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Numerical simulation of decay heat scattering out of AP1000 nuclear reactor spent fuel cask based on finite element method

机译:基于有限元法的AP1000核反应堆腐烂热散射的数值模拟

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The heat transfer performance of the spent fuel transport cask is inseparably related to the safety of the whole reprocessing system. In this study, we carried out the thermal analysis on the NAC-STC transport cask for AP1000 spent fuel assembly to evaluate the thermal performance of transport cask by the finite element method software ANSYS. A computational dynamics model was developed to study the temperature distribution inside the transport cask and on the surface of the cask. The effectiveness of the numerical calculation is demonstrated by comparing with the theoretical results. The results show that transport cask can reach steady-state during transportation, and the highest temperature in the case is 328°C, which is below the maximum safety limit of 400°C. Besides, the temperature of the fuel element baskets, sealing ring, photon shielding layer and neutron shielding layer in the cask are all within the safety limit.
机译:花费燃料运输桶的传热性能与整个后处理系统的安全性密不可分。在这项研究中,我们对AP1000废燃料组件的NAC-STC运输桶进行了热分析,以通过有限元方法软件ANSYS评估运输桶的热性能。开发了一种计算动力学模型,以研究运输桶内的温度分布和桶的表面。通过与理论结果进行比较来证明数值计算的有效性。结果表明,运输桶可在运输过程中达到稳态,壳体的最高温度为328°C,低于400°C的最大安全限度。此外,燃料元件筐,密封环,光子屏蔽层和中子屏蔽层的温度均在安全极限内。

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