Search Results - "Cooper, M W D"

Thermophysical properties and oxygen transport in (Thx,Pu1−x)O2 by Galvin, C. O. T., Cooper, M. W. D., Rushton, M. J. D., Grimes, R. W.

“…Using Molecular Dynamics, this paper investigates the thermophysical properties and oxygen transport of (Th x ,Pu 1−x )O 2 (0 ≤ x ≤ 1) between 300–3500 K. In…”
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A many-body potential approach to modelling the thermomechanical properties of actinide oxides by Cooper, M W D, Rushton, M J D, Grimes, R W

“…A many-body potential model for the description of actinide oxide systems, which is robust at high temperatures, is reported for the first time. The embedded…”
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Point defects and non-stoichiometry in thoria by Murphy, S.T., Cooper, M.W.D., Grimes, R.W.

“…Thoria is a possible alternative to urania as a nuclear fuel. In order to adopt thoria it is necessary to gain a thorough understanding of the defect processes…”
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Partition of soluble fission products between the grey phase, ZrO2 and uranium dioxide by Cooper, M.W.D., Middleburgh, S.C., Grimes, R.W.

“…The energies to remove fission products from UO2 or UO2+x and incorporate them into BaZrO3, SrZrO3 (grey phase constituent phases) and ZrO2 have been…”
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Formation of (Cr,Al)UO4 from doped UO2 and its influence on partition of soluble fission products by Cooper, M.W.D., Gregg, D.J., Zhang, Y., Thorogood, G.J., Lumpkin, G.R., Grimes, R.W., Middleburgh, S.C.

“…CrUO4 and (Cr,Al)UO4 have been fabricated by a sol–gel method, studied using diffraction techniques and modelled using empirical pair potentials. Cr2O3 was…”
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Vacancy mediated cation migration in uranium dioxide: The influence of cluster configuration by Cooper, M.W.D., Middleburgh, S.C., Grimes, R.W.

“…The effect of cluster configuration on vacancy mediated uranium migration is investigated for stoichiometric UO2 and hyper-stoichiometric UO2+x. The minimum…”
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Swelling due to the partition of soluble fission products between the grey phase and uranium dioxide by Cooper, M.W.D., Middleburgh, S.C., Grimes, R.W.

“…The change in volume associated with the partition of soluble cations from uranium dioxide into the (Ba,Sr)ZrO3 grey phase has been investigated using atomic…”
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Fission gas release from UO2 nuclear fuel: A review by Rest, J., Cooper, M.W.D., Spino, J., Turnbull, J.A., Van Uffelen, P., Walker, C.T.

“…Gaseous fission product generation, transport, and release can have a large impact on nuclear fuel performance, degrading fuel and fuel–cladding gap…”
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The defect chemistry of UO2±x from atomistic simulations by Cooper, M.W.D., Murphy, S.T., Andersson, D.A.

“…Control of the defect chemistry in UO2±x is important for manipulating nuclear fuel properties and fuel performance. For example, the uranium vacancy…”
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Ceramic nuclear fuel performance and the role of atomic scale simulations by Cooper, M.W.D.

“…There are a number of important challenges facing the nuclear industry including the extension of the fuel cycle of traditional UO2 fuel and the adoption of…”
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Modelling the thermal conductivity of (UxTh1−x)O2 and (UxPu1−x)O2 by Cooper, M.W.D., Middleburgh, S.C., Grimes, R.W.

“…The degradation of thermal conductivity due to the non-uniform cation lattice of (UxTh1−x)O2 and (UxPu1−x)O2 solid solutions has been investigated by molecular…”
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The role of dopant charge state on defect chemistry and grain growth of doped UO2 by Cooper, M.W.D., Stanek, C.R., Andersson, D.A.

“…Additives are widely used to control the microstructure of materials via their effect on defect chemistry during sintering. As the primary nuclear fuel, the…”
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Cluster dynamics simulation of xenon diffusion during irradiation in UO2 by Matthews, Christopher, Perriot, Romain, Cooper, M.W.D, Stanek, Christopher R., Andersson, David A.

“…Diffusion of fission gas in UO2 nuclear fuel impacts several important performance metrics, such as fission gas release, swelling, and thermal conductivity…”
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Simulations of self- and Xe diffusivity in uranium mononitride including chemistry and irradiation effects by Cooper, M.W.D., Rizk, J., Matthews, C., Kocevski, V., Craven, G.T., Gibson, T., Andersson, D.A.

“…A combination of density functional theory and empirical potential atomic scale simulations have been used to determine a model for defect stability and…”
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Importance of elastic finite-size effects: neutral defects in ionic compounds by Burr, P. A, Cooper, M. W. D

“…Phys Rev B 96 094107 (2017) Small system sizes are a well known source of error in DFT calculations, yet computational constraints frequently dictate the use…”
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Modeling oxygen self-diffusion in UO2 under pressure by Cooper, M.W.D., Grimes, R.W., Fitzpatrick, M.E., Chroneos, A.

“…Access to values for oxygen self-diffusion over a range of temperatures and pressures in UO2 is important to nuclear fuel applications. Here, elastic and…”
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Elastic moduli of high-density, sintered monoliths of yttrium dihydride by Shivprasad, A.P., Frazer, D.M., Mehta, V.K., Cooper, M.W.D., Saleh, T.A., White, J.T., Wermer, J.R., Luther, E.P., Rao, D.V.

“…Yttrium dihydride has been considered as potential nuclear reactor moderator for micro-reactors operating in the thermal energy spectrum due to their ability…”
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Improvement of the BISON U3Si2 modeling capabilities based on multiscale developments to modeling fission gas behavior by Gamble, K.A., Pastore, G., Cooper, M.W.D., Andersson, D.A., Matthews, C., Beeler, B., Aagesen, L.K., Barani, T., Pizzocri, D.

“…•The recommended models for analyzing U3Si2 fuel behavior with BISON are provided.•Lower-length scale methods have been used to reduce uncertainty in fission…”
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Improvement of the $\mathrm{BISON U_3Si_2}$ modeling capabilities based on multiscale developments to modeling fission gas behavior by Gamble, K. A., Pastore, G., Cooper, M. W. D., Andersson, D. A., Matthews, C., Beeler, B., Aagesen, L. K., Barani, T., Pizzocri, D.

“…Uranium silicide (U3Si2) is a concept explored as a potential alternative to UO2 fuel used in light water reactors (LWRs) since it may improve accident…”
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Thermophysical properties of high-density, sintered monoliths of yttrium dihydride in the range 373–773 K by Shivprasad, A.P., Vogel, S.C., Mehta, V.K., Cooper, M.W.D., Saleh, T.A., White, J.T., Wermer, J.R., Luther, E.P., Trellue, H.R.

“…Yttrium dihydride is a promising nuclear reactor moderator for high-temperature, thermal micro-reactors due to its ability to retain hydrogen to high…”
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