The Development Of Arsac For Modeling Nuclear Power Plant System

A new safety analysis code for pressurized water reactors, ARSAC (Advanced Reactor System Analysis Code), is developed to satisfy the new demand for nuclear industry development in China. The code utilizes a hierarchical reactor system model to build the reactor model more conveniently, applies the general non-equilibrium nonhomogeneous Euler-Euler six equation two-fluid models, and adopts a high-efficiency system solving algorithm. A semi-implicit scheme is applied to the conservation equation and a NRLU algorithm is implemented. The code structure of the ARSAC is highly modular with C++ for further improvement. The preliminary code assessment on conceptual, separate effect, and integral effect experiments showed that the prediction is reasonable. The ARSAC code will be used for safety analysis of operating PWRs and the design of innovative reactors including small modular reactors.