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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| Egile Nagusiak: | , , |
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| Formatua: | Artigo |
| Hizkuntza: | Inglês |
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KeAi Communications Co., Ltd.
2025-12-01
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| Saila: | International Journal of Advanced Nuclear Reactor Design and Technology |
| Gaiak: | |
| Sarrera elektronikoa: | http://www.sciencedirect.com/science/article/pii/S2468605025001000 |
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