Real-time Simulation Model And Program Research Of Primary Coolant System Of Pool-type Sodium Cooled Fast Reactor

Based on the structure and physical characteristics of Primary Coolant System (PCS) of China Experimental Fast Reactor (CEFR), a series of reasonable mathematical and physical models were set up. A set of stable and highly active numerical methods were used to solve the models. Then a thermal-hydraulic analysis code for PCS of CEFR in real-time had been developed by FORTRAN programming language. The code had been merged into SimExecTM real-time simulation platform and will be linked to the other systems.Firstly, a series of reasonable mathematical and physical models were set up in this thesis. The models include: basic thermal-hydraulic model of coolant, heat transfer model in fuel pellet, thermal model of intermediate heat exchangers (IHX), hydraulic model of primary pump,loop flow mass rate distribution model,thermo-physical properties of liquid sodium,the flow friction and heat transfer correlations, etc. "Control body" method was put forward in the set of models, Gear method was applied to solve the thermal-hydraulic model of coolant and heat transfer model in fuel pellet. Quasi-newton iteration method was used to solve the flow rate distribution equations. The model and numerical method in this thesis contribute to the accurate and effective of calculation to meet the requirement of real-time simulation.Secondly, the thermal-hydraulic analysis code in real-time for PCS of CEFR was developed with modularized method by FORTRAN language. The design parameters of CEFR were used to validate six different steady-state conditions from 26.5%FP to 100%FP by this code, and the steady-state calculation of the reactor main vessel cooled system was also finished and the results were compared with the datum obtained by other references.Thus the validity and applicability of this code was proved. Then normal operation conditions including planned shutdown of reactor etc were calculated and validated by the manual of PCS of CEFR. Finally, the reactivity insertion accident, loss of coolant accident, and loss of heat sink accident were simulated. The variations of some main parameters such as reactor power, coolant and fuel temperature were obtained and analysis about results were given compared with DINROS calculation results in the final safety analysis report of CEFR. The results showed that the trend of simulation curves for transient condition were reasonable,which were in accordance with actual physical process. In addition,real-time character of the code was analyzed.