Platform Architecture And Control Panel Design For CEFR Simulator

The safe and economic operation of nuclear power plants or reactors, on one hand, depends on the level of design, construction and maintenance, on the other hand, is also affected by the professional level of operators. Therefore, a list of methods are supposed to be effective and helpful to improve the level of security and economic efficiency of the nuclear power plants and reactors, such as discovering and correcting the mistakes or defect in the design, eliminating hidden safety problems during the operation as promptly as possible, assessing the possibility of incidents and safety allowance objectively, and improving the operators'technical merit. However, a nuclear power station in service is not suitable or allowed for training operators, because incorrect operations by the new operators may cause major hidden dangers to the normal running of a nuclear power station. Furthermore, a nuclear power plant in regular service cannot be used to perform incident excise. As a result, the establishment of the nuclear power plant simulator seems to be the key to the problem discussed above, as it can be used to perform nuclear safety analysis and also to simulate similar situations to train the operators. This paper describes the research based on the theories of simulation system architecture and also the design and development of a simulator. The simulator is described including several theoretic options for the Distributed Component technology. The simulator is based on the Dynamic Link Library architecture that allows LabVIEW to call Fortran, which preliminarily completes the basic simulator of CEFR. The major purpose of simulator is to simulate the CEFR, the analysis of severe accident in nuclear power plant and probabilistic safety assessment(PSA). The main purpose of the paper is to design and construct fast reactor simulator based on SAC-CFR which has self-developed and the Dynamic Link Library architecture to perform real time or faster than real time transient analysis in the circumstances of normal, abnormal running or incidents. Combined with the results of the simulation analysis and the probabilistic safety analysis software, we can then assess the equipment, design, operation and control system of the nuclear power plants.