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Publications by Tomoaki MOURI
Nuclear and Thermal Design for High Temperature Gas Cooled Reactor (GTHTR300C) Using MOX Fuel
Transactions of the Atomic Energy Society of Japan
Risk
Nuclear Energy
Engineering
Reliability
Safety
Quality
Related publications
Nuclear, Thermal and Hydraulic Design for Gas Turbine High Temperature Reactor (GTHTR300)
Transactions of the Atomic Energy Society of Japan
Risk
Nuclear Energy
Engineering
Reliability
Safety
Quality
Options for Treating High-Temperature Gas-Cooled Reactor Fuel for Repository Disposal
Nuclear Hydrogen Production Based on High Temperature Gas Cooled Reactor in China
Chinese Journal of Engineering Science
Effective Coolant Flow Rate of Flange Type Fuel Element for Very High Temperature Gas-Cooled Reactor.
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
THATCH: A Computer Code for Modelling Thermal Networks of High- Temperature Gas-Cooled Nuclear Reactors
Development Strategy of High Temperature Gas Cooled Reactor in China
Chinese Journal of Engineering Science
Design Study on Evaluation for Power Conversion System Concepts in High Temperature Gas Cooled Reactor With Gas Turbine
Transactions of the Atomic Energy Society of Japan
Risk
Nuclear Energy
Engineering
Reliability
Safety
Quality
Gas-Cooled Reactor Programs: High-Temperature Gas-Cooled Reactor Base-Technology Program. Annual Progress Report for Period Ending December 31, 1978
Liquid Salt - Very High Temperature Reactor : Survey of Sodium-Cooled Fast Reactor Fuel Handling Systems for Relevant Design and Operating Characteristics.
