Research on RMC neutronics-thermal hydraulics coupling based on universal coupling methodology
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摘要: 在自主堆用蒙卡程序RMC内部开发的热工水力子通道功能模块 RMC-TH以及蒙特卡罗几何栅元计数器的基础上,研究并开发了通用型内耦合接口。与传统依赖文件传递信息的外耦合相比,该耦合方式对两种物理过程使用统一的输入文件,利用重复结构热工反馈栅元展开技术,可以实现物理-热工大规模几何模型的快速内部对应,突破了以往核热耦合程序通用性的限制;截面更新方面,采用在线多普勒展宽法(OTF)实现温度对中子截面的反馈作用。该方法只需加载0 K的截面库,可以降低对计算机内存的需求,提高计算效率。以单棒及典型压水堆PWR1717组件为例,对核热耦合过程进行了稳态模拟分析,结果证明了内耦合方法的可行性、正确性及高效性。Abstract: RMC is a self-developed Monte Carlo software for nuclear reactor analysis by Reactor Engineering Analysis Lab(REAL), Tsinghua University. On the basis of the self-developed subchannel modular(RMC-TH) and Monte Carlo CellTally the inner coupling interface is developed, which combines both input files and realizes the fast mesh correspondence process using the cell expansion technology for repeat structure with thermal hydraulics feedback, and it breaks through the threshold of geometrical variability and extensibility for coupled code. On-The-Fly Doppler broaden method is adopted considering the temperature effect on micro cross section, which only needs the 0K cross section library so that the memory cost can be apparently reduced. Steady state simulation analysis are performed on single rod and 1717 assembly model, and the results show the feasibility, accuracy and efficiency of the coupling methodology, so the technology roadmap and methodology foundation for the large scale and geometrically variable reactor steady-state as well as transient neutronics simulation with thermal hydraulic feedback and further neutronics-thermal hydraulics-depletion multi-physics simulation process are established.
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Key words:
- RMC /
- neutronics-thermal hydraulics coupling /
- inner coupling /
- subchannel code /
- Monte Carlo
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