Mechanical Behavior & Diffusion Of Gas During Neutron Irradiation Of Actinides In Ceramic Inert Matrices

This is a Ph.D. dissertation. Ordinary reactor fuel for commercial nuclear reactors is UO2. The Uranium is a mixture of the fissile isotope 235U and the fertile isotope 238U. The disadvantage of 238U is that other actinides are generated during neutron irradiation. Some of these actinides have very long half-lives. Consequently, the time that spent fuel is more radiotoxic than uranium ore is about 200,000 years. Spent fuel is composed of actinides and fission products. Contents include: Experimental Methods, Modeling of Helium in MgAl204, Diffusion of Helium in Helium Implanted Sampled of MgAl204, Inert Matrix Fuels.Neeft, Erika is the author of 'Mechanical Behavior & Diffusion Of Gas During Neutron Irradiation Of Actinides In Ceramic Inert Matrices', published 2004 under ISBN 9789040724756 and ISBN 904072475X.