Nuclear Materials for Fission Reactors - 1st Edition - ISBN: 9780444895714, 9780444596833

Nuclear Materials for Fission Reactors, Volume 28

1st Edition

Editors: H. Matzke G. Schumacher
Hardcover ISBN: 9780444895714
eBook ISBN: 9780444596833
Imprint: North Holland
Published Date: 21st August 1992
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Table of Contents

(Abbreviated). Sections: I. Fuel Fabrication and Performance. Irradiation behaviour of metallic fast reactor fuels (R.G. Pahl et al.). Preparation of uranium nitride in the form of microspheres (G. Ledergerber et al.). Fission product behaviour in Phenix fuel pins at high burnup (M. Tourasse et al.). Concerning the microstructure changes that occur at the surface of UO2 pellets on irradiation to high burnup (C.T. Walker et al.). Fuel performance under normal PWR conditions: A review of relevant experimental results and models (M. Charles, C. Lemaignan).II. Reactor Safety. The Phebus fission product project (P. von der Hardt, A. Tattegrain). Information on the evolution of severe LWR fuel element damage obtained in the CORA programme (G. Schanz et al.). Transient fuel behaviour of preirradiated PWR fuels under reactivity initiated accident conditions (T. Fujishiro et al.). On the kinetcs of UO2 interaction with molten Zircaloy at high temperatures (M.S. Veshchunov. A.M. Volchek). III. Basic Properties of Nuclear Materials. Neutron irradiation effects in boron carbides: Evolution of microstructure and thermal properties (K. Froment et al.). Thermal conductivity of SIMFUEL (P.G. Lucuta et al.). Effect of temperature on bubble precipitation in uranium dioxide implanted with krypton and xenon ions (J.H. Evans). Vaporization behaviour of uranium-plutonium mixed nitride (Y. Suzuki et al.). Study of the oxidation of a stainless steel under BWR conditions by advanced analytical techniques (C. Degueldre et al.). Structural analysis of oxide scales grown on zirconium alloys in autoclaves and in a PWR (H. Blank et al.). IV. Modelling of Fuel Performance. TRANSURANUS: A fuel rod analysis code ready for use (K. Lassmann). Mechanistic model of fission gas behaviour in metallic fuel (Y. Tsuboi et al.). Development of the thermal behaviour analysis code DIRAD and the fuel design procedure for LMFBR (N. Nakae et al.). Author index. Subject index.


Description

(Abbreviated). Sections: I. Fuel Fabrication and Performance. Irradiation behaviour of metallic fast reactor fuels (R.G. Pahl et al.). Preparation of uranium nitride in the form of microspheres (G. Ledergerber et al.). Fission product behaviour in Phenix fuel pins at high burnup (M. Tourasse et al.). Concerning the microstructure changes that occur at the surface of UO2 pellets on irradiation to high burnup (C.T. Walker et al.). Fuel performance under normal PWR conditions: A review of relevant experimental results and models (M. Charles, C. Lemaignan).II. Reactor Safety. The Phebus fission product project (P. von der Hardt, A. Tattegrain). Information on the evolution of severe LWR fuel element damage obtained in the CORA programme (G. Schanz et al.). Transient fuel behaviour of preirradiated PWR fuels under reactivity initiated accident conditions (T. Fujishiro et al.). On the kinetcs of UO2 interaction with molten Zircaloy at high temperatures (M.S. Veshchunov. A.M. Volchek). III. Basic Properties of Nuclear Materials. Neutron irradiation effects in boron carbides: Evolution of microstructure and thermal properties (K. Froment et al.). Thermal conductivity of SIMFUEL (P.G. Lucuta et al.). Effect of temperature on bubble precipitation in uranium dioxide implanted with krypton and xenon ions (J.H. Evans). Vaporization behaviour of uranium-plutonium mixed nitride (Y. Suzuki et al.). Study of the oxidation of a stainless steel under BWR conditions by advanced analytical techniques (C. Degueldre et al.). Structural analysis of oxide scales grown on zirconium alloys in autoclaves and in a PWR (H. Blank et al.). IV. Modelling of Fuel Performance. TRANSURANUS: A fuel rod analysis code ready for use (K. Lassmann). Mechanistic model of fission gas behaviour in metallic fuel (Y. Tsuboi et al.). Development of the thermal behaviour analysis code DIRAD and the fuel design procedure for LMFBR (N. Nakae et al.). Author index. Subject index.


Details

Language:
English
Copyright:
© North Holland 1992
Published:
Imprint:
North Holland
eBook ISBN:
9780444596833

About the Editors

H. Matzke Editor

Affiliations and Expertise

European Institute of Transuranium Elements, Karlsruhe, Germany

G. Schumacher Editor

Affiliations and Expertise

Kernforschungszentrum Karlsruhe, Germany