International audienceThis study is concerned with structural integrity assessment of Pressure Water Reactor's (PWR) fuel rods under pellet-cladding interaction (PCI) loading condition. An important experimental and research cooperative program between EDF, AREVA-NP and the Atomic Energy Commission CEA is achieved in order to get a better understanding of the mechanisms possibly leading to PCI failure, as well as to qualify a PCI resistant rod design. The objectives of this work are: first, to improve the understanding of the pellet mechanical properties impact on cladding local loading with 3D simulations results, and second, to propose a new phenomenological rupture criterion for a better assessment of the failure risk. In this study fuel...
The inventory of spent nuclear fuel (SNF) generated in nuclear power plants is continuously increasi...
Mechanical loading originating due to Pellet- Cladding Interaction (PCI) in PWR nuclear fuel rod con...
A finite element model of pellet fragment relocation in the r-θ plane of advanced gas-cooled reactor...
International audienceThis study is concerned with structural integrity assessment of Pressure Water...
Pellet cladding interaction (PCI) in PWR type rods subjected to power ramps was analysed by means of...
International audienceh i g h l i g h t s • This paper presents closed-formed solutions concerning p...
The importance of fuel reliability is growing due to the deregulated electricity market and the dema...
In commercial light water reactors, one important fuel failure scenario to analyze is fuel failure ...
The comprehensive understanding of fuel rod behavior and accurate prediction of the lifetime in norm...
A 3-dimensional (3D) fuel performance analysis program, able to simulate normal operating conditions...
The elementary parts of every fuel assembly, and thus of the reactor core, are fuel rods. The main f...
The elementary parts of every fuel assembly, and thus of the reactor core, are fuel rods. The main f...
The elementary parts of every fuel assembly, and thus of the reactor core, are fuel rods. The main f...
The cladding on light water reactor (LWR) fuel rods provides a stable enclosure for fuel pellets and...
The Zircaloy cladding of water reactor fuel rods is susceptible to local breach-type failure, common...
The inventory of spent nuclear fuel (SNF) generated in nuclear power plants is continuously increasi...
Mechanical loading originating due to Pellet- Cladding Interaction (PCI) in PWR nuclear fuel rod con...
A finite element model of pellet fragment relocation in the r-θ plane of advanced gas-cooled reactor...
International audienceThis study is concerned with structural integrity assessment of Pressure Water...
Pellet cladding interaction (PCI) in PWR type rods subjected to power ramps was analysed by means of...
International audienceh i g h l i g h t s • This paper presents closed-formed solutions concerning p...
The importance of fuel reliability is growing due to the deregulated electricity market and the dema...
In commercial light water reactors, one important fuel failure scenario to analyze is fuel failure ...
The comprehensive understanding of fuel rod behavior and accurate prediction of the lifetime in norm...
A 3-dimensional (3D) fuel performance analysis program, able to simulate normal operating conditions...
The elementary parts of every fuel assembly, and thus of the reactor core, are fuel rods. The main f...
The elementary parts of every fuel assembly, and thus of the reactor core, are fuel rods. The main f...
The elementary parts of every fuel assembly, and thus of the reactor core, are fuel rods. The main f...
The cladding on light water reactor (LWR) fuel rods provides a stable enclosure for fuel pellets and...
The Zircaloy cladding of water reactor fuel rods is susceptible to local breach-type failure, common...
The inventory of spent nuclear fuel (SNF) generated in nuclear power plants is continuously increasi...
Mechanical loading originating due to Pellet- Cladding Interaction (PCI) in PWR nuclear fuel rod con...
A finite element model of pellet fragment relocation in the r-θ plane of advanced gas-cooled reactor...