Nuclear Materials for Fission Reactors: Proceedings of Symposium E on Nuclear Materials for Fission Reactors of the 1991 E-Mrs Fall Conference : Str
, by Matzke, Hj; Schumacher, G.Note: Supplemental materials are not guaranteed with Rental or Used book purchases.
- ISBN: 9780444895714 | 044489571X
- Cover: Hardcover
- Copyright: 9/1/1992
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. |
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