Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference42 articles.
1. Kairos power thermal hydraulics research and development;Blandford;Nucl. Eng. Des.,2020
2. Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Core design and safety analysis;Brown;Ann. Nucl. Energy,2017
3. N. R. Brown, “A review of in-pile fuel safety tests of TRISO fuel forms and future testing opportunities in non-HTGR applications,” Journal of Nuclear Materials, vol. 534, no. 152139, 2020.
4. T. Burchell, D. Felde and K. Thoms, “Experimental Plan and Preliminary Design Report for HFIR High Temperature Graphite Irradiation Capsules HTV-1 and 2,” Oak Ridge National Laboratory, ORNL-GEN4/LTR-05-013, 2005.
5. Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature;Campbell;Nucl. Inst. Methods Phys. Res. B,2016
Cited by
1 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