Amanote Research
Register
Sign In
Discover open access scientific publications
Search, annotate, share and cite publications
Publications by E. T. Cheng
Conceptual Design of a Self-Cooled FLiBe Blanket
Fusion Technology
Activation Product Safety in the ARIES-I Reactor Design
Fusion Technology
Related publications
APEX Advanced Ferritic Steel, Flibe Self-Cooled First Wall and Blanket Design
Journal of Nuclear Materials
High Energy Physics
Materials Science
Engineering
Nuclear Energy
Nuclear
High Power Density Self-Cooled Lithium–vanadium Blanket
Fusion Engineering and Design
Materials Science
Mechanical Engineering
Civil
Nuclear Energy
Structural Engineering
Engineering
Flibe Blanket Concept for Transmuting Transuranic Elements and Long Lived Fission Products
Fusion Technology
Conceptual Design and Development of an Indirect-Cooled Superconducting Helical Coil in the FFHR
Plasma and Fusion Research
Condensed Matter Physics
Analysis of the Conceptual Shielding Design for the Upflow Gas-Cooled Fast Breeder Reactor
Sizing of the Vacuum Vessel Pressure Suppression System of a Fusion Reactor Based on a Water-Cooled Blanket, for the Purpose of the Preconceptual Design
Science and Technology of Nuclear Installations
Engineering
Nuclear Energy
Conceptual Design of an Indirect-Cooled Superconducting Magnet for the LHD-type Fusion Reactor FFHR
Fusion Engineering and Design
Materials Science
Mechanical Engineering
Civil
Nuclear Energy
Structural Engineering
Engineering
Constructal Design of Gas-Cooled Electric Power Generators, Self-Pumping and Atmospheric Circulation
International Journal of Heat and Mass Transfer
Transfer Processes
Fluid Flow
Condensed Matter Physics
Mechanical Engineering
Magnetohydrodynamic Considerations for the Design of Self-Cooled Liquid-Metal Fusion Reactor Blankets
Fusion Technology