The development of ARSAC for modeling nuclear power plant system. (October 2021)

• Record Type: Journal Article
• Authors: Deng, Jian; Ding, Shuhua; Li, Zhongchun; Huang, Tao; Wu, Dan; Wang, Jie; Ma, Haifu
• Is Part Of: Progress in nuclear energy. Volume 140(2021)
• Publication Date: 2021-10
• Subjects: Nuclear power plant -- System behavior simulation -- Thermal hydraulic -- Two phase flow; Nuclear energy -- Periodicals; Nuclear engineering -- Periodicals; 333.7924
• DOI: 10.1016/j.pnucene.2021.103880
• Languages: English
• ISSNs: 0149-1970

Abstract

Abstract: 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 non-homogeneous 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. Graphical abstract: Image 1 Highlights: A new system analysis code ARSAC was developed. The system model, model framework and solving algorithm were introduced. The preliminary assessment showed that the code prediction was reasonable.