反应堆FPGA保护子系统开发与验证

Development and Verification of FPGA- based Reactor Protection Subsystem

验证与确认(V&V)方法是FPGA在核安全级仪控系统中应用所面临的关键问题之一。本研究以CPR1000核电机组一次冷却剂流量和ΔT保护系统为对象,进行基于FPGA的系统开发和V&V研究,提出了FPGA仪控系统的开发、V&V过程和方法。采用通用验证方法学(UVM)和第三方仿真工具确保硬件描述语言(HDL)代码获得100%的测试覆盖率,借助核电厂原理模拟机开展集成测试。研究结果为FPGA反应堆保护系统的开发、V&V和评审提供了理论和技术参考。

Verification and Validation method is one of the key problems in the usage of FPGA in nuclear power plant safety instrumentation and control system. In this research, the primary loops coolant flow protection and delta T protection subsystems in CPR1000 NPP are chosen as the research subjects. Based on FPGA, the system development and V＆V method research are conducted. The development process of FPGA instrumentation and control system, and its V＆V processes and methods are proposed. Using the Universal Verification methodology and the third - party simulation software ensures the 100 percent test coverage of the HDL codes; Withthe NPP simulator, the integration verification is executed. The research results provide the theory and the technical reference to the development, V＆V and the review of FPGA - based reactor protection system.