用PARCS／TRACE／ROBIN程序系统研究秦山二期弹棒事故  

Study on the REA in Qinshan Ⅱ by Using PARCS/TRACE/ROBIN Codes

作　　者：冯进军[1] 胡威 周克峰[1] 李明[1] 肖红[1] 柴国旱[1] 

机构地区：[1]环境保护部核与辐射安全中心,北京100082 [2]秦山第三核电厂,浙江海盐314300

出　　处：《核科学与工程》2015年第1期148-156,共9页Nuclear Science and Engineering

摘　　要：利用美国核管制委员会(US NRC)堆芯三维中子动力学软件PARCS、热工水力软件TRACE、辅助建模软件SNAP以及具有国内自主知识产权的压水堆燃料组件计算软件RONBIN,建立了秦山二期两环路压水堆物理模型和热工水力系统模型,进行弹棒事故模拟计算,得出合理的计算结果。AFA 3G燃料组件的两维中子输运计算由ROBIN程序完成,生成的宏观中子截面参数被传递给PARCS程序作为输入。然后由PARCS程序进行堆芯三维弹棒模拟计算,得到事故过程中的核功率变化趋势。最后将反应堆功率瞬态数据输入TRACE热工水力系统模型计算系统压力响应以及燃料包壳和芯块温度。本文通过使用与设计单位完全不同的软件体系,独立地验证了该堆型在弹棒事故下的安全性。The purpose of this paper is to provide an overview of the rod ejection accident （REA） simulation of the two-loop PWR of Qinshan II by using US NRC＇s safety analysis code PARCS/TRACE/SNAP and domestic fuel assembly calculation code ROBIN. The 2D neutron transportation calculation of AFA3G fuel assembly is performed by using ROBIN code. Macro cross sections are obtained from ROBIN outputs and supplied to PARCS code as inputs. Then rod ejection accident is simulated by the PARCS 3D core neutronic model and the reactor power trend is calculated as output of PARCS simulation. Finally, the reactor power trend is input to TRACE thermal hydraulic system model, and the system pressure response is calculated as well as fuel pellet and cladding temperature. Both steady-state and transient calculation are carried out in this paper. The calculation result is reasonable and safety of the specific reactor design is independently verified by using the analysis code that is totally different from design codes.

关 键 词：PARCS TRACE SNAP ROBIN 压水堆 弹棒事故 

分 类 号：TL48[核科学技术—核技术及应用]