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- Lee, Deokjung
- Computational Reactor physics & Experiment Lab.
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Neutronic Analysis for Accident Tolerant Fuel and Control Rod Loaded APR-1400 with STREAM/RAST-K 2.0 Code
- Author(s)
- Jeong, Eun, Lee, Deokjung
- Issued Date
- 2025-07-21
- Citation
- Advances in Nuclear Fuel Management (ANFM 2025)
- Publisher
- ANS(American Nuclear Society)
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