摘要
子通道分析软件CORTH基于具有滑速比的四方程模型,适用于反应堆堆芯或加热棒束实验热工水力分析。CORTH软件的研发采用模块化设计和面向对象的编程语言,针对输入和输出特别设计了图形化的用户界面。软件通过了独立的第三方测试,检验了编码的可靠性和规范性。利用核电厂实测数据、国际基准题和AP1000额定工况对软件进行验证。结果表明,CORTH软件的计算精度较高,与国际同类软件相当,能够满足工程设计与分析需求。
CORTH is a subchannel code self-reliant developed by Nuclear Power Institute of China （NPIC） based on four equation model with slip ratio to perform thermal-hydraulic analysis of reactor cores or experimental facility with heating rod bundles. The development of CORTH adopted modular design and object-oriented programming method, and specially provided with graphic user interface for input deck preparing and output analysis. CORTH has been executed software testing by independent third organization to ensure the readability and standardization of coding. Testing data in NPPs, international benchmark and AP 1000 nominal condition were used to carry out verifications and validations of CORTH. The results show the good accuracy of CORTH that meets the requirement of engineering design and analysis.
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2017年第6期157-162,共6页
Nuclear Power Engineering
