The reference fuel design currently being considered within the Generation-IV Gas-cooled Fast Reactor (GFR) project is a ceramic plate matrix with a honeycomb inner structure containing small fuel cylinders. The fuel is mixed plutonium-uranium carbide, while the matrix material is silicon carbide. The present paper describes the mechanical part of a thermal-mechanical model being developed for studying the transient behavior of this highly heterogeneous fuel type. Benchmarking has been carried out against detailed finite-elements modeling (FEM). The resultant thermal-mechanical model can provide reliable fuel and cladding (matrix) stress/strain conditions to evaluate temperatures and neutronic feedbacks. As such, it has been integrated into...
A finite element model of pellet fragment relocation in the r-θ plane of advanced gas-cooled reactor...
This article presents assessment of the mechanical behavior of U-10wt% Mo (U10Mo) alloy based monoli...
International audienceWe employ a novel methodology to simulate the irradiation of Sodium cooled Fas...
Three aspects of the mechanical behaviour of fast reactor fuel have been studied, two being theoreti...
The fuel-pin modeling code LIFE-GCFR has been developed to predict the thermal, mechanical, and fiss...
A poro-elasto-plastic material model has been developed to capture the response of oxide fuels insid...
The harsh conditions in the reactor affect the thermal and mechanical performance of the fuel plate ...
The importance of fuel reliability is growing due to the deregulated electricity market and the dema...
A new 3D fuel behavior solver is currently under collaborative development at the Laboratory for Rea...
A review of the current thermomechanical needs along with a recommendation of the most urgent ones t...
In light water reactors the nuclear fuel is in the form of uranium dioxide pellets stacked inside a ...
In light water reactors the nuclear fuel is in the form of uranium dioxide pellets stacked inside a ...
This research concerns the fuel cycle and safety aspects of a Gas Cooled Fast Reactor, one of the so...
This research concerns the fuel cycle and safety aspects of a Gas Cooled Fast Reactor, one of the so...
The basic unit of the fuel in the core of a High Temperature Reactor (HTR) with block or spherical f...
A finite element model of pellet fragment relocation in the r-θ plane of advanced gas-cooled reactor...
This article presents assessment of the mechanical behavior of U-10wt% Mo (U10Mo) alloy based monoli...
International audienceWe employ a novel methodology to simulate the irradiation of Sodium cooled Fas...
Three aspects of the mechanical behaviour of fast reactor fuel have been studied, two being theoreti...
The fuel-pin modeling code LIFE-GCFR has been developed to predict the thermal, mechanical, and fiss...
A poro-elasto-plastic material model has been developed to capture the response of oxide fuels insid...
The harsh conditions in the reactor affect the thermal and mechanical performance of the fuel plate ...
The importance of fuel reliability is growing due to the deregulated electricity market and the dema...
A new 3D fuel behavior solver is currently under collaborative development at the Laboratory for Rea...
A review of the current thermomechanical needs along with a recommendation of the most urgent ones t...
In light water reactors the nuclear fuel is in the form of uranium dioxide pellets stacked inside a ...
In light water reactors the nuclear fuel is in the form of uranium dioxide pellets stacked inside a ...
This research concerns the fuel cycle and safety aspects of a Gas Cooled Fast Reactor, one of the so...
This research concerns the fuel cycle and safety aspects of a Gas Cooled Fast Reactor, one of the so...
The basic unit of the fuel in the core of a High Temperature Reactor (HTR) with block or spherical f...
A finite element model of pellet fragment relocation in the r-θ plane of advanced gas-cooled reactor...
This article presents assessment of the mechanical behavior of U-10wt% Mo (U10Mo) alloy based monoli...
International audienceWe employ a novel methodology to simulate the irradiation of Sodium cooled Fas...