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| Preface | |
| Supporting Organizations and Sponsors | |
| Irradiation behavior of metallic fast reactor fuels | p. 3 |
| MOX fuel development: yesterday, today and tomorrow | p. 10 |
| Development and characteristics of the rim region in high burnup UO[subscript 2] fuel pellets | p. 19 |
| Preparation of uranium nitride in the form of microspheres | p. 28 |
| Mechanism and kinetics of the uranium-plutonium mononitride synthesis | p. 36 |
| Irradiation of a 19 pin subassembly with mixed carbide fuel in KNK II | p. 43 |
| Fission product behaviour in Phenix fuel pins at high burnup | p. 49 |
| Fission product behaviour in fast breeder fuel pins | p. 58 |
| Microstructural change and its influence on fission gas release in high burnup UO[subscript 2] fuel | p. 65 |
| Concerning the microstructure changes that occur at the surface of UO[subscript 2] pellets on irradiation to high burnup | p. 73 |
| Microstructural analysis of LWR spent fuels at high burnup | p. 80 |
| Transmission electron microscopy study of fission product behaviour in high burnup UO[subscript 2] | p. 90 |
| Fuel performance under normal PWR conditions: A review of relevant experimental results and models | p. 96 |
| Fuel rod and core materials investigations related to LWR extended burnup operation | p. 104 |
| The Phebus fission product project | p. 115 |
| Information on the evolution of severe LWR fuel element damage obtained in the CORA program | p. 131 |
| Fuel behaviour under severe accident conditions: Interpretation of PTE results from the CABRI test programme | p. 146 |
| Failure behavior of plutonium-uranium mixed oxide fuel under reactivity-initiated accident condition | p. 154 |
| Transient fuel behavior of preirradiated PWR fuels under reactivity initiated accident conditions | p. 162 |
| UO[subscript 2] fuel behavior under RIA type tests | p. 168 |
| On the kinetics of UO[subscript 2] interaction with molten Zircaloy at high temperatures | p. 177 |
| Neutron irradiation effects in boron carbides: Evolution of microstructure and thermal properties | p. 185 |
| On the theory of high temperature transition in fluorite-type oxides | p. 189 |
| Thermal conductivity of(U, Pu)O[subscript 2-x] mixed oxide fuel | p. 194 |
| Thermal conductivity of SIMFUEL | p. 198 |
| High temperature heat capacities and electrical conductivities of UO[subscript 2] doped with yttrium and simulated fission products | p. 205 |
| Defect structure and oxygen diffusion in UO[subscript 2+[delta]] | p. 210 |
| A comparison of the behaviour of fission gases in [actual symbol not reproducible] and [alpha]-U[subscript 3]O[subscript 8-z] | p. 216 |
| Effect of temperature on bubble precipitation in uranium dioxide implanted with krypton and xenon ions | p. 222 |
| Investigation of nuclear mixed oxide fuel-gas interaction by a solid electrolyte based coulometric technique | p. 226 |
| Nonideality of the solid solution in (U, Pu)O[subscript 2] nuclear fuels M. Beauvy | p. 232 |
| Vaporization behavior of uranium-plutonium mixed nitride | p. 239 |
| The fate of nitrogen upon reprocessing of nitride fuels | p. 244 |
| Stability and structure of the [delta] phase of the U-Zr alloys | p. 249 |
| Study of the oxidation of a stainless steel under BWR conditions by advanced analytical techniques | p. 255 |
| Modelling of inert gas bubble behaviour during annealing of irradiated molybdenum | p. 258 |
| Mass and gamma spectrometric measurements of fission products released from overheated, fresh irradiated, uranium dioxide | p. 262 |
| Structural analysis of oxide scales grown on zirconium alloys in autoclaves and in a PWR | p. 273 |
| Carbon activity measurements in boron carbides using a solid state potentiometric cell | p. 280 |
| Ion implantation studies UO[subscript 2] and UN | p. 285 |
| TRANSURANUS: a fuel rod analysis code ready for use | p. 295 |
| GERMINAL - A computer code for predicting fuel pin behaviour | p. 303 |
| Modelling fission gas behaviour in mixed oxide fuel under normal and off-normal conditions in fast reactors | p. 308 |
| Mechanistic model of fission gas behavior in metallic fuel | p. 312 |
| Simplified model for the analysis on the duct wall deflection due to in-reactor creep in LMFBR fuel assemblies | p. 319 |
| Modelling of (U, Gd)O[subscript 2] fuel behaviour in boiling water reactors | p. 323 |
| Development of the Thermal behavior analysis code DIRAD and the fuel design procedure for LMFBR | p. 331 |
| Author index | p. 337 |
| Subject index | p. 341 |
| Table of Contents provided by Blackwell. All Rights Reserved. |
