Author:
Cai Lu,Smith Rebecca E.,Matthews Austin C.,Cottle David L.,Chuirazzi William C.,Xu Fei,Gross Brian J.,Chen Chong,Latta Ryan,Windes William E.
Funder
U.S. Department of Energy
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference38 articles.
1. Carbon materials in a high temperature gas-cooled reactor pebble-bed module.”;Zhou;New Carbon Mater.,2018
2. “Current status and future development of modular high temperature gas cooled reactor technology.”;Int. Atomic Energy Agency, Report No. IAEA-TECDOC-1198,2001
3. “Fluoride-salt-cooled high-temperature reactors: review of historical milestones, research status, challenges, and outlook.”;Jiang;Renew. Sustain. Energy Rev.,2022
4. “Oxidation behavior of matrix graphite and its effect on compressive strength;Zhou;Sci. Technol. Nucl. Ins.,2017
5. Effects of microstructure on the oxidation behavior of A3 matrix-grade graphite;Bratten;J. Am. Ceram. Soc.,2021