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Browsing by Author "Grimes, RW"

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Accommodation of excess oxygen in fluorite dioxides
(Elsevier, 2013-12-15) Middleburgh, SC; Lagerlof, KPD; Grimes, RW
Accommodation of excess oxygen in CeO2, ThO2 and UO2 has been investigated using ab-initio modelling. Calculations indicate that hyperstoichiometry is preferentially accommodated by the formation of peroxide species in CeO2 and ThO2 but not in UO2, where oxygen interstitial defects are dominant. Migration of the excess oxygen defects was also studied; the peroxide ion in CeO2 and ThO2 is transported via a different mechanism, due to the formation of peroxide molecules, to the oxygen interstitial in UO2. Frenkel pair defects were investigated to understand if the interstitial component could assume a peroxide like configuration in the vicinity of the vacancy. While it was already expected that this would not be the case for UO2 since peroxide was not stable, it was also not found to be the case for CeO2 and ThO2 with the peroxide disassociating into a lattice species and a separate interstitial ion. © 2013, Elsevier B.V.
Accommodation of excess oxygen in group II monoxides
(John Wiley and Sons, 2013-01-07) Middleburgh, SC; Lagerlof, KPD; Grimes, RW
Atomic scale simulations are used to predict how excess oxygen is accommodated across the group II monoxides. In all cases, the preference is to form a peroxide ion centered at an oxygen site, rather than a single oxygen species, although the peroxide ionic orientation changes from <100> to <110> to <111> with increasing host cation radius. The enthalpy for accommodation of excess oxygen in BaO is strongly negative, whereas in SrO it is only slightly negative and in CaO and MgO the energy is positive. Interestingly, the increase in material volume due to the accommodation of oxygen (the defect volume) does not vary greatly as a function of cation radius. The vibrational frequency of peroxide ions in the group II monoxides is predicted with the aim to provide test data for future experimental observations of oxygen uptake. Finally, calculations of the dioxide structures have also been carried out. For these materials the oxygen vacancy formation energy is always positive (1.0–1.5 eV per oxygen removed) indicating that they exhibit only small oxygen defect concentrations. © 2012, The American Ceramic Society.
Crystal structure, thermodynamics, magnetics and disorder properties of Be–Fe–Al intermetallics
(Elsevier B.V., 2015-08-05) Burr, PA; Middleburgh, SC; Grimes, RW
The elastic and magnetic properties, thermodynamical stability, deviation from stoichiometry and order/disorder transformations of phases that are relevant to Be alloys were investigated using density functional theory simulations coupled with phonon density of states calculations to capture temperature effects. A novel structure and composition were identified for the Be–Fe binary ε phase. In absence of Al, FeBe5 is predicted to form at equilibrium above ∼1100 K, while the ε phase is stable only below ∼1500 K, and FeBe2 is stable at all temperatures below melting. Small additions of Al are found to stabilise FeBe5 over FeBe2 and ε, while at high Al content, AlFeBe4 is predicted to form. Deviations from stoichiometric compositions are also considered and found to be important in the case of FeBe5 and ε. The propensity for disordered vs ordered structures is also important for AlFeBe4 (which exhibits complete Al–Fe disordered at all temperatures) and FeBe5 (which exhibits an order–disorder transition at ∼950 K). © 2015 Elsevier B.V.
Formation of (Cr,Al)UO4 from doped UO2 and its influence on partition of soluble fission products
(Elsevier, 2013-11-01) Cooper, MWD; Gregg, DJ; Zhang, YJ; Thorogood, GJ; Lumpkin, GR; Grimes, RW; Middleburgh, SC
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 predicted to preferentially form CrUO4 over entering solution into hyper-stoichiometric UO2+x by atomic scale simulation. Further, it was predicted that the formation of CrUO4 can proceed by removing excess oxygen from the UO2 lattice. Attempts to synthesise AlUO4 failed, instead forming U3O8 and Al2O3. X-ray diffraction confirmed the structure of CrUO4 and identifies the existence of a (Cr, Al)UO4 phase for the first time (with a maximum Al to Cr mole ratio of 1:3). Simulation was subsequently used to predict the partition energies for the removal of fission products or fuel additives from hyper-stoichiometric UO2+x and their incorporation into the secondary phase. The partition energies are consistent only with smaller cations (e.g. Zr4+, Mo4+ and Fe3+) residing in CrUO4, while all divalent cations are predicted to remain in UO2+x. Additions of Al had little effect on partition behaviour. The reduction of UO2+x due to the formation of CrUO4 has important implications for the solution limits of other fission products as many species are less soluble in UO2 than UO2+x. © 2013, Elsevier B.V.
