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Tao Zhou

Southeast University - School of Energy and Environment

Nanjing

China

SCHOLARLY PAPERS

4

DOWNLOADS

174

TOTAL CITATIONS

2

Scholarly Papers (4)

1.

Heat Transfer Performance of High-Temperature Heat Pipe Startup in Small Nuclear Reactors

Number of pages: 26 Posted: 13 Oct 2023
Southeast University, Southeast University - School of Energy and Environment, Southeast University, Southeast University, Southeast University, Southeast University and Southeast University
Downloads 57 (989,921)
Citation 2

Abstract:

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nuclear reactor, high temperature heat pipe, transient, start-up, power, condensing section

2.

Nuclear-Thermal Characteristics and Material Optimization of a Lunar Heat Pipe Space Reactor

Number of pages: 19 Posted: 20 Nov 2025
Southeast University, affiliation not provided to SSRN, affiliation not provided to SSRN, Southeast University, Southeast University - School of Energy and Environment and Southeast University
Downloads 43 (1,170,409)

Abstract:

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Space heat pipe-cooled reactor, Lunar base, Structural material selection, Multi-physics modeling, Reactor Safety

3.

Research on Calculation and Verification of Hazardous Area for Radioactive Sewage Entering Into The Ocean

Number of pages: 20 Posted: 04 Jan 2023
China Waterborne Transport Research Institute, China Waterborne Transport Research Institute, Southeast University - School of Energy and Environment, China Waterborne Transport Research Institute, Chinese Academy of Sciences (CAS) - Institute of Oceanology and China Waterborne Transport Research Institute
Downloads 41 (1,170,409)

Abstract:

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Radioactive sewage, Coastal waters, Diffusion, Concentration distribution, Hazardous area, Verification

4.

Neutronic and Thermaldynamic Analysis on Control Drum Failures Accident in Heat Pipe Cooled Reactors

Number of pages: 29 Posted: 28 Nov 2023
Southeast University, Southeast University - School of Energy and Environment, Southeast University, Southeast University, Southeast University and Southeast University
Downloads 33 (1,290,922)

Abstract:

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heat pipe cooled reactor, control drum failure, reactor safety analysis;neutronic-thermal coupling