Add to ORKGNuclear fuel rods (FRs) are transverselly linked to each other by three spacer grid cells at several vertical levels inside a fuel assembly (FA). Vibration of FA components, caused by the motion of FA support plates in the reactor core, generates variable contact forces between FRs and spacer grid cells. Friction effects in contact surfaces have an influence on the expected lifetime period of nuclear FA in terms of FR cladding fretting wear. This paper introduces an original approach to mathematical modelling and simulation analysis of FR nonlinear vibrations and fretting wear taking into consideration friction forces at all levels of spacer grids
The internal components of Pressurized Water Reactors (PWRs), particularly nuclear fuel assemblies, ...
ABSTRACT The fluid-induced fuel rod fretting wear in PWRs mainly proceeds in the grid-to-rod contact...
The goal of this research is to predict to what extent fretting wear damage occurs in a wire-wrapped...
Nuclear fuel rods (FRs) are transverselly linked to each other by three spacer grid cells at several...
The paper is focused on calculation of the friction forces work in the contact of nuclear fuel rods ...
The key-groove couplings between the lower part of core barrel and reactor pressure vessel in the nu...
Fuel elements (fuel rods) and spacer grids are the main elements of the fuel assembly of a nuclear r...
The release of fissile material into the coolant caused by fretting of the fuel rods at the interfac...
The fretting behavior of nuclear fuel assemblies is influenced by a number of parameters. One of the...
Fretting damage to fuel rods reduces the service lives of the fuel assemblies and therefore increase...
This work was supported by the project LO1506 of the Ministry of Education, Youth and Sports of the ...
The paper deals with dynamic load calculation of the hexagonal type nuclear fuel assembly caused by ...
This work was developed under the research project Fuel cycle of NPP coordinated by Nuclear Research...
The key-groove couplings between the lower part of core barrel and reactor pressure vessel in the nu...
In pressurized water reactors, the nuclear fuel rods are continuously subjected to turbulent fluid f...
The internal components of Pressurized Water Reactors (PWRs), particularly nuclear fuel assemblies, ...
ABSTRACT The fluid-induced fuel rod fretting wear in PWRs mainly proceeds in the grid-to-rod contact...
The goal of this research is to predict to what extent fretting wear damage occurs in a wire-wrapped...
Nuclear fuel rods (FRs) are transverselly linked to each other by three spacer grid cells at several...
The paper is focused on calculation of the friction forces work in the contact of nuclear fuel rods ...
The key-groove couplings between the lower part of core barrel and reactor pressure vessel in the nu...
Fuel elements (fuel rods) and spacer grids are the main elements of the fuel assembly of a nuclear r...
The release of fissile material into the coolant caused by fretting of the fuel rods at the interfac...
The fretting behavior of nuclear fuel assemblies is influenced by a number of parameters. One of the...
Fretting damage to fuel rods reduces the service lives of the fuel assemblies and therefore increase...
This work was supported by the project LO1506 of the Ministry of Education, Youth and Sports of the ...
The paper deals with dynamic load calculation of the hexagonal type nuclear fuel assembly caused by ...
This work was developed under the research project Fuel cycle of NPP coordinated by Nuclear Research...
The key-groove couplings between the lower part of core barrel and reactor pressure vessel in the nu...
In pressurized water reactors, the nuclear fuel rods are continuously subjected to turbulent fluid f...
The internal components of Pressurized Water Reactors (PWRs), particularly nuclear fuel assemblies, ...
ABSTRACT The fluid-induced fuel rod fretting wear in PWRs mainly proceeds in the grid-to-rod contact...
The goal of this research is to predict to what extent fretting wear damage occurs in a wire-wrapped...