Thermal hydraulic safety characteristics analysis for the natural circulation primary loop under inclined condition on LFR
Lead-cooled fast reactor (LFR) has been an important option for floating nuclear power plant. The design of 50 MW natural circulation LFR had been proposed by Lanzhou University for floating nuclear power plant. However, floating nuclear power plant was affected by the marine environment, which led...
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| Autors principals: | , , , , |
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| Format: | Artigo |
| Idioma: | Inglês |
| Publicat: |
Frontiers Media S.A.
2025-05-01
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| Col·lecció: | Frontiers in Energy Research |
| Matèries: | |
| Accés en línia: | https://www.frontiersin.org/articles/10.3389/fenrg.2025.1566271/full |
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