The knowledge of the reduced damping coefficient of the first mode of a fuel assembly of PWR (pressurized water reactor) fuel assembly is an important parameter in a nuclear safety context. Indeed, this characteristic is an input to the calculation codes dedicated to the prediction of the behavior of fuel assemblies subjected to seismic loading. The experimental methods classically used for the determination of this coefficient are based on a linear formalism of the dynamic behavior of the assembly. It has been shown, and we confirm it in our analysis, that this structure has a non-linear behavior. We propose here a method for the identification of the damping and the frequency of the first mode of the assembly, taking into account this cha...
The internal components of Pressurized Water Reactors (PWRs), particularly nuclear fuel assemblies, ...
Spent fuel racks are steel structures used in the storage of the spent fuel removed from the nuclear...
The paper presents a complex modelling concept for the nuclear fuel assembly vibration caused by the...
This study is in the scope of Pressurized Water Reactors (P. W. R. ) core response calculations in t...
Université de la Méditerranée - Aix-Marseille IIThis study is in the scope of Pressurized Water Reac...
Nuclear fuel bundles in PWR reactors present vibrations due to coolant flow, which may result in fre...
ABSTRACT Pressurized Water Reactor (PWR) seismic or Lost Of Coolant Accident (LOCA) loads could resu...
In Pressurized Water Reactors (PWR), fuel assemblies are made up of fuel rods, long slender tubes fi...
The core of Pressurized Water Reactors (PWR) is composed by nuclear fuel assemblies, bundles of slen...
The paper deals with mathematical modelling and computer simulation of the seismic response of fuel ...
In Pressurized Water Reactors (PWR), fuel assemblies are composed of fuel rods, long slender tubes f...
The designing of a pressurized water reactor core subjected to seismic loading, is a major concern o...
Dans le cadre des études de sûreté, il est nécessaire de disposer de modèles validés des forces flui...
For safety reasons, the nuclear fuel assemblies of Pressurized Water Reactors (PWR) must be able to ...
27th annual European Safety and Reliability Conference (ESREL 2017), Portoroz, Slovenia, June, 2017S...
The internal components of Pressurized Water Reactors (PWRs), particularly nuclear fuel assemblies, ...
Spent fuel racks are steel structures used in the storage of the spent fuel removed from the nuclear...
The paper presents a complex modelling concept for the nuclear fuel assembly vibration caused by the...
This study is in the scope of Pressurized Water Reactors (P. W. R. ) core response calculations in t...
Université de la Méditerranée - Aix-Marseille IIThis study is in the scope of Pressurized Water Reac...
Nuclear fuel bundles in PWR reactors present vibrations due to coolant flow, which may result in fre...
ABSTRACT Pressurized Water Reactor (PWR) seismic or Lost Of Coolant Accident (LOCA) loads could resu...
In Pressurized Water Reactors (PWR), fuel assemblies are made up of fuel rods, long slender tubes fi...
The core of Pressurized Water Reactors (PWR) is composed by nuclear fuel assemblies, bundles of slen...
The paper deals with mathematical modelling and computer simulation of the seismic response of fuel ...
In Pressurized Water Reactors (PWR), fuel assemblies are composed of fuel rods, long slender tubes f...
The designing of a pressurized water reactor core subjected to seismic loading, is a major concern o...
Dans le cadre des études de sûreté, il est nécessaire de disposer de modèles validés des forces flui...
For safety reasons, the nuclear fuel assemblies of Pressurized Water Reactors (PWR) must be able to ...
27th annual European Safety and Reliability Conference (ESREL 2017), Portoroz, Slovenia, June, 2017S...
The internal components of Pressurized Water Reactors (PWRs), particularly nuclear fuel assemblies, ...
Spent fuel racks are steel structures used in the storage of the spent fuel removed from the nuclear...
The paper presents a complex modelling concept for the nuclear fuel assembly vibration caused by the...