Beryllium oxide utilized in nuclear reactors: Part I: Application history, thermal properties, mechanical properties, corrosion behavior and fabrication methods
Authors:
- Ming-Dong HouMHMing-Dong Hou
- Xiang-Wen ZhouXZXiang-Wen Zhou
- Bing LiuBLBing Liu
Open Access
- 31 July 2022
- journal article
- review article
- Published by Elsevier in Nuclear Engineering and Technology
- Vol. 54 (12) , 4393-4411
Abstract
No abstract availableKeywords
Funding Information
- National Major Science and Technology Projects of China (ZX06901)
This publication has 76 references indexed in Scilit:
- The crystal structure of beta berylliaJournal of Nuclear Materials, 1964
- The role of dispersed fuels in the further development of the advanced gas-cooled reactorJournal of Nuclear Materials, 1964
- The Australian high temperature gas-cooled reactor feasibility studyJournal of Nuclear Materials, 1964
- Thermal conductivity at low temperature of neutron-irradiated BeOJournal of Nuclear Materials, 1964
- Utilization of BeO in reactorsJournal of Nuclear Materials, 1964
- Some thermomechanical properties of pure oxide ceramicsRefractories and Industrial Ceramics, 1963
- The lattice parameter and density of beryllium oxide determined by precise X-ray methodsJournal of Nuclear Materials, 1962
- Fabrication and properties of dense beryllium oxideJournal of Nuclear Materials, 1961
- High temperature creep and anelastic phenomena in polycrystalline refractory oxidesJournal of Nuclear Materials, 1959
- The Reaction of Beryllium Oxide with Water VaporJournal of the American Chemical Society, 1952