High Temperature Gas-cooled Reactors JSME Series in Thermal and Nuclear Power Generation Series
Coordonnateurs : Takeda Tetsuaki, Inagaki Yoshiyuki
2. Design of High Temperature Engineering Test Reactor (HTTR)
3. R&D on components
4. Operation of HTTR
5. R&D on commercial high temperature gas-cooled reactor
Yoshiyuki Inagaki is Researcher of Department of Hydrogen and Heat Application Research and Development, HTGR Research and Development Center, Oarai Research and Development Institute, Sector of Fast Reactor and Advanced Reactor Research and Development in JAEA. He received his PhD degree from Kyushu University in 1996. He started his research career at JAERI in 1981 for the HTGR technology such as reactor internals and high temperature components. He then worked in Juelich Research Center in Germany from 1994 to 1995 for a hydrogen production process. He also researched HTGR heat application systems such as hydrogen production and nuclear steelmaking systems and the system integration technology for safe connection between a reactor and a hydrogen production system.
- Written by the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience
- Includes real examples and case studies from Japan, the US and Europe to provide a deeper learning opportunity with practical benefits
- Considers the societal impact and sustainability concerns and goals throughout the discussion
- Includes safety factors and considerations, as well as unique results from performance testing of HTGR systems
Date de parution : 02-2021
Ouvrage de 478 p.
15x22.8 cm
Thèmes de High Temperature Gas-cooled Reactors :
Mots-clés :
Advanced fuel; Air ingress; Commercial HTGR; Core; Core components; First criticality; Fuel; Full power; Gas turbine; Graphite; HTGR; HTTR; Heat application; Helium gas; High temperature; IS process; Inherent safety; Integration technology; Intermediate heat exchanger; Metal; Nuclear heat; Operation; Passive cooling system; Power generation; Reactor internals; Safety demonstration; Safety design; Seismic design; Spherical fuel; System design; Thermal hydraulic tests