摘要
模块式高温气冷堆是国际上公认的安全性好、发电效率高、用途广的先进堆型。本文研究开发了三维圆柱几何堆芯多群中子动力学改进准静态方法模拟计算程序。对给定的模块式高温气冷堆堆芯物理模型进行了模拟计算。初始状态下,该程序计算结果与中子扩散程序CITATION吻合很好。动态情况下,模拟了堆芯反应性、堆芯相对功率以及堆内r,z网格上各群点中子注量率三维分布随时间的变化,计算结果与理论分析一致。
Module High Temperature Gas-cooled Reactor（MHTGR） is well known as an advanced rector type in world nuclear industry.Simulation of the 3D-cylinder reactor core neutron kinetics by improved quasi-static method is studied in this paper,and the computation program is developed.For the supposable MHTGR model,the core neutronics is simulated.At the initiatory state,the calculated result from this code and the one from the neutron diffusion code system CITATION are met with each other very well.The variance of the core reactivity,the relative power,and the 3D distribution of the point neutron flux for each group in r,z mesh along with time are computed for the dynamic simulation of the given model.The simulated results are identical with that of the theoretic analysis.
出处
《核科学与工程》
CSCD
北大核心
2010年第2期135-143,共9页
Nuclear Science and Engineering
基金
国家重大科技专项(2008ZX06902-006)
