The author studied on the modeling and simulation of PWR core and itscontrol systems. The neutron flux distributions are calculated from the 3Ddiffosion equations of two energy groups and six delayed neutron precursors byseparaing the "time" and "space" variables. The following parameters are takenaccount of the effects on reactivity' moderator density boron concentration,xenon and samarium poisoning, control rod positions, moderator and fueltemperature, fuel bum-uP and so on. Basing on the analysis of the mode G, a 3dimension fuzzy control system of boron concentration is designed for loadfollowing. Using the mixed-language programming with C++ and Fortran, thereal-time simulation software is developed. The results of the core model and itscontrol system model are satisfatory. This paPer is helpful to analyze and directfor the full scope simulator of nuclear power station.Duan Xinhui (Thermal Power Engineering)Directed by Pro f Tong Zhensheng...
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