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[ASME 2017 25th International Conference on Nuclear Engineering - Shanghai, China (Sunday 2 July 2017)] Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues - Experimental Study of the Sodium-Cooled Fast Reactor Vessel Seismic Analysis Considered the Liquid Sloshing
Liu, Hongda, Lu, Daogang, Li, Xiaoxuan, Zeng, Xiaojia, Bao, GuangdongYear:
2017
Language:
english
DOI:
10.1115/ICONE25-66111
File:
PDF, 766 KB
english, 2017