A microcomputer code MACONP/MOD1.0 for PWR nuclear power plant high-speed safety analysis is developed successfully in this paper. The mathematical model of this code mainly includes reactor core heat transfer model, point-reactor kinetic model, pressurizer model, U-tube steam generator model as well as flow field models and fluid property equations related to the above system models. The code has friendly interface and is very convenient for users. Several transients of qinshan Nuclear Power Plant are analyzed by the code, and results agree well with ones of the RELAP5/MOD2 code.
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