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ZPPR Fuel Element Thermal Stress-Strain Analysis

机译:ZPPR燃料元件热应力-应变分析

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The design temperature of high plutonium concentration ZPPR fuel plates is 600°C. Cladding integrity of the 304 L stainless steel cladding is a significant concern with this fuel since even small holes can lead to substantial fuel degradation. Since the fuel has a higher coefficient of thermal expansion than the cladding, an investigation of the stress induced in the cladding due to the differential thermal expansion of fuel and cladding up to the design temperature was conducted. Small holes in the cladding envelope would be expected to lead to the fuel hydriding and oxidizing into a powder over a long period of time. This is the same type of chemical reaction chain that exists in the degradation of the high uranium concentration ZPPR fuel. Unfortunately, the uranium fuel was designed with vents which allowed this degradation to occur. The Pu cladding is sealed so only fuel with damaged cladding would be subject to this damage. The thermal stresses that can be developed in the fuel cladding have been calculated in this paper and compared to the ultimate tensile stress of the cladding. The conclusion is drawn that thermal stresses cannot induce holes in the cladding even for the highest storage temperatures predicted in calculations (292°C). In fact, thermal stress cannot cause cladding failure as long as the fuel temperatures are below the design limit of 600°C (1112°F).
机译:高p浓度ZPPR燃料板的设计温度为600°C。 304 L不锈钢包壳的包壳完整性是这种燃料的一个重要问题,因为即使很小的孔也会导致燃料严重降解。由于燃料的热膨胀系数高于包层,因此研究了由于燃料和包层的热膨胀差异达到设计温度而在包层中引起的应力。预期包层外壳中的小孔会导致燃料在较长时间内氢化并氧化成粉末。这与高铀浓度ZPPR燃料的降解中存在的化学反应链类型相同。不幸的是,铀燃料的设计带有排气孔,可以使这种降解发生。 Pu包层是密封的,因此只有损坏了包层的燃油才会遭受这种损坏。本文已经计算了燃料包壳中可能产生的热应力,并将其与包壳的极限拉应力进行了比较。得出的结论是,即使对于计算中预测的最高存储温度(292°C),热应力也不会在覆层中引起孔洞。实际上,只要燃料温度低于600°C(1112°F)的设计极限,热应力就不会导致覆层失效。

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