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Denis Horlait (CNRS/Université de Bordeaux)05/11/2019, 17:30
The noble gases helium, krypton and xenon are generated or implanted in many materials employed in or developed for fission or fusion nuclear reactors (e.g. UO2, neutron absorbers, high-level waste matrices, etc.). Taking the example of the usual fission nuclear fuel UO2, the in-pile generation of noble gases is greatly responsible for the unfavorable microstructure and thermal properties...
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Kerr Fitzgerald (National Nuclear Laboratory)05/11/2019, 17:30
Atomistic modelling of materials is typically achieved by using Molecular Dynamics (MD). However, due to the fact that MD needs to resolve atomic vibrations, a very large number of small time steps are needed and the total simulation time is therefore often limited to less than one microsecond. The timescale limitation can be overcome by using Adaptive Kinetic Monte Carlo (AKMC) methods....
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Mike Welland (Canadian Nuclear Laboratories)05/11/2019, 17:30
This work discusses advances in phase-field modelling of multiphase nuclear materials with a focus on incorporating bulk equilibrium thermodynamics and interfacial phenomena. Tools have been developed for the automated construction of explicit multiphase, temperature dependent composite potentials from those of the pure phases obtained from CALPHAD-type databases. The interfacial energy is...
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Simon Middleburgh (Bangor University)05/11/2019, 17:30
A combination of materials modelling techniques and targeted experimental investigations have identified the manner in which non-stoichiometry is accommodated in both crystalline and amorphous ZrO$_2$. Not only is excess oxygen possible in both crystalline and amorphous ZrO$_2$, but it is found that there is a high propensity for significant deviations–especially in the amorphous...
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Dr Anna Smith (Delft University of Technology)05/11/2019, 17:30
Advanced Generation-IV nuclear reactors, which should excel in the areas of sustainability, economics, safety & reliability and proliferation resistance, are currently being developed to replace the Light Water Reactors (LWRs) at the end of their operating licenses. Among the various designs selected by the Generation-IV International Forum, research has been focused in Europe on fast neutron...
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Mr Xinhu Zhang (Xi'an jiaotong University)05/11/2019, 17:30
Abstract: Fuel performance modeling and analysis plays an important role in fuel design and performance optimization, especially accurate fuel rod modeling and analysis in 3D. Fuel thermal behaviors are very complex and are strongly coupled with other factors. For example, with the increase of burnup, fuel thermal conductivity decreases which further increases the pellet central temperature,...
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Mr Tiantian Shi05/11/2019, 17:30
Abstract: The microstructural evolution of two Fe-9Cr model alloys with different C content after irradiation was investigated by transmission electron microscopy. These two steels were both irradiated with 3.5 MeV Fe13+ ions at 450℃ to a peak damage level of 3 dpas. TEM results indicate that <100> loops and 1/2<111> loops coexist in the two irradiated steels. Furthermore, the loop size of...
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Dr Marjorie Bertolus (Commisariat à l’Energie Atomique et aux énergie alternatives, DEN, DEC/SESC), Renaud Masson (CEA)05/11/2019, 17:30
For the future Sodium-cooled Fast Reactors, uranium-plutonium mixed dioxide (U,Pu)O2-x, with the plutonium content ranging between 19 to 40 mol.%, is foreseen as potential fuel. The pellets have to match various physico-chemical specifications: physical integrity, chemical homogeneity, to be oxygen hypostoichiometric (Oxygen/Metal ratio included in 1.94 and 1.99 range). However, for a Pu...
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Sylvie Chatain (CEA Saclay)05/11/2019, 17:30
Under irradiation in nuclear reactors, the microstructure of oxide nuclear fuel changes. To improve the modeling of the UO2 fuel behavior under irradiation, it is necessary to understand the elementary mechanisms of fission products diffusion. Among them, rare gas Xenon and Krypton represent 30% of created elements moreover fission products such as Iodine and Caesium are corrosive for the...
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Dmitry Bocharov (University of Latvia)05/11/2019, 17:30
Uranium dioxide (UO$_2$) is an important industrial material which is employed as a fuel in most nuclear reactors world-wide. The doping of UO$_2$ with small amounts of chromium oxide Cr$_2$O$_3$ is technically applied to obtain a larger average grain size after the fuel sintering process. In this study the local environment of chromium in UO$_2$ was investigated using X-ray absorption...
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Mr Diogo Ribeiro Costa (KTH Royal Institute of Technology and Westinghouse Electric Sweden AB)05/11/2019, 17:30
Uranium mononitride (UN) has been considered a potential accident tolerant fuel (ATF) mainly because its high uranium density, high melting point, and high thermal conductivity. Composite fuels like UN-UO2 have been proposed so as to combine the good properties of both fuels. This study is focused on analysing the first results regarding the sintering behaviours and the microstructures of an...
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Dr Christine Guéneau (CEA)05/11/2019, 17:30
The thermodynamic modelling of the U-Pu-Am-O system is proposed by using the CALPHAD method. The aim is to provide basic thermodynamic data (melting temperature, heat capacity …) on the (U,Pu,Am)O2 mixed oxide fuel to be used as input data in Fuel Performance Codes. In 2011, a CALPHAD model was developed in the TAF-ID database. An update of some of the binary and ternary sub-systems is...
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