Platform development for multi-physics coupling and uncertainty analysis based on a unified framework
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The multi-physics coupled methodologies that have been widely used to analyze the complex process occurring in nuclear reactors have also been used to the R&D of numerical reactors. The advancement in the field of computer technology has helped in the development of these methodologies. Herein, we report the integration of ADPRES code and RELAP5 code into the SALOME-ICoCo framework to form a multi-physics coupling platform. The platform exploits the supervisor architecture, serial mode, mesh one-to-one correspondence and explicit coupling methods during analysis, and the uncertainty analysis tool URANIE was used. The correctness of the platform was verified through the NEACRP-L-335 benchmark. The results obtained were in accordance with the reference values. The platform could be used to accurately determine the power peak. In addition, design margins could be gained post uncertainty analysis. The initial power, inlet coolant temperature and the mass flow of assembly property significantly influence reactor safety during the rod ejections accident (REA).
Abstract
The multi-physics coupled methodologies that have been widely used to analyze the complex process occurring in nuclear reactors have also been used to the R&D of numerical reactors. The advancement in the field of computer technology has helped in the development of these methodologies. Herein, we report the integration of ADPRES code and RELAP5 code into the SALOME-ICoCo framework to form a multi-physics coupling platform. The platform exploits the supervisor architecture, serial mode, mesh one-to-one correspondence and explicit coupling methods during analysis, and the uncertainty analysis tool URANIE was used. The correctness of the platform was verified through the NEACRP-L-335 benchmark. The results obtained were in accordance with the reference values. The platform could be used to accurately determine the power peak. In addition, design margins could be gained post uncertainty analysis. The initial power, inlet coolant temperature and the mass flow of assembly property significantly influence reactor safety during the rod ejections accident (REA).
참고문헌 (12)
- S. Stimpson, "Cycles 1-3", Nucl. Eng. Des, 327, pp.172~186 (2018)
- N. Capps, "Assessment of the analysis capability for core-wide PWR pellet-clad interaction screening of Watts Bar Unit 1", Nucl. Eng. Des, 333, pp.131~144 (2018)
- "Nuclear Energy Advanced Modeling and Simulation, NEAMS" (2010)[URL]
- US DOE NEAMS Program and SHARP Multi-Physics Toolkit for High-Fidelity SFR Core Design and Analysis, "T. Sofu", Argonne Natl. Lab., 1~10, pp.IAEA-CN245-054 (2017)
- Y. Yu, "Evaluation of hot channel factor for sodium-cooled fast reactors with multi-physics toolkit", Nucl. Eng. Des, 365, pp.110704~ (2020)
- Extension and Demonstration of NEAMS Multiphysics Tools to Lead- Cooled, Sodium-Cooled, and Molten Salt Fast Reactor Applications, "E.R. Shemon", Argonne Natl. Lab, 1~70, pp.ANL (2019), NSE-19[DOI]
- C. Chauliac, "NURESIM - a European simulation platform for nuclear reactor safety: multi-scale and multi-physics calculations, sensitivity and uncertainty analysis", Nucl. Eng. Des, 241, pp.3416~3426 (2011)
- B. Chanaron, "Advanced multi-physics simulation for reactor safety in the framework of the NURESAFE project", Ann. Nucl. Energy, 84, pp.166~177 (2015)
- B. Chanaron, "Overview of the NURESAFE European project", Nucl. Eng. Des, 321, pp.1~7 (2017)
- I. Spasov, "Best-estimate simulation of a VVER MSLB core transient using the NURESIM platform codes", Nucl. Eng. Des, 321, pp.26~37 (2017)
- Yann Perin, "CTF", DYN3D multi-scale coupled simulation of a rod ejection transient on the NURESIM platform, 2017, pp.49(6), 1339~1345[DOI]
- N. U. Aydemir, "Coupling of reactor transient simulations via the SALOME platform", Ann. Nucl. Energy, 126, pp.434~442 (2019)