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Effective Thermal Conductivity Method for Predicting Spent Nuclear Fuel Cladding Temperatures in a Dry Fill Gas

机译:预测干式填充气体中乏核燃料包壳温度的有效热导率方法

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The effective thermal convductivities developed here provide a method fo rpredicting (with a high level of confidence) a "best estimate" of peak cladding temperatures fo rspent nuclear fuel (SNF) assemblies in a dry environment. This paper describes the development of effective thermal conductivies for PWR and BWR assemblies as a methodology for performing SNF container thermal analyses. Over-predicting SNF cladding temperatures due to excessive conservatism can constrain container design and limit the capacity of potential design concepts. The analyses performed here indicate that the discrete SNF models are more accurate and realistic than other approaches for predicting SNF cladding temperatures. Further, the efective thermal conductivities, calculated using the SNF model results, wre found to be primarily a function of temperature, generally not a function of assembly heat load, and suitable for predicting best-estimate temperatures of PWR and BWR SNF assemblies in fill environments of helium, vacuum, nitrogen, and argon.
机译:这里开发的有效热导率提供了一种预测(具有高置信度)干燥环境中核燃料(SNF)组件峰值包层温度的“最佳估计值”的方法。本文介绍了用于PWR和BWR组件的有效热导率的开发方法,作为进行SNF容器热分析的一种方法。由于过度保守而过度预测SNF包层温度会限制容器设计并限制潜在设计概念的能力。此处进行的分析表明,与其他用于预测SNF包层温度的方法相比,离散SNF模型更为准确和现实。此外,发现使用SNF模型结果计算的有效导热系数主要是温度的函数,通常不是组件热负荷的函数,并且适合预测填充环境中PWR和BWR SNF组件的最佳估计温度氦,真空,氮气和氩气。

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