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A review of CFD studies on thermal hydraulic analysis of coolant flow through fuel rod bundles in nuclear reactor

Document Type

Review

Author

Wang, M.; Ju, H.; Wu, J.; Qiu, H.; Liu, K.; Tian, W.; Su, G.H.

Source

In: Progress in Nuclear Energy. (Progress in Nuclear Energy, June 2024, 171)

Subject

Language

English

ISSN

01491970

Online Access

Full Text (ScienceDirect 종량제) Web of Science JCR 저널정보 Scopus Find it@PNU

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