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Publications by Hiroyasu Mochizuki
Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor
Science and Technology of Nuclear Installations
Engineering
Nuclear Energy
Related publications
Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design
Basis of Technical Standard on Fuel for Sodium-Cooled Fast Breeder Reactor
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Sodium-Reactor Experiment Advanced Sodium-Cooled Reactors and Sodium- Component Development
Liquid Salt - Very High Temperature Reactor : Survey of Sodium-Cooled Fast Reactor Fuel Handling Systems for Relevant Design and Operating Characteristics.
Fast Reactor Fuel Assembly Thermal Hydraulic Development Program: Sodium Heat Transfer.
Hot Fuel Element Thermal-Hydraulics in the Jules Horowitz Reactor
Nuclear Engineering and Design
Materials Science
Risk
Mechanical Engineering
Waste Management
Nuclear
Nuclear Energy
High Energy Physics
Engineering
Reliability
Safety
Disposal
Quality
Uranium Nitride--Sodium Paste Fuel for Fast-Reactor Blankets.
Measurement of the Residual Stresses and Investigation of Their Effects on a Hardfaced Grid Plate Due to Thermal Cycling in a Pool Type Sodium-Cooled Fast Reactor
Science and Technology of Nuclear Installations
Engineering
Nuclear Energy
Calculation Methodology of Fast Fission Factor in a Thermal Reactor
MATEC Web of Conferences
Materials Science
Engineering
Chemistry