From solid solution to cluster formation of Fe and Cr in α-Zr
(Elsevier B.V., 2015-12-01) Burr, PA; Wenman, MR; Gault, B; Moody, MP; Ivermark, M; Rushton, MJD; Preuss, M; Edwards, L; Grimes, RW
To understand the mechanisms by which the re-solution of Fe and Cr additions increase the corrosion rate of irradiated Zr alloys, the solubility and clustering of Fe and Cr in model binary Zr alloys was investigated using a combination of experimental and modelling techniques — atom probe tomography (APT), x-ray diffraction (XRD), thermoelectric power (TEP) and density functional theory (DFT). Cr occupies both interstitial and substitutional sites in the α-Zr lattice; Fe favours interstitial sites, and a low-symmetry site that was not previously modelled is found to be the most favourable for Fe. Lattice expansion as a function of Fe and Cr content in the α-Zr matrix deviates from Vegard's law and is strongly anisotropic for Fe additions, expanding the c-axis while contracting the a-axis. Matrix content of solutes cannot be reliably estimated from lattice parameter measurements, instead a combination of TEP and APT was employed. Defect clusters form at higher solution concentrations, which induce a smaller lattice strain compared to the dilute defects. In the presence of a Zr vacancy, all two-atom clusters are more soluble than individual point defects and as many as four Fe or three Cr atoms could be accommodated in a single Zr vacancy. The Zr vacancy is critical for the increased apparent solubility of defect clusters; the implications for irradiation induced microstructure changes in Zr alloys are discussed. © 2015 Elsevier B.V.
Greater tolerance for nuclear materials.
(Nature Publishing Group, 2008-09) Grimes, RW; Konings, RJM; Edwards, L
As interest in new generations of nuclear reactors is increasing worldwide, renewed research effort into new materials more tolerant to extreme conditions is crucial. © 2008, Nature Publishing Group.
Hydrogen accommodation in Zr second phase particles: implications for H pick-up and hydriding of zircaloy-2 and zircaloy-4
(Elsevier, 2013-04-01) Burr, PA; Murphy, ST; Lumley, SC; Wenman, MR; Grimes, RW
Ab-initio computer simulations have been used to predict the energies associated with the accommodation of H atoms at interstitial sites in α, β-Zr and Zr–M intermetallics formed with common alloying additions (M = Cr, Fe, Ni). Intermetallics that relate to the Zr2(Ni,Fe) second phase particles (SPPs) found in Zircaloy-2 exhibit favourable solution enthalpies for H. The intermetallic phases that relate to the Zr(Cr,Fe)2 SPPs, found predominantly in Zircaloy-4, do not offer favourable sites for interstitial H. It is proposed that Zr(Cr,Fe)2 particles may act as bridges for the migration of H through the oxide layer, whilst the Zr2(Ni,Fe)-type particles will trap the migrating H until these are dissolved or fully oxidised. © 2012, Elsevier Ltd.
