A computer code, named COMPASS, is being developed employing the Moving Particle Semi-implicit (MPS) method for various complex phenomena of core disruptive accidents (CDAs) in the sodium-cooled fast reactors (SFRs). The COMPASS is designed to analyze multi-physics problems involving thermal hydraulics, structure and phase change, in a unified framework of MPS method. In FYs2006 and 2007 (Japanese Fiscal Year, hereafter), the development of basic functions of COMPASS was completed and fundamental verification calculations were carried out. In FY2007, the integrated verification program using available experimental data for key phenomena in CDAs was also started. In this paper, we show the basic verification calculations for the phase change model of COMPASS and the results of experimental analyses, together with the outline of the formulation of MPS method and the conceptual design of the COMPASS code.
- Nuclear Engineering Division
Next Generation Safety Analysis Methods for SFRs—(3) Thermal Hydraulics Models of COMPASS Code and Experimental Analyses
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Yamamoto, Y, Hirano, E, Oue, M, Shimizu, S, Shirakawa, N, Koshizuka, S, Morita, K, Yamano, H, & Tobita, Y. "Next Generation Safety Analysis Methods for SFRs—(3) Thermal Hydraulics Models of COMPASS Code and Experimental Analyses." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 5: Fuel Cycle and High and Low Level Waste Management and Decommissioning; Computational Fluid Dynamics (CFD), Neutronics Methods and Coupled Codes; Instrumentation and Control. Brussels, Belgium. July 12–16, 2009. pp. 409-418. ASME. https://doi.org/10.1115/ICONE17-75521
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