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 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 FY2006, development of the basic functions of the COMPASS was completed and fundamental verification calculations are being carried out at the moment. In this paper, we describe the conceptual design of COMPASS and the outline of the formulation of MPS method, and show the results of the basic verification calculations for thermo -hydrodynamics module.
- Nuclear Engineering Division
R&D of the Next Generation Safety Analysis Methods for Fast Reactors With New Computational Science and Technology: Part 2 — Development and Verification of Thermo-Hydrodynamics Module of the COMPASS Code
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Yamamoto, Y, Hirano, E, Oue, M, Shimizu, S, Shirakawa, N, Koshizuka, S, & Morita, K. "R&D of the Next Generation Safety Analysis Methods for Fast Reactors With New Computational Science and Technology: Part 2 — Development and Verification of Thermo-Hydrodynamics Module of the COMPASS Code." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition. Orlando, Florida, USA. May 11–15, 2008. pp. 359-367. ASME. https://doi.org/10.1115/ICONE16-48485
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