This work was supported by the project LO1506 of the Ministry of Education, Youth and Sports of the Czech Republic.The original mathematical model of the VVER-type reactor excited by coolant pressure pulsations was derived as the linear clearance-free model in couplings. Assembly clearances in the key-groove (K-G) couplings between the lower part of core barrel (CB3) and the reactor pressure vessel (PV) (Fig. 1) produce nonlinear vibration of reactor components. Friction vibration interactions in the above mentioned couplings cause the fretting wear on their contact surfaces. The aim of this contribution is an investigation of the VVER 1000 type reactor nonlinear vibration respecting the assembling side clearances and friction in eight K-G ...
The core of Pressurized Water Reactors (PWR) is composed by nuclear fuel assemblies, bundles of slen...
The paper deals with dynamic load calculation of the hexagonal type nuclear fuel assembly caused by ...
The phenomenon of structural-coolant interaction is often observed in nuclear reactor plants. The mo...
This work was supported by the project LO1506 of the Ministry of Education, Youth and Sports of the ...
The key-groove couplings between the lower part of core barrel and reactor pressure vessel in the nu...
The key-groove couplings between the lower part of core barrel and reactor pressure vessel in the nu...
The paper presents a complex modelling concept for the nuclear fuel assembly vibration caused by the...
This work was developed under the research project Fuel cycle of NPP coordinated by Nuclear Research...
In Pressurized Water Reactors (PWR), fuel assemblies are composed of fuel rods, long slender tubes f...
Nuclear fuel bundles in PWR reactors present vibrations due to coolant flow, which may result in fre...
The internal components of Pressurized Water Reactors (PWRs), particularly nuclear fuel assemblies, ...
In pressurized water reactors, the nuclear fuel rods are continuously subjected to turbulent fluid f...
For safety reasons, the nuclear fuel assemblies of Pressurized Water Reactors (PWR) must be able to ...
This work was developed under the research project ”Fuel Cycle of Nuclear Power Plant” coordinated b...
Nuclear fuel rods (FRs) are transverselly linked to each other by three spacer grid cells at several...
The core of Pressurized Water Reactors (PWR) is composed by nuclear fuel assemblies, bundles of slen...
The paper deals with dynamic load calculation of the hexagonal type nuclear fuel assembly caused by ...
The phenomenon of structural-coolant interaction is often observed in nuclear reactor plants. The mo...
This work was supported by the project LO1506 of the Ministry of Education, Youth and Sports of the ...
The key-groove couplings between the lower part of core barrel and reactor pressure vessel in the nu...
The key-groove couplings between the lower part of core barrel and reactor pressure vessel in the nu...
The paper presents a complex modelling concept for the nuclear fuel assembly vibration caused by the...
This work was developed under the research project Fuel cycle of NPP coordinated by Nuclear Research...
In Pressurized Water Reactors (PWR), fuel assemblies are composed of fuel rods, long slender tubes f...
Nuclear fuel bundles in PWR reactors present vibrations due to coolant flow, which may result in fre...
The internal components of Pressurized Water Reactors (PWRs), particularly nuclear fuel assemblies, ...
In pressurized water reactors, the nuclear fuel rods are continuously subjected to turbulent fluid f...
For safety reasons, the nuclear fuel assemblies of Pressurized Water Reactors (PWR) must be able to ...
This work was developed under the research project ”Fuel Cycle of Nuclear Power Plant” coordinated b...
Nuclear fuel rods (FRs) are transverselly linked to each other by three spacer grid cells at several...
The core of Pressurized Water Reactors (PWR) is composed by nuclear fuel assemblies, bundles of slen...
The paper deals with dynamic load calculation of the hexagonal type nuclear fuel assembly caused by ...
The phenomenon of structural-coolant interaction is often observed in nuclear reactor plants. The mo...