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《中国原子能科学研究院年报:英文版》
>Science and Technology of Reactor:Experimental Study of Subcooled Flow Boiling Critical Heat Flux of Water Under Steady-State and Flow-Transient Conditions at Lower Pressure
Science and Technology of Reactor:Experimental Study of Subcooled Flow Boiling Critical Heat Flux of Water Under Steady-State and Flow-Transient Conditions at Lower Pressure