Research Group for High Temperature Science on Fuel Materials
Research Group for High Temperature Science on Fuel Materials
Location ： JAEA > Nuclear Science and Engineering Center > Fuels and Material Engineering Division > Research Group for High Temperature Science on Fuel Materials
| "Research on the Effect of Additives for Uranium Nitride Pellets to Mitigate Reaction with Water" Mitsubishi Heavy Industries (NEXIP), 2020-2022fy. |
| "R&D on nitride fuel cycle for MA transmutation to enhance safety and economy" MEXT, 2017-2020fy. |
| "Development of Technical Basis for Introducing Advanced Fuels Contributing to Safety Improvement of Current Light Water Reactors" METI, 2015-2021fy. |
| "Advanced Multi-scale Modeling and Experimental Tests on Fuel Degradation in Severe Accident Conditions" METI, 2012-2016fy. |
| "Development of numerical simulation technology of microstructure for nuclear fuels" MEXT, CRIEPI, 2010-2012fy. |
| "Development of the reprocessing of spent nitride fuel by chemical dissolution in molten salt" MEXT, 2010-2011fy. |
| "Engineering development of MA－alloy fuel fabrication for irradiation test" MEXT, Fukui Univ., 2010-2012fy. |
| "Research and development of flexible technology realization for smooth transition to FBR" MEXT, Hitachi-GE Nuclear Energy, 2009-2011fy. |
| "Development of metal fuel cycle technology for closing FBR fuel cycle" MEXT, CRIEPI, 2009-2011fy. |
| "Basic actinide chemistry and physics research in close cooperation with hot laboratories" MEXT, 2008-2010fy |
| "Development of common and fundamental technologies on the evaluation of fuel behavior for realizing MA recycling" MEXT, 2007-2009fy. |
| "Development of a fabrication technology of TRU alloy fuel and fuel design for TRU transmutation" MEXT, Nagoya University, 2006-2008fy. |
| "Development of fabrication technique for the MA-containing nitride fuel dispersed in TiN inert matrix" MEXT, 2006-2008fy. |
| "Application of electrochemical reduction to pyrochemical reprocessing for oxide nuclear fuel" MEXT, CRIEPI, 2006-2008fy. |
| "Research and development of flexible fuel cycle for the smooth introduction of FBR" MEXT, Hitachi-GE Nuclear Energy, 2006-2008fy. |
| "Development of high-efficiency separation and recovery technology of minor actinides using liquid gallium MEXT, 2005-2007fy |
| "Technological development of a fuel cycle based on nitride fuel and pyrochemical reprocessing" MEXT, 2002-2006fy |