Abstract
With the rapid improvement of computer performance and solving algorithms, the high-precision simulation of nuclear power plant becomes more and more practical. The main advantage of high-precision simulation is that it can improve the prediction range of safety parameters and identify the main influencing parameters. This involves the research of many physical processes, including the solution of complex problems of thermal hydraulics with other disciplines or different fields (such as primary system and containment). The coupling program can be used as a favorable method for nuclear reactor core safety analysis, and it can simulate and predict the behavior of nuclear power plant more accurately and in detail, thus further improving the safety and economy of nuclear power plants. The interaction between neutron dynamics and thermal hydraulics is very important for safety analysis and accurate prediction of local parameters. The coupled analysis program of hydraulics and containment can reasonably simulate the response of reactor system and containment in LOCA at the same time. Most coupled programs are developed by integrating an independent program in the most appropriate way. The main purpose of this development model is to provide a more realistic description of key phenomena for reactor design and safety, thus reducing conservatism introduced in the traditional program calculation process. Coupling program must consider coupling method (integration algorithm or parallel process, internal or external coupling), spatial map** scheme and time synchronization algorithm. The coupling program can be based on a modern and user-friendly simulation platform, such as GENUS. It has powerful functions of preprocessor and post-processor, and can easily realize the coupling of multiple programs according to the specific needs of users. In this paper, the present situation of coupling thermal hydraulics with three-dimensional neutron physics, containment program and other system programs is introduced, and the coupling schemes, simulation platforms and applications of different programs are discussed.
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Zhou, S. et al. (2023). Research on Interface Technology of Coupling Thermal-Hydraulics and Other Codes. In: Liu, C. (eds) Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3. Springer Proceedings in Physics, vol 285. Springer, Singapore. https://doi.org/10.1007/978-981-19-8899-8_77
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DOI: https://doi.org/10.1007/978-981-19-8899-8_77
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