摘要
瞬态堆芯耦合模拟软件CTSS V1.0是以节块法堆芯中子学计算软件NACK V1.0、热工水力子通道软件CORTH V2.0、燃料元件性能分析软件FUPAC V1.1为模块的耦合软件,用于模拟典型压水堆堆芯性能,计算瞬态运行物理、热工、燃料等专业参数。堆芯三维时空中子动力学软件NACK V1.0采用粗网节块法进行堆芯扩散计算,为子通道模块和燃料性能分析模块提供堆芯精细功率。CORTH V2.0用于计算反应堆堆芯冷却剂的温度和密度。FUPAC V1.1用于模拟燃料棒在堆内的热力学行为以及计算燃料棒有效温度。NEACRP-L-335压水堆基准问题验证计算结果表明,CTSS V1.0的计算结果与国际基准程序PARCS总体符合较好。
Reactor Core Transient Simulation Software （CTSS VI.0）, which is coupled by 3D space-time kinetic program NACK V1.0, CORe Thermal-Hydraulic analysis program （CORTH V2.0） and Fuel Rod Performance Analysis Code （FUPAC V1.1 ） , is used to simulate the typical PWR core. NACK V1.0 calculates the core diffusion equations with coarse node method and provides core power distribution for sub-channel model and fuel analysis model. CORTH V2.0 describes the core as a series of connected or unconnected sunchannel to calculate the coolant temperature. FUPAC V1 .! is used to simulate the thermodynamic behavior of fuel rod and calculate the fuel rod temperature. The calculation of PWR benchmark problem NEACRP-L-335 shows that CTSS is in uood aureement with benchmark orouram PARCS.
作者
潘俊杰
安萍
王玮
赵文博
邢硕
芦韡
柴晓明
Pan Junjie;An Ping;Wang Wei;Zhao Wenbo;Xing Suo;Lu Wei;Chai Xiaoming(Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institution of China, Chengdu, 610213, China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2018年第2期137-141,共5页
Nuclear Power Engineering
