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Xinxin Wu

Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China

Articles:

Numerical Investigation of the Flow and Temperature Uniformity in the Reactor Core of a Pebble Bed HTGR Using Porous Media Method - Vol. 40 '2014 - International Heat Transfer Conference 15

CROSS FLOW AND HEAT TRANSFER CHARACTERISTICS OVER HELICAL TUBE BUNDLES - Vol. 9 '2018 - International Heat Transfer Conference 16

PRESSURE DROP AND HEAT TRANSFER MEASUREMENTS OF THE ONCE THROUGH STEAM GENERATOR HELICAL TUBE BUNDLES OF HIGH TEMPERATURE GAS-COOLED REACTORS - Vol. 9 '2018 - International Heat Transfer Conference 16

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