摘要
针对先进核反应堆中结构复杂的燃料组件,中国核动力研究设计院开发了先进中子学栅格中子学程序KYLIN-2,该程序采用子群方法进行共振处理,采用特征线方法(MOC)进行复杂几何中子输运计算,并利用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,采用基于改进预估校正临界-燃耗迭代方法(PPC)的切比雪夫方法求解复杂燃耗链,同时,为了方便用户使用,开发形成了支持复杂组件图形化建模工具和后处理显示工具。通过初步的数值检验,针对典型压水堆燃料组件,KYLIN-2具有较高的计算精度,满足工程使用需求。
In order to simulate the complex structure fuel assembly, Nuclear Power Institute of China（NPIC） has developed an advanced neutron transport lattice code, named KYLIN-2. The subgroup method is adopted in KYLIN-2 to treat resonance problems. And method of characteristics（MOC） is used to solve neutron transport equation and generalized coarse mesh finite difference（GCMFD） method is used to accelerate the calculation. In order to solve the depletion equation, CRAM method and PPC method are used. The graphical input and display interface are developed to make sure the KYLIN-2 code can be used easily by engineers. The numerical results show that the KYLIN-2 can calculate the PWR assembly accurately.
出处
《强激光与粒子束》
EI
CAS
CSCD
北大核心
2017年第1期90-96,共7页
High Power Laser and Particle Beams
基金
核反应堆系统设计技术重点实验室基金项目(9140C730102140C73019)
