Development and Verification of Direct Transport Code KuaFu

被引：0
作者：
Zhao C. [1 ]
Peng X. [1 ]
Zhao W. [1 ]
Yu Y. [1 ]
Li Q. [1 ]
机构：
[1] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2021年 / 42卷 / 01期
关键词：
2D/1D transport method; C5G7; benchmark; Direct transport calculation; KuaFu;
D O I：
10.13832/j.jnpe.2021.01.0211
中图分类号：
学科分类号：
摘要：
To develop the adaptability of the direct transport method for advanced reactors with complicated geometry, the constructive solid geometry method and the 2D/1D transport method were adopted in a newly-developed direct transport code KuaFu. C++/Python hybrid programming was used. A 2D/1D transport solver with CMFD acceleration method and parallel technology was developed in KuaFu. With the validation of the C5G7 benchmark, these techniques were evaluated, and the difference between KuaFu and Monte-Carlo code MCNP are listed. All results show that KuaFu is with good accuracy compared with reference results. The CMFD and parallel method improves the efficiency significantly. © 2021, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.
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页码：211 / 216
页数：5
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