271 results on '"Corkhill, Claire L."'
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2. Crystal chemical design, synthesis and characterisation of U(IV)-dominant betafite phases for actinide immobilisation
3. Spectroscopic identification of Ca-bearing uranyl silicates formed in C–S–H systems
4. Oxidative dissolution of Cr-doped UO2 nuclear fuel
5. Localised extended (“vermiform”) features formed during glass dissolution
6. Bending Bad-Testing Caramel Wafer Bars (#TestATunnocks)
7. Stability of SrCO3 within composite Portland-slag cement blends
8. Synthesis and characterisation of Ce-doped zirconolite Ca0.80Ce0.20ZrTi1.60M0.40O7 (M = Fe, Al) formed by reactive spark plasma sintering (RSPS)
9. Investigating the mechanical behaviour of Fukushima MCCI using synchrotron Xray tomography and digital volume correlation
10. Surface interfacial analysis of simulant high level nuclear waste glass dissolved in synthetic cement solutions
11. Chemical characterisation of degraded nuclear fuel analogues simulating the Fukushima Daiichi nuclear accident
12. Cr2+ solid solution in UO2 evidenced by advanced spectroscopy
13. ‘Among his fellows cast’: A histotaphonomic investigation into the impact of the Black Death in England
14. Thermal treatment of Cs-exchanged chabazite by hot isostatic pressing to support decommissioning of Fukushima Daiichi Nuclear Power Plant
15. Early age hydration and application of blended magnesium potassium phosphate cements for reduced corrosion of reactive metals
16. Temperature transformation of blended magnesium potassium phosphate cement binders
17. Synthesis of Ca1-xCexZrTi2-2xAl2xO7 zirconolite ceramics for plutonium disposition
18. Synthesis and characterisation of Ca1-xCexZrTi2-2xCr2xO7: Analogue zirconolite wasteform for the immobilisation of stockpiled UK plutonium
19. The dissolution of simulant UK Ca/Zn-modified nuclear waste glass: the effect of increased waste loading
20. Synthesis and characterisation of HIP Ca0.80Ce0.20ZrTi1.60Cr0.40O7 zirconolite and observations of the ceramic–canister interface
21. Analysis of the Structure of Heavy Ion Irradiated LaFeO3 Using Grazing Angle X‑ray Absorption Spectroscopy.
22. Applying laboratory methods for durability assessment of vitrified material to archaeological samples
23. Forty years of durability assessment of nuclear waste glass by standard methods
24. Fenton and Fenton-like wet oxidation for degradation and destruction of organic radioactive wastes
25. Influence of accessory phases and surrogate type on accelerated leaching of zirconolite wasteforms
26. Synthesis, characterisation and preliminary corrosion behaviour assessment of simulant Fukushima nuclear accident fuel debris
27. Hot Isostatic Pressing (HIP): A novel method to prepare Cr-doped UO2 nuclear fuel
28. The dissolution of simulant UK Ca/Zn-modified nuclear waste glass: Insight into Stage III behavior
29. The dissolution of simulant vitrified intermediate level nuclear waste in young cement water
30. Analysis of the Structure of Heavy Ion Irradiated LaFeO3Using Grazing Angle X-ray Absorption Spectroscopy
31. Glass structure and crystallization in boro-alumino-silicate glasses containing rare earth and transition metal cations: a US-UK collaborative program
32. The Formation of Pitted Features on the International Simple Glass during Dynamic Experiments at Alkaline pH
33. Synthesis, characterisation and corrosion behaviour of simulant Chernobyl nuclear meltdown materials
34. The mineralogical and biogeochemical transformations associated with As-bearing sulphide minerals in acid mine drainage system
35. A Review of Zirconolite Solid Solution Regimes for Plutonium and Candidate Neutron Absorbing Additives
36. A multimodal X-ray spectroscopy investigation of uranium speciation in ThTi2O6 compounds with the brannerite structure.
37. Dissolution of glass in cementitious solutions: An analogue study for vitrified waste disposal
38. Leaching of Nirex Reference Vault Backfill cement by clay, granite and saline groundwaters
39. Investigation of the Effect of Milling Duration on a Ce-Gd Doped Zirconolite Phase Assemblage Synthesised by Hot Isostatic Pressing
40. Process Development of Zirconolite Ceramics for Pu Disposition: Use of a CuO Sintering Aid
41. Physical and optical properties of the International Simple Glass
42. An Investigation of Iodovanadinite Wasteforms for the Immobilisation of Radio-Iodine and Technetium.
43. Micro- and Nanoscale Surface Analysis of Late Iron Age Glass from Broborg, a Vitrified Swedish Hillfort
44. Effect of Zn- and Ca-oxides on the structure and chemical durability of simulant alkali borosilicate glasses for immobilisation of UK high level wastes
45. Geochemical association of Pu and Am in selected host-phases of contaminated soils from the UK and their susceptibility to chemical and microbiological leaching
46. Characterisation of a Complex CaZr0.9Ce0.1Ti2O7 Glass–Ceramic Produced by Hot Isostatic Pressing
47. Interactions between Simulant Vitrified Nuclear Wastes and high pH solutions: A Natural Analogue Approach
48. Evaluation of novel leaching assessment of nuclear waste glasses
49. Underpinning the use of indium as a neutron absorbing additive in zirconolite by X-ray absorption spectroscopy.
50. Corrosion of the International Simple Glass under acidic to hyperalkaline conditions
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