Validation of the subchannel code LINDEN for void fraction simulation based on the NUPEC PWR tests (PSBT)
Subchannel analysis code is one of the most important thermal-hydraulic analysis tools for nuclear reactor cores. A new subchannel analysis code for PWRs named LINDEN code has been developed by China Nuclear Power Technology Research Institute (CNPRI), and it is also as a part of the self-reliant so...
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| Asıl Yazarlar: | , , |
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| Materyal Türü: | Artigo |
| Dil: | Inglês |
| Baskı/Yayın Bilgisi: |
KeAi Communications Co., Ltd.
2025-12-01
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| Seri Bilgileri: | International Journal of Advanced Nuclear Reactor Design and Technology |
| Konular: | |
| Online Erişim: | http://www.sciencedirect.com/science/article/pii/S2468605025001000 |
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