V&V Methods Used in the Development of FPGA-based I&C Systems for HTR-10

Abstract

Currently, in few countries, there have been many projects related to the development of Field Programmable Gate Array (FPGA)-based Instrumentation and control (I&C) system designs for their nuclear power plant (NPP), whether for modernization or the new development of NPPs. Indonesia already develops a study related to High Temperature Gas Cooled Reactor as the generation IV for NPPs type for these few years with a specific type which is High Temperature Reactor–10 MW (HTR-10). Since the FPGA-based technology is new in the field, and both the international standards and guidance, from national and international has not defined provisions this issue, therefore verification and validation (V&V) activities for this HTR-10 are mandatory to be included in the design life cycle of I&C system development to get license approval from the national regulatory body. The FPGA-based system needs concentration both in hardware and software development, but commonly only software-related standards that usually included in the design and V&V in the previous computer-based I&C system. Therefore, in this study the V&V plan needs to be developed to state the methods to be required regarding the correctness of the applications of FPGA based I&C system. By arranging this V&V method, we will see whether they are easily applicable to actual systems, had the result to reach the requirement to have reliability, availability, maintainability and safety aspects, and has shortened and easier V&V step than computer-based I&C system. From the results of this study, it can be seen that the results of the method used for V&V between Programmable Logic Controller (PLC)-based and FPGA are almost the same because both have almost the same requirements, especially in software design. Some testing is not mandatory for FPGA-based because of the reduced system complexity. The use of FPGA can shorten the V&V process which can also reduce costs.