摘要
对于一些具有强烈核热耦合行为的新型反应堆(如超临界水堆),一般的迭代方法不再适用。本文基于不动点理论提出核反应堆核热耦合计算的数学模型,结合超临界水堆的计算实例,对核热耦合计算的迭代方法进行收敛性分析,总结出核热耦合计算的收敛判定方法,通过该方法可实时得到迭代的收敛情况,同时提出了自适应松弛因子及其算法,并编写了实现该算法的程序。
The traditional iterative method is not applicable for some new reactors (such as supercritical water-cooled reactor) which have intense neutronic/thermohydraulic coupling (N-T coupling) behavior. The mathematical model of N-T coupling based on fixed point theory is established in this paper, with the calculation examples of SCWR, so as to present the convergence analysis Of iterative methods in N-T coupling. The convergent criterion of N-T coupling is proposed, which can show the real-time convergence situation of iteration. Moreover, the self-adaptive relaxation factor and corresponding algorithm were introduced.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2014年第3期152-157,共6页
Nuclear Power Engineering
基金
"百人计划"引进人才科研启动经费
中央高校基本科研业务费专项资金(11lgpy90)
教育部"新世纪优秀人才支持计划"(NCET-10-0846)
关键词
超临界水堆
核热耦合
收敛性分析
Supercritical water-cooled reactor, Neutronic/thermalhydraulic coupling, Convergence analysis