Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system-Reference-Cited by-同舟云学术

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Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system

Published:2020-01 Issue:1 Volume:52 Page:19-26
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Wang Chenglong^ORCID,Sun Hao,Tang Simiao,Tian Wenxi,Qiu Suizheng,Su Guanghui

Funder

National Postdoctoral Program for Innovative Talents

China Postdoctoral Science Foundation

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference22 articles.

1. Space Nuclear Power: Opening the Final frontier[C]//4th International Energy Conversion Engineering Conference and Exhibit (IECEC);Bennett,2006

2. Deployment history and design considerations for space reactor power systems;El-Genk;Acta Astronaut.,2009

3. Design and Anal-Ysis of the SAFE-400 Space Fission reactor[C];Poston,2002

4. The Heatpipe-Operated Mars Exploration Reactor (HOMER);Poston,2000

5. The Martian Surface Reactor: an Advanced Nuclear Power Station for Manned Extraterrestrial Exploration;Bushman,2004

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1. Design and analysis on the HP-PHRS for small modular lead-bismuth fast reactor;Nuclear Engineering and Design;2024-09

2. Experimental investigation of thermal characteristics on a new loop pipe model for passive cooling system;Thermal Science and Engineering Progress;2024-05

3. Numerical simulation analysis of high-temperature bent sodium heat pipes;Kerntechnik;2024-03-27

4. Multiphysics analysis of a metal hydride moderated megawatt heat pipe reactor with burnable poisons;Frontiers in Energy Research;2024-02-06

5. Non-uniform fuel distribution and thermo-mechanical analysis of a 1 MW thermal power micronuclear heat pipe reactor;Heliyon;2024-02

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