262 results on '"Wiss, T."'
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2. Single-step, high pressure, and two-step spark plasma sintering of UO2 nanopowders
3. Effect of molybdenum on the behaviour of caesium in uranium dioxide at high temperature
4. Thermal behaviour of caesium implanted in UO2: A comparative study with the xenon behaviour
5. Radiation effects in alpha-doped UO2
6. Elastic properties of severely degraded fuels
7. Melting behaviour of uranium-americium mixed oxides under different atmospheres
8. Helium diffusivity in oxide nuclear fuel: Critical data analysis and new correlations
9. TEM analysis of irradiation-induced interaction layers in coated UMo/X/Al trilayer systems (X= Ti, Nb, Zr, and Mo)
10. Physical and mechanical characterization of irradiated uranium dioxide with a broad burnup range and different dopants using acoustic microscopy
11. Cs diffusion mechanisms in UO2 investigated by SIMS, TEM, and atomistic simulations.
12. Determination of fission gas release of spent nuclear fuel in puncturing test and in leaching experiments under anoxic conditions
13. The dissolution of helium in La-doped UO2 as a surrogate of hypo-stoichiometric UO2
14. Quality improvements of thermodynamic data applied to corium interactions for severe accident modelling in SARNET2
15. Effect of 10B(n, α)7Li irradiation on the structure of a sodium borosilicate glass
16. Helium behaviour in stoichiometric and hyper-stoichiometric UO2
17. Thermal diffusion of helium in 238Pu-doped UO2
18. Fission product release and microstructure changes of irradiated MOX fuel at high temperatures
19. The mechanism of the hydrothermal alteration of cerium- and plutonium-doped zirconolite
20. The use of the electrochemical quartz crystal microbalance (EQCM) in corrosion studies of UO 2 thin film models
21. Neptunyl (Np [formula omitted]) interaction with green rust, [formula omitted]
22. Experimental investigation of the ionization mechanisms of uranium in thermal ionization mass spectrometry in the presence of carbon
23. Improvement of the European thermodynamic database NUCLEA
24. Cs diffusion mechanisms in UO2 investigated by SIMS, TEM, and atomistic simulations
25. Updates on European Americium Uranium Oxide Fuel and Clad Compatibility Tests for European Radioisotope Power Systems
26. Helium solubility and behaviour in uranium dioxide
27. Specific low temperature release of 131Xe from irradiated MOX fuel
28. Development of fuel-model interfaces: Investigations by XPS, TEM, SEM and AFM
29. Recent Results of Microstructural Characterization of Irradiated Light Water Reactor Fuels using Scanning and Transmission Electron Microscopy
30. Fission product release and microstructure changes during laboratory annealing of a very high burn-up fuel specimen
31. Growth mechanisms of interstitial loops in α-doped UO2 samples
32. Volatile fission product behaviour during thermal annealing of irradiated UO 2 fuel oxidised up to U 3O 8
33. Exploratory Research on Radioisotope Thermoelectric Generators for Deep Space Missions
34. Investigation on the use of Americium Oxide for Space Power Sources: Radiation Damage Studies
35. Helium Infusion In Nuclear Materials
36. Hydrothermal alteration of BaxMIV xCe2−2x (PO4)2 [MIV=Zr, Hf] as hosts for minor actinides
37. Helium release from plutonium and curium-doped zirconolite
38. Microgravimetric Corrosion Studies on UO2
39. Spent Fuel as Waste Material
40. Inert Matrix Fuel
41. Radiation Effects in UO2
42. Cesium and iodine release from fluoride-based molten salt reactor fuel
43. Actinides – A Challenge for Nuclear Forensics
44. Self-irradiation effects in UO 2 and (U,Pu)O 2 accelerated by doping with 238Pu
45. Particle Size vs. Local Environment Relationship for ThO2 and PuO
46. Hydrothermal alteration of BaxMIV xCe2−2x(PO4)2 [MIV=Zr, Hf] as hosts for minor actinides
47. Probing the Local Structure of Nanoscaled Actinide Oxides: A Comparison between PuO2 and ThO2 Nanoparticles Rules out PuO2+x Hypothesis
48. Helium solubility in oxide nuclear fuel: Derivation of new correlations for Henry’s constant
49. The thermal conductivity of Nd 2Zr 2O 7 pyrochlore and the thermal behaviour of pyrochlore-based inert matrix fuel
50. Study by microtomography of 3D porosity networks in irradiated beryllium
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