Light-water power reactors use Zircaloy tubing as cladding to contain the UO/sub 2/ fuel pellets. In-service operating conditions impose an external hydrostatic force on the cladding, causing it to creep down into eventual contact with the fuel. Knowledge of the rate of such creepdown is of great importance to modelers of fuel element performance. An experimental system was devised for studying creepdown that meets several severe requirements by providing (1) correct stress state, (2) multiple positions for measuring radial displacement of the cladding surface, (3) high-precision data, and (4) an experimental configuration compact enough to fit in-reactor. A microcomputer-controlled, eddy-current monitoring system was developed for this stu...
International audienceCustom experimental setup has been designed to investigate the secondary creep...
Cladding tubes are structural parts of nuclear plants, submitted to complex thermomechanical loading...
Coated cladding materials are considered as a near-term concept for so-called Accident Tolerant Fuel...
The report describes the initial creepdown tests of Zircaloy fuel cladding in which the surface disp...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
The creepdown and collapse study on Zircaloy fuel cladding is concerned with the deformation behavio...
The zirconium based alloys are widely used as cladding materials for nuclear fuels in commercial rea...
In light water reactors the nuclear fuel is in the form of uranium dioxide pellets stacked inside a ...
International audienceThis paper presents an assessment of the thermo-mechanical behavior of non-irr...
Creep is a high temperature deformation mechanism that becomes significant when the temperature exce...
International audienceThe thermo-mechanical behavior of Zircaloy-4 fuel rods under Loss-Of-Coolant A...
The hypothetical scenario of a control rod ejection in a Pressurised Water Reactor leads to a Reacti...
International audienceThe secondary creep behavior of Zircaloy-4 (Zr-4) claddings under simulated Lo...
Mechanical properties and creep resistance are among the key issues in the selection of fuel claddin...
International audienceCustom experimental setup has been designed to investigate the secondary creep...
Cladding tubes are structural parts of nuclear plants, submitted to complex thermomechanical loading...
Coated cladding materials are considered as a near-term concept for so-called Accident Tolerant Fuel...
The report describes the initial creepdown tests of Zircaloy fuel cladding in which the surface disp...
The understanding of the creep behavior of nuclear fuel claddings is essential to predict safely and...
The creepdown and collapse study on Zircaloy fuel cladding is concerned with the deformation behavio...
The zirconium based alloys are widely used as cladding materials for nuclear fuels in commercial rea...
In light water reactors the nuclear fuel is in the form of uranium dioxide pellets stacked inside a ...
International audienceThis paper presents an assessment of the thermo-mechanical behavior of non-irr...
Creep is a high temperature deformation mechanism that becomes significant when the temperature exce...
International audienceThe thermo-mechanical behavior of Zircaloy-4 fuel rods under Loss-Of-Coolant A...
The hypothetical scenario of a control rod ejection in a Pressurised Water Reactor leads to a Reacti...
International audienceThe secondary creep behavior of Zircaloy-4 (Zr-4) claddings under simulated Lo...
Mechanical properties and creep resistance are among the key issues in the selection of fuel claddin...
International audienceCustom experimental setup has been designed to investigate the secondary creep...
Cladding tubes are structural parts of nuclear plants, submitted to complex thermomechanical loading...
Coated cladding materials are considered as a near-term concept for so-called Accident Tolerant Fuel...