Assessment of Screen-Covered Grooved Sodium Heat Pipes for Microreactor Applications
Author:
Affiliation:
1. Idaho National Laboratory, P.O. Box 1625, Idaho Falls, Idaho 83415
Funder
US Department of Energy
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295450.2021.1977085
Reference33 articles.
1. Thermal-hydraulic analysis of a new conceptual heat pipe cooled small nuclear reactor system
2. Conceptual design and analysis of a multipurpose micro nuclear reactor power source
3. A walk-away safe, Very-Small, Long-LIfe, Modular (VSLLIM) reactor for portable and stationary power
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