Sökning: "γ-irradiation"
Visar resultat 1 - 5 av 18 avhandlingar innehållade ordet γ-irradiation.
1. Stability and sorption capacity of montmorillonite colloids : Investigation of size fractional differences and effects of γ-irradiation
Sammanfattning : Bentonite clay is intended to form one of the barriers in most repositories of spent nuclear fuel located in granite. One important function of the bentonite barrier is to retard transport of radionuclides in the event of waste canister failure. Bentonite has a high sorption capacity of cations and its main constituent is montmorillonite. LÄS MER
2. Assessment of acetabular cup wear with computed tomography and influence of surface roughness on wear of materials for hip prostheses
Sammanfattning : Over one million hip prostheses are implanted in patients worldwide each year and the need is increasing as the patient group of younger and more active patients is increasing. Many parameters affect the longevity of the implant, where aseptic loosening caused by wear debris is the most common reason for revision. LÄS MER
3. Computed Tomography of Acetabular Cup Wear and Effect of Surface Roughness on Wear and Oxidation of UHMWPE Hip Prostheses
Sammanfattning : Aseptic loosening is the most common complication in total hip replacement (5- 10% at 10 years follow up). The magnitude of the problem is illustrated by the fact that about one million hip prostheses are implanted worldwide each year. LÄS MER
4. Long-term performance of polymeric materials in nuclear power plants
Sammanfattning : Access to energy is crucial for modern societies to function sustainably. In addition, nuclear power has for a long time been considered a reliable source of energy. However, the majority of nuclear power plants are reaching the end of their service lifetimes, and it is crucial to verify that every component can withstand the added service time. LÄS MER
5. The bentonite barrier : microstructural aspects on colloid filtration and radiation effects on bentonite colloid stability
Sammanfattning : In many countries a multi-barrier concept in a deep geological repository is planned for final disposal of nuclear waste. Many of these different concepts, for example the Swedish KBS-3 model, include an engineered barrier consisting of compacted bentonite. LÄS MER