堆芯物理-热工水力分析软件DCNMC开发与初步验证  

Development and Abecedarian Verification of Reactor Core Physic and Thermal-Hydraulic Analysis Software Package DCNMC

作　　者：周旭华[1,2] 蔡琦[1] 王登营 李富[3] 伊雄鹰 

机构地区：[1]海军工程大学核能科学与工程系,武汉430033 [2]北京核化安全研究所,北京100077 [3]清华大学核能与新能源技术研究院,北京100084

出　　处：《核动力工程》2013年第6期55-60,共6页Nuclear Power Engineering

基　　金：中国博士后科学基金第49批一等面上资助(20110490190)

摘　　要：针对特定类型核动力反应堆的特点,以DRAGON程序为反应堆组件均匀化参数计算内核,以CITATION程序、NGFM程序、MCNP程序为堆芯物理计算内核、以COBRA程序为堆芯热工水力计算内核,以自主开发的组件少群均匀化参数加工处理程序DOCS和反应堆-物理热工计算主程序DCNMC为接口程序和计算内核管理程序,开发形成一套具有较好通用性的特定类型反应堆堆芯物理-热工计算分析软件,并以特定反应堆为对象,完成计算模型开发、初步验证与校正。结果表明:该程序包可用于某特定堆堆芯物理-热工计算分析,精度满足要求。With a view to the characteristics of the specific type nuclear reactor, five reactor core physic and thermal-hydraulic codes are integrated into the software package as calculation kernel. In the software package, the Dragon code is applied to calculate the homogenized few group constant for fuel assembly, the CITATION code, NGFM code and MCNP code are applied for core physic calculation with different methodology, the COBRA code is applied for core thermal-hydraulic calculation. In addition two homegrown codes named as DOCS and DCNMC are used as data transmission interface tool and calculation management tool.. Then, a generic reactor core physic and thermal-hydraulic analysis software for the specific type nuclear reactor is developed. A calculation model on some reactor core is established. Then, the accuracy of the code system and model is verified, and the results indicate the accuracy meets the requirements.

关 键 词：反应堆物理 反应堆热工水力 格林函数节块法 并行计算 

分 类 号：TL329.2[核科学技术—核技术及应用]