Simulator Of Nuclear Power Plant For Teaching And Internship

Nuclear power simulation technology can simulate the normal operating conditions and accident status of real nuclear power plant, which provide support for the technical personnel to master the Normal operation and abnormal operation method of nuclear power plant. At present, there are various kinds of virtual simulation products in the field of nuclear power simulation, such as full range simulator, serious accident simulator, simulation analysis machine, teaching and training simulator. The teaching and training simulator is generally based on the PC as the working platform, which is compatible with the commonly used Windows operating system. It can simulate the thermal system and control system by using the physical model and mathematical model, which operate the device by means of the device soft control window, mouse and keyboard. Based on the graphical and modular modeling method, the thermal system dynamic mathematical model of Tianwan VVER-1000 PWR nuclear power plant is established. Based on the B/S model, the virtual DCS system is build, which form a simple simulation system together with the thermal model. The simulation system provides a modern tool for the teaching internship of students major in nuclear power. The main contents and results are summarized as follows:?A graphical simulation modeling system based on Browser/Sever model is built. It adopts the modular modeling idea, and the modeling step of the pressurized water reactor nuclear power plant is divided into the equipment layer or module layer, the system layer and the unit layer. Device module is developed using ActiveX control and LIB dynamic link library technology, communication program is developed based on shared memory and Soket communication technology. The graphics modeling page of thermal system is painted on FrontPage by calling the embedded ActiveX control. The Graphics conversion program that use module capture technology can convert the graphical modeling HTML page to the model program on C++language form. The modeling system behaved well at generality, portability and extensibility, whose device module library can be extend based on the new modeling object.?Virtual instrument control system program VDCS is integrated. Virtual controller program of TXP and TXS is constructed by using the virtual AP/FDG mode. The virtual HMI interface is created by in WEB pages which embed the dynamic macro elements. The virtual control block and dynamic macro elements are built. Based on the Soket communication mode, the communication between the VPLANT model program, TXP and TXS is completed.?According to the structure and thermodynamic properties of thermal equipment of Tianwan PWR nuclear power plant, the dynamic mathematical model of the key equipment is created by using the basic thermal hydraulic equation and lumped parameter method, such as steam generator, steam turbine unit, feed water heater, regulating valve, etc. The equipment model program is written in C++ by using the object-oriented programming method, which is placed on the LIB library for model program total thread to call. Besides, the fluid network model based on node pressure method is established. The fluid network model solving program is written in the form of matrix equation that is beneficial for the program of last layer to call. The topological relations of model can be identified by the graph transformation program which is used to create the model program of the thermal system.?Taking the technical data of Tianwan nuclear power plant thermal system and the HMI of Tianwan DCS system as reference, graphical modeling HTML pages of the main thermodynamic system of nuclear power plant are painted, which convert to the model program VPALNT. Basic function test of VPLANT and VDCS indicate that the virtual system meet the basic requirements of teaching internship. Static and dynamic experiments which carry out on the valve module program and fluid network solution program based on node pressure method indicate that the change of pressure in the fluid network is calculated accurately by the model program, and that model of valve can accurately reflect the flow characteristic curve of the real valve. Static and dynamic experiments on the high pressure heater show that the model can simulate the behavior of HPH-6A when its flow rate of feed water increase or its flow rate of extract steam decrease.