This volume brings together 47 papers from scientists involved in the fabrication of new nuclear fuels, in basic research of nuclear materials, their application and technology as well as in computer codes and modelling of fuel behaviour. The main emphasis is on progress in the development of non-oxide fuels besides reporting advances in the more conventional oxide fuels. The two currently performed large reactor safety programmes CORA and PHEBUS-FP are described in invited lectures. The contributions review basic property measurements, as well as the present state of fuel performance modelling. The performance of today's nuclear fuel, hence UO2, at high burnup is also reviewed with particular emphasis on the recently observed phenomenon of grain subdivision in the cold part of the oxide fuel at high burnup, the so-called qrimq effect. Similar phenomena can be simulated by ion implantation in order to better elucidate the underlying mechanism and reviews on high resolution electron microscopy provide further information. The papers will provide a useful treatise of views, ideas and new results for all those scientists and engineers involved in the specific questions of current nuclear waste management.At the bottom, label B, the back of the oxide layer adjacent to the alloy (oxide/ oxide interface of the aactive layera) is exposed. water pre-transition oxide Yo _ ... layers and the oxide of the active layer at the oxide/metal interface. polished cross sections of autoclave oxidised and irradiated PWR cladding materials. ... 4 shows a schematic diagram of the layer structure in the oxide scale on a PWR cladding.
|Title||:||Nuclear Materials for Fission Reactors|
|Author||:||H. Matzke, G. Schumacher|
|Publisher||:||Elsevier - 2012-12-02|