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Reactor Pressure Vessel Cooling Scheme: Selection and Validation for Small Nuclear Power Plants
Atomic Energy ( IF 0.5 ) Pub Date : 2021-06-05 , DOI: 10.1007/s10512-021-00745-4
D. A. Afremov , Yu. G. Dragunov , S. A. Koretskii , V. V. Kudinov , D. G. Kulikov

An analysis of existing and possible designs of high-temperature gas-cooled reactor installations has shed light on the critical elements determining the reactor’s efficiency and reliability; it required determination of approaches to the development and theoretical and experimental substantiation of solutions for such critical units. Among the problems requiring a separate investigation in the development of the concept for the reactor are the selection and validation of the solutions for the cooling system of the reactor’s pressure vessel, which is one of the nuclear and radiation safety barriers. The selection and validation were accomplished using modern software tools, tests, and tests and experimental studies were performed on prototypes. The proposed and substantiated, both computationally and experimentally, scheme of the low-temperature leg that cools the units of the reactor vessel that are sensitive to high temperatures made it possible to reduce the temperature gradient and increase the permissible stresses on the reactor pressure vessel.



中文翻译:

反应堆压力容器冷却方案:小型核电站的选择和验证

对高温气冷反应堆装置现有和可能设计的分析揭示了决定反应堆效率和可靠性的关键要素;它需要确定开发此类关键单元解决方案的方法以及理论和实验证明。在反应堆概念的开发过程中需要单独研究的问题之一是反应堆压力容器冷却系统解决方案的选择和验证,这是核和辐射安全屏障之一。选择和验证是使用现代软件工具完成的,测试和测试和实验研究是在原型上进行的。所提出和证实的,无论是在计算上还是在实验上,

更新日期:2021-06-05
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