Hydrogen solubility in zirconium intermetallic second phase particles
(Elsevier, 2013-11-01) Burr, PA; Murphy, ST; Lumley, SC; Wenman, MR; Grimes, RW
The enthalpies of solution of H in Zr binary intermetallic compounds formed with Cu, Cr, Fe, Mo, Ni, Nb, Sn and V were calculated by means of density functional theory simulations and compared to that of H in α-Zr. It is predicted that all Zr-rich phases (formed with Cu, Fe, Ni and Sn), and those phases formed with Nb and V, offer lower energy, more stable sites for H than α-Zr. Conversely, Mo and Cr containing phases do not provide preferential solution sites for H. In all cases the most stable site for H are those that offer the highest coordination fraction of Zr atoms. Often these are four Zr tetrahedra but not always. Implications with respect to H-trapping properties of commonly observed ternary phases such as Zr(Cr, Fe)2, Zr2(Fe, Ni) and Zr(Nb, Fe)2 are also discussed. © 2013, Elsevier B.V.
Partition of soluble fission products between the grey phase, ZrO2 and uranium dioxide
(Elsevier, 2013-07-01) Cooper, MWD; Middleburgh, SC; Grimes, RW
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 calculated using atomistic scale simulation. These energies provide the thermodynamic drive for partition of soluble fission products between UO2 or UO2+x and these secondary oxide constituents of the fuel system. Tetravalent cation partition into BaZrO3, SrZrO3 and ZrO2 was only preferable for species with smaller radii than Zr4+, regardless of uranium dioxide stoichiometry. Under stoichiometric conditions both the larger and the smaller trivalent cations were found to segregate to BaZrO3 but only the smaller fuel additive elements Cr3+ and Fe3+ segregate to SrZrO3. Partition from UO2+x was always unfavourable for trivalent cations. Additions of excess Cr3+ (as a fuel additive) are predicted make the partition into BaZrO3 and SrZrO3 more favourable from UO2 for the larger trivalent cations. Trivalent fission products with radii smaller than or equal to that of Sm3+ were identified to segregate into ZrO2 only from UO2. No segregation to SrO or BaO is predicted. © 2013, Elsevier B.V.
Peroxide defect formation in zirconate perovskites
(Royal Society of Chemistry, 2014) Middleburgh, SC; Karatchevtseva, I; Kennedy, BJ; Burr, PA; Zhang, ZM; Reynolds, EM; Grimes, RW; Lumpkin, GR
Atomic scale modelling suggests that excess oxygen can be accommodated in the group II perovskite zirconates by the formation of peroxide ion defects. This is unprecedented given the lack of charge compensating defects required for standard excess oxygen accommodation. The solution energy of O2 was predicted to be close to zero for BaZrO3, accommodating the peroxide ion defect more easily than in SrZrO3 or CaZrO3. This was experimentally examined by exposing SrZrO3 and BaZrO3 to hydrogen peroxide solution and then carrying out Raman spectroscopy measurements to look for a peak indicative of peroxide ions. A peak was observed at ∼1000 cm−1 in both compositions, suggesting the theoretically predicted peroxide ion is present. © 2014, The Royal Society of Chemistry.
The stability of alloying additions in zirconium
(Elsevier, 2013-06-01) Lumley, SC; Murphy, ST; Burr, PA; Grimes, RW; Chard-Tuckey, PR; Wenman, MR
The interactions of Cr, Fe, Nb, Ni, Sn, V and Y with Zr are simulated using density functional theory. Thermodynamic stabilities of various different Zr based intermetallic compounds, including multiple Laves phase structures and solutions of alloying additions in both α and β -Zr were investigated. The thermodynamic driving forces in this system can be correlated with trends in atomic radii and the relative electronegativities of the different species. Formation energies of Fe, Ni and Sn based intermetallic compounds were found to be negative, and the Zr2FeZr2Fe and Zr2NiZr2Ni intermetallics were metastable. Most elements displayed negative energies of solution in β-Zr but positive energies in the α-phase, with the exception of Sn (which was negative for both) and Y (which was positive for both). Solutions formed from intermetallics showed a similar trend. © 2013, Elsevier B.V.
