Simulation and RTA-driven assessment of SMR deployment and concrete waste recycling at retired Kori-1 NPP
The repurposing of retired Kori-1 Nuclear Power Plant site for Small Modular Reactor (SMR) deployment presents unique challenges and opportunities in sustainable infrastructure reuse and waste management. This study integrates Reactor Technology Assessment (RTA), simulation-based analysis, and on-site concrete recycling methodologies to comprehensively evaluate feasibility from both a technology comparison and implementation planning perspective. The RTA was conducted for Korea's two representative SMRs, SMART and i-SMR, using a partially tailored framework aligned with certain site-specific conditions. Both SMRs showed competitive performance across key evaluation criteria. Simulation-based analyses utilized FlexSim software to model concrete recycling processes, focusing on logistics for large-scale material handling. The recycling system combined coarse and fine aggregate processing with fresh concrete production while identifying bottlenecks in critical processors. The results indicated manageable recycling timelines for both SMRs aligning well with the Kori-1 decommissioning schedule. Addressing bottlenecks was effective in enhancing system efficiency. The simulation analyses suggest that this approach can help identify project schedule challenges, resolve bottlenecks, and allocate resources effectively to ensure the project schedule by incorporating advanced on-site concrete recycling into SMR deployment scenarios. This study provides a robust framework for optimizing waste management and repurposing retired nuclear sites, advancing innovative strategies for nuclear infrastructure redevelopment.
Authors
- Chang-Lak Kim (ORCID: https://orcid.org/0000-0002-6931-9541)
- Eui-Taek Lee (ORCID: https://orcid.org/0000-0003-1914-8550)
Institutions
- Korea Electric Power Corporation (South Korea) (KR)
Publication Details
- Journal
- Nuclear Engineering and Technology
- Published
- 2025-08-29
- DOI
- https://doi.org/10.1016/j.net.2025.103889
- Primary Topic
- Graphite, nuclear technology, radiation studies
- Type
- article
- Field-Weighted Citation Impact
- 0.00