50 results on '"Rondinella, V. V."'
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2. Modelling of the (U1−y238Puy)O2+x Leaching Behaviour in Deionised Water under Anoxic Conditions
3. Ion chromatography inductively coupled plasma mass spectrometry (IC-ICP-MS) and radiometric techniques for the determination of actinides in aqueous leachate solutions from uranium oxide
4. Defect Structure and Stability in Uranium and Zirconium Nitrides
5. Xps and Sem Studies on the Corrosion of UO2 Cointaining Plutonium in Demineralized and Carbonated Water.
6. Leaching Behavior and α-Decay Damage Accumulation of UO2 Containing Short-Lived Actinides
7. α-Radiolysis and α-Radiation Damage Effects on UO2 Dissolution Under Spent Fuel Storage Conditions
8. Response of irradiated nuclear fuel rods to quasi-static and dynamic loads
9. Reductive precipitation of neptunium on iron surfaces under anaerobic conditions
10. High Frequency Acoustic Microscopy for the Determination of Porosity and Young’s Modulus in High Burnup Uranium Dioxide Nuclear Fuel
11. Evidence on spent fuel aging: Gas behaviour and Alpha-Damage
12. Analysis of the revaporisation behaviour of radioactive deposits of fission products in non-stationary thermal conditions and constant atmosphere
13. High frequency acoustic microscopy for the determination of porosity and Young's modulus in high burnup uranium dioxide nuclear fuel
14. New fixed-point mini-cell to investigate thermocouple drift in a high-temperature environment under neutron irradiation
15. Carbon nanotubes for potential applications in the field of nuclear waste management
16. 5 Diffusion in nitrides
17. 5 Diffusion in carbides
18. 5 Diffusion in hydrides
19. Characterization of alloy particles extracted from spent nuclear fuel
20. Hydrogen catalytic effects of nanostructured alloy particles in spent fuel on radionuclide immobilization
21. Immobilization of radionuclides on iron canister material at simulated near-field conditions
22. Comparison of theα-decay half-life ofPo210implanted in a copper matrix at 4.2 and 293 K
23. On the behaviour of spent fuel under simulated early canister-failure conditions
24. ChemInform Abstract: Failure Mechanisms of High Level Nuclear Waste Forms in Storage and Geological Disposal Conditions
25. Characterisation of high temperature refractory ceramics for nuclear applications
26. Investigation of high temperature irradiated fuel-liquefied Zircaloy interactions in support of severe accident safety studies
27. First‐principles modelling of defects in advanced nuclear fuels
28. Dose Rate Effects on the Accumulation of Radiation Damage
29. The Thermal Conductivity of Nd2Zr2O7 Pyrochlore and the Thermal Behavior of Pyrochlore‐Based Inert Matrix Fuel.
30. Studies on Spent Fuel Alterations During Storage and Radiolysis Effects on Corrosion Behaviour Using Alpha-Doped UO2
31. Xps and Sem Studies on the Corrosion of UO2Cointaining Plutonium in Demineralized and Carbonated Water.
32. Modelling of the (U1−y238Puy)O2+x Leaching Behaviour in Deionised Water under Anoxic Conditions.
33. Leaching Study of the Behaviour of Spent Fuel and SIMFUEL Under Simulated Granitic Repository Conditions
34. Xps and Sem Studies on the Corrosion of UO2 Cointaining Plutonium in Demineralized and Carbonated Water.
35. Leaching Behavior and α-Decay Damage Accumulation of UO2 Containing Short-Lived Actinides.
36. Effect of burn-up on the thermal conductivity of uranium--gadolinium dioxide up to 100 GWd/tHM.
37. α-Radiolysis and α-Radiation Damage Effects on uo2 Dissolution Under Spent Fuel Storage Conditions
38. Comparison of the Leaching Behaviour of Irradiated Fuel, SIMFUEL, and Non-Irradiated U02 under Oxic Conditions
39. First-principles modelling of defects in advanced nuclear fuels.
40. Influence of Plutonium on the Dissolution Behavior of the Spent-Fuel Matrix.
41. Radiation damage and simulated fission product effects on the properties of inert matrix materials
42. Damage produced in magnesium aluminate spinel by high energy heavy ions including fission products of fission energy: microstructure modifications
43. Leaching of SIMFUEL in simulated granitic water: comparison to results in demineralized water
44. Defect structure and stability in uranium, zirconium and titanium nitrides
45. Destructive tests for determining mechanical integrity of spent nuclear fuel rods
46. Mechanical integrity studies on spent nuclear fuel rods
47. Experimental studies on the revaporisation behaviour and aerosol formation of caesium under severe accident conditions
48. The Thermal Conductivity of Nd2Zr2O7 Pyrochlore and the Thermal Behavior of Pyrochlore-Based Inert Matrix Fuel.
49. The Thermal Conductivity of Nd2Zr2O7Pyrochlore and the Thermal Behavior of Pyrochlore‐Based Inert Matrix Fuel.
50. Comparison of the a-decay half-life of 210Po implanted in a copper matrix at 4.2 and 293 K.
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