Performance investigation of UN spherical fuel elements in MSR-SF
This study explores Uranium Nitride (UN) fuel performance in Molten Salt Reactors (MSRs), focusing on thermal efficiency, mechanical stability, and fission product retention. UN fuels offer advantages like higher thermal conductivity and heavy metal density compared to traditional uranium oxide (UO2...
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| Main Authors: | , , , , , |
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| Format: | Article |
| Language: | English |
| Published: |
Elsevier
2025-11-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573325003523 |
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