Swelling due to the partition of soluble fission products between the grey phase and uranium dioxide
(Elsevier, 2014-04-01) Cooper, MWD; Middleburgh, SC; Grimes, RW
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 scale simulations. Here past work on the thermodynamic drive for the segregation of trivalent and tetravalent cations from uranium dioxide is built upon in the context of fuel swelling. Only small tetravalent cations segregate into the grey phase and this is predicted to result in an overall reduction in fuel volume. Individual trivalent cations that segregate, can cause either a contraction or an expansion of the overall fuel volume. Cr2O3 doped UO2 promotes co-partition forming mixed cation clusters in the grey phase and causing an overall reduction in fuel volume for all trivalent cations. This may have implications for fuel performance and may alter other fuel swelling mechanisms.© 2013 Elsevier Ltd.
Thermal conductivity and energetic recoils in UO2 using a many-body potential model
(IOP Science, 2014-11-14) Qin, MJ; Cooper, MWD; Kuo, EY; Rushton, MJD; Grimes, RW; Lumpkin, GR; Middleburgh, SC
Classical molecular dynamics simulations have been performed on uranium dioxide (UO2) employing a recently developed many-body potential model. Thermal conductivities are computed for a defect free UO2 lattice and a radiation-damaged, defect containing lattice at 300 K, 1000K and 1500 K. Defects significantly degrade the thermal conductivity of UO2 as does the presence of amorphous UO2, which has a largely temperature independent thermal conductivity of ∼1.4Wm−1 K−1. The model yields a pre-melting superionic transition temperature at 2600 K, very close to the experimental value and the mechanical melting temperature of 3600 K, slightly lower than those generated with other empirical potentials. The average threshold displacement energy was calculated to be 37 eV. Although the spatial extent of a 1 keV U cascade is very similar to those generated with other empirical potentials and the number of Frenkel pairs generated is close to that from the Basak potential, the vacancy and interstitial cluster distribution is different. © 2014, IOP Publishing Ltd.
Thermal conductivity variation in uranium dioxide with gadolinia additions
(Elsevier, 2020-11) Qin, MJ; Middleburgh, SC; Cooper, MWD; Rushton, MJD; Puide, M; Kuo, EY; Grimes, RW; Lumpkin, GR
By combining experimental observations on Gd doped fuel with a theoretical understanding, the variation in thermal conductivity with Gd concentration and accommodation mechanism has been modelled. Four types of Gd accommodation mechanisms have been studied. In UO2−x, isolated substitutional Gd3+ ions are compensated by oxygen vacancies and {2Gd'u:V"o}x defect clusters. In UO2, isolated substitutional Gd3+ ions are compensated by U5+ ions and {Gd'u:U'u}x defect clusters. The results indicate that defect clusters can be considered as less effective phonon scatterers and therefore result in less thermal conductivity degradation. The thermal conductivity predicted for UO2 with {Gd/u:U'u}x defect clusters is in good agreement with experimental data for UO2 with 5 wt% Gd2O3. This supports the previous theoretical results that Gd is accommodated through defect clusters {Gd'u:U'u}x in UO2 in the presence of excess oxygen. © 2020 Elsevier B.V.
The thermodynamics of hydride precipitation: the importance of entropy, enthalpy and disorder
(Elsevier, 2014-10-15) Lumley, SW; Grimes, RW; Murphy, ST; Burr, PA; Chroneos, A; Chard-Tuckey, PR; Wenmam, MR
The precipitation of zirconium hydrides from Zr solid solution was investigated using first-principles lattice dynamics simulations. These included the temperature-dependent vibrational enthalpy and vibrational entropy combined with the configurational entropy terms. In contrast with previous approaches, it was found that the latent enthalpy alone is not sufficient to fully describe precipitation of hydrides; a full thermodynamic assessment is required. In particular, the vibrational enthalpy of precipitation assists in stabilizing hexagonal close-packed hydrides and is especially important in forming the metastable ζζ phase. The configurational entropy change during precipitation favours face-centred cubic hydrides. Given this, at concentrations below 300 ppm H, no hydride precipitation is predicted, suggesting that when hydrides are seen in those materials it is because the local concentration of H is greater than that measured globally. While γγ hydride is the most stable phase, it is very close in energy to the δδ phase. © 2014 Acta Materialia Inc.

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