Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase
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Wen-Sheng Hsu
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Jung-Hua Yang
Abstract
The Unit 1 of Kuosheng nuclear power plant is in the decommissioning transition phase and still has spent fuel in the core of reactor now. The time to reach the TAF (top of active fuel) for water level and reach 600/800 °C for cladding temperature are the key parameters in the safety analysis, these affect that the plant has how much time to handle transients. Therefore, to study the water level and cladding temperature for station blackout (SBO) and loss of coolant accident (LOCA) transients in the decommissioning transition phase, the analysis model of Kuosheng nuclear power plant was established by using TRACE code. To evaluate the effect of the decay heat of spent fuel on the water level and cladding temperature, the sensitivity analysis of decay heat was also performed in this study.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: None declared.
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
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Articles in the same Issue
- Frontmatter
- The 33rd German CFD Network of Competence Meeting: 20 years of advances in the numerical 3D simulation of reactor relevant flows
- Sustainable development of simulation setups and addons for OpenFOAM for nuclear reactor safety research
- Numerical investigations of flow in nuclear fuel assembly with spacer grid and OpenFOAM validation
- GRS contributions to flow-induced vibrations related activities in Europe
- Numerical simulation of subcooled flow boiling for nuclear engineering applications using OpenFOAM
- Model of terminal debris bed formation after a CANDU core collapse
- Weibull model for RUL estimation at RSG-GAS reactor implemented on PA01-AP01 secondary pump
- Study of the effect of virtual mass force on two-phase critical flow
- Using TRACE to establish the analysis model of Kuosheng nuclear power plant for decommissioning transition phase
- Post-LOCA control room dose analysis for Maanshan NPP using the AST methodology
- Lithium–lithium fusion evaporation research
- Study on the accidents analyses of a single channel for XADS by using MPC-LBE code
- Events
