Neutronic and depletion analysis of a 5 MWth heat pipe cooled reactor with TRISO fuel and fluoride salt using MCS
Authors:
- Kyeongwon KimKKKyeongwon Kim
- Hae-Yong JeongHJHae-Yong Jeong
- Deokjung LeeDeokjung Lee
Open Access
- 10 August 2026
- journal article
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 59 (1)
Abstract
No abstract availableFunding Information
- Korea Institute of Energy Technology Evaluation and Planning (2024-00398867)
- Nuclear Safety and Security Commission
- Korea Foundation
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