摘要
面向下一代反应堆堆芯分析的多功能栅格物理程序(SONG)采用特征线方法(MOC)求解任意几何区域内的中子输运方程,可灵活模拟由棒状元件或板状元件组成的矩形栅格或六角栅格的两维燃料组件模型或两维堆芯模型。程序采用指数矩阵方法求解拓展的裂变产物链和全锕系嬗变链,以满足超长寿期、超深燃耗的钍铀燃料循环或铀钚燃料循环计算的功能需求。相关验证计算结果表明SONG程序满足预期要求。
SONG, a multi-functional lattice code focusing on the core analysis of next-generation reactor systems, adopted Method Of Characteristics(MOC) to solve the neutron transport equation with arbitrary geometry. It can simulate flexibly the two-dimensional fuel subassembly model or core model with rectangular lattice or hexagonal lattice, which consist of pin-type or plate-type fuel elements. To meet the demands of calculation on thorium-uranium and uranium-plutonium fuel cycle with extra-long lifetime and extra-deep burnup, the exponential matrix method is adopted to solve the problem of extended fission products and actinides chain. Verification shows that SONG satisfies the anticipated performance and function requirements.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2014年第S2期112-115,共4页
Nuclear Power Engineering
基金
国家自然科学基金重点支持项目(91326201)