Thorium-plutonium Mixed OXide (Th-MOX) fuel is considered for use in light water reactors fuel due to some inherent benefits over conventional fuel types in terms of neutronic properties. The good material properties of ThO2 also suggest benefits in terms of thermal-mechanical fuel performance, but the use of Th-MOX fuel for commercial power production demands that its thermal-mechanical behavior can be accurately predicted using a well validated fuel performance code. Given the scant operational experience with Th-MOX fuel, no such code is available today. This article describes the first phase of the development of such a code, based on the well-established code FRAPCON 3.4, and in particular the correlations reviewed and chosen for the f...
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its perform...
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its perform...
The burning-out of excess plutonium from the reprocessing of spent nuclear fuel and from the dismant...
Thorium-plutonium Mixed OXide (Th-MOX) fuel is considered for use in light water reactors fuel due t...
Thorium-plutonium Mixed OXide fuel (Th-MOX) is considered for use as light water reactor fuel. Both ...
Thorium-plutonium Mixed OXide fuel (Th-MOX) is considered for use as light water reactor fuel. Both ...
Both the Russian Federation and the US are pursing mixed uranium-plutonium oxide (MOX) fuel in light...
Thermal conductivity and melting temperature of nuclear fuel are essential for its performance under...
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its perform...
A three-dimensional MCNP model of a Westinghouse-type 17 x 17 PWR was used to assess the feasibility...
Thorium-containing nuclear fuel is proposed as a means of gaining a number of benefits in the operat...
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its perform...
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its perform...
Recent investigations into the performance and economics of mixed thoria-urania (ThO2/UO2) fuel cycl...
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its perform...
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its perform...
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its perform...
The burning-out of excess plutonium from the reprocessing of spent nuclear fuel and from the dismant...
Thorium-plutonium Mixed OXide (Th-MOX) fuel is considered for use in light water reactors fuel due t...
Thorium-plutonium Mixed OXide fuel (Th-MOX) is considered for use as light water reactor fuel. Both ...
Thorium-plutonium Mixed OXide fuel (Th-MOX) is considered for use as light water reactor fuel. Both ...
Both the Russian Federation and the US are pursing mixed uranium-plutonium oxide (MOX) fuel in light...
Thermal conductivity and melting temperature of nuclear fuel are essential for its performance under...
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its perform...
A three-dimensional MCNP model of a Westinghouse-type 17 x 17 PWR was used to assess the feasibility...
Thorium-containing nuclear fuel is proposed as a means of gaining a number of benefits in the operat...
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its perform...
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its perform...
Recent investigations into the performance and economics of mixed thoria-urania (ThO2/UO2) fuel cycl...
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its perform...
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its perform...
Thermal conductivity and melting temperature of nuclear fuel are essential for analysing its perform...
The burning-out of excess plutonium from the reprocessing of spent nuclear fuel and from the dismant...