The translation-based virtual DCS based on Simulink can realize the function of virtualizing the physical DCS. This paper presents a method to virtualize physical DCS by using Simulink to realize the functions of running, freezing, acceleration and deceleration, setting and acquiring variable values, malfunction simulation, snapping and loading initial conditions, etc. Virtual DCS realizes the configuration translation by translating the configuration files of the physical DCS platform to Simulink platform, generating codes by using the configuration, and compiling the codes into algorithm files. The virtual DCS is combined with process model software to form a closed-loop, which simulates the level control system of the steam generator of a megawatt pressurized water reactor nuclear power plant for verification. Effective results have been achieved, which proves that the translation virtual DCS can meet the simulation effect of the simulator.

System Availability, Rejection rate and Malfunction rate are vital technical indicators for safety class DCS when evaluating the reliability of the control system to meet technical requirements. This trend has attracted great attention of equipment manufacturers, regulatory agencies and users. Since there is no relevant standards or norms to guide the restriction at this stage, there is no unified verification idea in the industry. Although domestic and foreign equipment enterprises have tried relevant verification research, it still remains at the level of theoretical analysis and the confidence is not high. In the research of test method, if the traditional test simulation method is used for index verification, it often requires a lot of manpower, material resources and time. Therefore, this method is also regarded as inoperable, so it has not been able to form a reasonable and mature test of the verification scheme for a long time. Based on the general principle of reliability analysis, this paper makes a comparative analysis of the objects of reliability test, and proposes a reliability analysis verification and implementation scheme of safety class DCS.

The nuclear reactor 1E DCS priority logic module is one of the very important components of the nuclear reactor I&C (Instrument and Control) system. Its main function is to prioritize different DCS control command, and then drive especial safety facilities and related support systems (pumps, valves and other related equipment). Driven devices such as pumps, valves, etc. need to execute related functions according to the drive signals issued by the priority logic modules. The characteristics and advantages between seven kinds of domestic and international priority logic modules are analyzed by comparing their function and implementation mode. Comparison shows that different manufacturers' products also have their own characteristics. At present, many companies at home and abroad have designed different priority logic modules based on their own ideas. However, the public literature about priority logic modules is very limited, let alone summary analysis about it. Therefore, this paper has important engineering significance and reference value for the design of priority logic module.

As key equipment in nuclear power plant, the reactor power control system is adopted to strictly control and regulate the reactor power of a PWR (pressurized water reactor) in a nuclear power plant. A well-optimized predictive control algorithm based on SDMC (stepped dynamic matrix controller) is developed and introduced in this paper and applied to the power regulation of a reactor power model. In addition, the test and verification of this application is conducted by two different methods and devices: the virtual verification platform and the physical DCS (digital control system). The result of the verification suggests that the application of SDMC gains a better performance in the maximum dynamic deviation, adjustment time, overshoot, and so on.