Conceptual design and feasibility analysis of a heat pipe cooled cermet fuel space nuclear reactor for mars surface application-Reference-Cited by-同舟云学术

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Conceptual design and feasibility analysis of a heat pipe cooled cermet fuel space nuclear reactor for mars surface application

Published:2024-06 Issue: Volume:171 Page:105156
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Fan Yuhan^ORCID,Yan Rui,Yu Shihe,Chen Liang,Zou Yang

Funder

Natural Science Foundation of Shanghai Municipality

Science and Technology Commission of Shanghai Municipality

Publisher

Elsevier BV

Reference45 articles.

1. A stainless-steel, uranium-dioxide, potassium-heatpipe-cooled surface reactor;Amiri;AIP Conf. Proc.,2006

2. Thermal stability investigation technique for uranium nitride;Baranov;Ann. Nucl. Energy,2016

3. A Basic LEGO Reactor Design for the Provision of Lunar Surface Power;Bess,2008

4. Review of recent research on heat pipe cooled reactor;Bo;Nucl. Eng. Des.,2023

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

Cited by 2 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Designing sustainable built environments for Mars habitation: Integrating innovations in architecture, systems, and human well-being;Nexus;2024-09

2. Preliminary neutronics design and analysis of lithium heat pipe cooled space reactor with low-enriched uranium;Nuclear Engineering and Technology;2024-07

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