先进中子学栅格程序KYLIN-2中特征线方法模块的开发与验证

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基金项目:

总装重点实验室基金(9140C730102140C73019)

Development and Verification and Validation of MOC Module in Advanced Neutronics Lattice Code KYLIN-2

1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610041, China;
2. Nuclear Power Insititute of China, Chengdu, 610041, China

摘要: 针对先进核反应堆中结构复杂的燃料组件,基于特征线中子输运计算方法,在先进栅格计算程序KYLIN-2中开发能够满足各类燃料组件中子学数值模拟的输运计算模块。分别利用循环射线布置和射线反向延长追踪技术处理特定和任意边界条件问题,同时采用广义粗网格有限差分加速方法(GCMFD)来加速中子输运求解流程。数值结果表明,开发的特征线方法模块具有较高的计算精度,满足未来工程使用的需求。
- 核反应堆 /
- 中子输运方程 /
- 特征线方法 /
- 射线追踪 /
- 广义粗网格有限差分加速方法
Abstract: In order to simulate the complex fuel assembly in the advanced nuclear reactor, the method of characteristics（MOC） calculation module is developed in neutronics lattice code KYLIN-2. The MOC module adopts cyclic trajectory layout and angle quadrature set for special geometrical shapes, and uses ray prolongation method for other general geometrical shapes. The generalized coarse mesh finite differential（GCMFD） acceleration method is adopted in the MOC module. The numerical results show that the MOC module in KYLIN-2 code can calculate 2D neutronics problems accurately, and can be used in future reactor design.
- Nuclear reactor /
- Neutron transport equation /
- Method of characteristics /
- Ray tracing /
- Generalized coarse mesh finite differential method