用于桩内应用。特别地,已经努力使传感器的影响最小化并且使燃料热线加热最大化。该探头具有类似热电偶的结构,具有耐高温的材料,可保持韧性,同时抵抗变形和材料相互作用。 THWM-NP原型是为室温下的概念验证评估和高温测试而制造的。 INL和法国替代能源与原子能委员会(CEA)在爱达荷福尔斯(美国)和卡达拉奇(法国)的材料测试反应堆仪器合作计划的框架内共同进行了评估。初始测试是对具有大范围热导率和20至600°C温度范围的样品进行的。特别是,最近对具有类似于UO2和MOX核燃料的热导率和尺寸的样品进行了测试,以验证该传感器为轻水反应堆燃料的堆内表征而运行的能力。 INL和CEA已经完成的测试结果表明,瞬态热线针式探头为堆内导热系数的检测提供了一种增强的方法。

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