超临界水冷堆核热耦合计算研究

留言板

尊敬的读者、作者、审稿人, 关于本刊的投稿、审稿、编辑和出版的任何问题, 您可以本页添加留言。我们将尽快给您答复。谢谢您的支持!

姓名

邮箱

手机号码

标题

留言内容

验证码

Study on Neutronic-Thermohydraulic Coupling Calculation of SCWR

1. School of Physics and Engineering, Sun Yat-sen University, Guangzhou, 510275, China;
2. Sino-French Institute of Nuclear Engineering & Technology, Sun Yat-sen University, Guangzhou, 510275, China

摘要: 以美国超临界水堆(SCWR)设计为研究对象,开发超临界水堆的物理-热工耦合计算程序。该计算程序采用Dragon和Donjon直接耦合计算,提高计算精度和速度;并在功率迭代中引入松弛因子,通过部分迭代法解决传统迭代方法不收敛的问题。轴向温度和密度分布的计算结果验证了程序的有效性和准确性。
- 超临界水堆 /
- 核热耦合 /
- 部分迭代法
Abstract: Based on the U.S. SCWR design, the thermohydraulic module is coupled with neutronic codes Dragon and Donjon directly, to develop a calculation codes for neutronic/thermohydraulic coupling, which can improve the accuracy and efficiency of coupling calculation. The relaxation factor is introduced to solve the problem of misconvergence of traditional successive iteration for new reactors such as SCWR. Key parameters have been calculated and analyzed to prove the feasibility and accuracy of the developed calculation codes. The study provides the basis for further study of stability and safety analysis for new SCWR.
- Supercritical water-cooled reactor /
- Neutronics/thermal-hydraulics coupling /
- Partitioned iterative approach