Cermet nuclear fuels have been demonstrated to have significant potential to enhance fuel performance because of low internal fuel temperatures and low stored energy. The combination of these benefits with the inherent proliferation resistance, high burnup capability, and favorable neutronic properties of the thorium fuel cycle produces intriguing options for advanced nuclear fuel cycles. This paper describes aspects of a Nuclear Energy Research Initiative (NERI) project with two primary goals: (1) Evaluate the feasibility of implementing the thorium fuel cycle in existing or advanced reactors using a zirconium-matrix cermet fuel, and (2) Develop enabling technologies required for the economic application of this new fuel form. Spray drying...
Four different concepts for fuels and targets for transmutation of (minor) actinides are discussed i...
An evolutionary, rather than a revolutionary approach to thorium fueled reactors is proposed with an...
AbstractDuring operation of a fourth generation reactor system it is necessarily not desirable to ut...
Cermet nuclear fuels have been demonstrated to have significant potential to enhance fuel performanc...
Processing techniques are being developed to fabricate refractory metal and ceramic cermet materials...
A process for the production of nuclear fuels in particle or pellet form has been developed on the b...
The plutonium disposition is presently acknowledged as a most urgent issue at the world level. Inert...
Zirconium oxide is an inert matrix candidate for the transmutation of plutonium in light water react...
At the heart of a nuclear reactor resides its fuel. The chemical composition of the nuclear fuel aff...
Thorium, which is a fissile nuclide, was considered as a fuel for nuclear power plants in the beginn...
Two new methods are being investigated to manufacture cermet casks to be used for storage, transport...
From international conference on nuclear fuel performance; London, UK (15 Oct 1973). Fuel for large ...
For the production of ceramic microspheres for future space travel, new methods of processing must b...
Hydrated gel-microspheres of U, Pu, Th oxide or oxide plus carbon mixture of diameter 400-800µ ...
Cerium oxide and uranium oxide microspheres are being produced via an internal gelation sol-gel meth...
Four different concepts for fuels and targets for transmutation of (minor) actinides are discussed i...
An evolutionary, rather than a revolutionary approach to thorium fueled reactors is proposed with an...
AbstractDuring operation of a fourth generation reactor system it is necessarily not desirable to ut...
Cermet nuclear fuels have been demonstrated to have significant potential to enhance fuel performanc...
Processing techniques are being developed to fabricate refractory metal and ceramic cermet materials...
A process for the production of nuclear fuels in particle or pellet form has been developed on the b...
The plutonium disposition is presently acknowledged as a most urgent issue at the world level. Inert...
Zirconium oxide is an inert matrix candidate for the transmutation of plutonium in light water react...
At the heart of a nuclear reactor resides its fuel. The chemical composition of the nuclear fuel aff...
Thorium, which is a fissile nuclide, was considered as a fuel for nuclear power plants in the beginn...
Two new methods are being investigated to manufacture cermet casks to be used for storage, transport...
From international conference on nuclear fuel performance; London, UK (15 Oct 1973). Fuel for large ...
For the production of ceramic microspheres for future space travel, new methods of processing must b...
Hydrated gel-microspheres of U, Pu, Th oxide or oxide plus carbon mixture of diameter 400-800µ ...
Cerium oxide and uranium oxide microspheres are being produced via an internal gelation sol-gel meth...
Four different concepts for fuels and targets for transmutation of (minor) actinides are discussed i...
An evolutionary, rather than a revolutionary approach to thorium fueled reactors is proposed with an...
AbstractDuring operation of a fourth generation reactor system it is necessarily not desirable to ut...