Nuclear Materials for Fission Reactors

Content: 
EUROPEAN MATERIALS RESEARCH SOCIETY SYMPOSIA PROCEEDINGS, Page ii
Front Matter, Page iii
Copyright, Page iv
Preface, Page vii, Hj. Matzke, G. Schumacher
Supporting Organizations and Sponsors, Page viii
Irradiation behavior of metallic fast reactor fuels, Pages 3-9, R.G. Pahl, D.L. Porter, D.C. Crawford, L.C. Walters
MOX fuel development: yesterday, today and tomorrow, Pages 10-18, H. Bairiot, P. Deramaix
Development and characteristics of the rim region in high burnup UO2 fuel pellets, Pages 19-27, M.E. Cunningham, M.D. Freshley, D.D. Lanning
Preparation of uranium nitride in the form of microspheres, Pages 28-35, G. Ledergerber, Z. Kopajtic, F. Ingold, R.W. Stratton
Mechanism and kinetics of the uranium–plutonium mononitride synthesis, Pages 36-42, Philippe Bardelle, Dominique Warin
Irradiation of a 19 pin subassembly with mixed carbide fuel in KNK II, Pages 43-48, D. Geithoff, G. Mühling, K. Richter
Fission product behaviour in Phenix fuel pins at high burnup, Pages 49-57, M. Tourasse, M. Boidron, B. Pasquet
Fission product behaviour in fast breeder fuel pins, Pages 58-64, O. Götzmann
Microstructural change and its influence on fission gas release in high burnup UO2 fuel, Pages 65-72, K. Une, K. Nogita, S. Kashibe, M. Imamura
Concerning the microstructure changes that occur at the surface of UO2 pellets on irradiation to high burnup, Pages 73-79, C.T. Walker, T. Kameyama, S. Kitajima, M. Kinoshita
Microstructural analysis of LWR spent fuels at high burnup, Pages 80-89, L.E. Thomas, C.E. Beyer, L.A. Charlot
Transmission electron microscopy study of fission product behaviour in high burnup UO2, Pages 90-95, I.L.F. Ray, H. Thiele, Hj. Matzke
Fuel performance under normal PWR conditions: A review of relevant experimental results and models, Pages 96-103, M. Charles, C. Lemaignan
Fuel rod and core materials investigations related to LWR extended burnup operation, Pages 104-112, Erik Kolstad, Carlo Vitanza
The Phebus fission product project, Pages 115-130, P. von der Hardt, A. Tattegrain
Information on the evolution of severe LWR fuel element damage obtained in the CORA program, Pages 131-145, G. Schanz, S. Hagen, P. Hofmann, G. Schumacher, L. Sepold
Fuel behaviour under severe accident conditions: Interpretation of PTE results from the CABRI test programme, Pages 146-153, H. Steiner
Failure behavior of plutonium–uranium mixed oxide fuel under reactivity-initiated accident condition, Pages 154-161, T. Abe, N. Nakae, K. Kodato, M. Matsumoto, T. Inabe
Transient fuel behavior of preirradiated PWR fuels under reactivity initiated accident conditions, Pages 162-167, Toshio Fujishiro, Kazuaki Yanagisawa, Kiyomi Ishijima, Koreyuki Shiba
UO2 fuel behavior under RIA type tests, Pages 168-176, Gheorghe Negut, Mircea Popov
On the kinetics of UO2 interaction with molten Zircaloy at high temperatures, Pages 177-182, M.S. Veshchunov, A.M. Volchek
Neutron irradiation effects in boron carbides: Evolution of microstructure and thermal properties, Pages 185-188, K. Froment, D. Gosset, M. Guéry, B. Kryger, C. Verdeau
On the theory of high temperature transition in fluorite-type oxides, Pages 189-193, M.S. Veshchunov
Thermal conductivity of (U, Pu)O2−x mixed oxide fuel, Pages 194-197, Y. Philipponneau
Thermal conductivity of SIMFUEL, Pages 198-204, P.G. Lucuta, Hj. Matzke, R.A. Verrall, H.A. Tasman
High temperature heat capacities and electrical conductivities of UO2 doped with yttrium and simulated fission products, Pages 205-209, Tsuneo Matsui, Yuji Arita, Keiji Naito
Defect structure and oxygen diffusion in UO2+δ, Pages 210-215, J.P. Goff, B. Fåk, W. Hayes, M.T. Hutchings
A comparison of the behaviour of fission gases in UO2±x and α-U3O8−z, Pages 216-221, Richard G.J. Ball, Robin W. Grimes
Effect of temperature on bubble precipitation in uranium dioxide implanted with krypton and xenon ions, Pages 222-225, J.H. Evans
Investigation of nuclear mixed oxide fuel–gas interaction by a solid electrolyte based coulometric technique, Pages 226-231, K. Teske, C. Nebelung, H. Ullman, I.I. Kapshukov, L.V. Sudakov, A.S. Bevz
Nonideality of the solid solution in (U, Pu)O2 nuclear fuels, Pages 232-238, Michel Beauvy
Vaporization behavior of uranium–plutonium mixed nitride, Pages 239-243, Yasufumi Suzuki, Atsushi Maeda, Yasuo Arai, Toshihiko Ohmichi
The fate of nitrogen upon reprocessing of nitride fuels, Pages 244-248, N. Hadibi-Olschewski, J.-P. Glatz, H. Bokelund, M.J.-F. Leroy
Stability and structure of the δ phase of the U–Zr alloys, Pages 249-254, M. Akabori, A. Itoh, T. Ogawa, F. Kobayashi, Y. Suzuki
Study of the oxidation of a stainless steel under BWR conditions by advanced analytical techniques, Pages 255-257, C. Degueldre, J.C. Dran, E. Schenker
Modelling of inert gas bubble behaviour during annealing of irradiated molybdenum, Pages 258-261, V.F. Chkuaseli
Mass and gamma spectrometric measurements of fission products released from overheated, fresh irradiated, uranium dioxide, Pages 262-272, R.H.J. Tanke
Structural analysis of oxide scales grown on zirconium alloys in autoclaves and in a PWR, Pages 273-279, H. Blank, G. Bart, H. Thiele
Carbon activity measurements in boron carbides using a solid state potentiometric cell, Pages 280-284, Karine Froment, Christian Chatillon, Jacques Fouletier, Mireille Fouletier
Ion implantation studies of UO2 and UN, Pages 285-292, Hj. Matzke, A. Turos
TRANSURANUS: a fuel rod analysis code ready for use, Pages 295-302, K. Lassmann
GERMINAL – A computer code for predicting fuel pin behaviour, Pages 303-307, J.C. Melis, L. Roche, J.P. Piron, J. Truffert
Modelling fission gas behaviour in mixed oxide fuel under normal and off-normal conditions in fast reactors, Pages 308-311, L. Väth
Mechanistic model of fission gas behavior in metallic fuel, Pages 312-318, Y. Tsuboi, T. Ogata, M. Kinoshita, H. Saito
Simplified model for the analysis on the duct wall deflection due to in-reactor creep in LMFBR fuel assemblies, Pages 319-322, S. Komoda, N. Nakae, M. Matsumoto
Modelling of (U, Gd)O2 fuel behaviour in boiling water reactors, Pages 323-330, A.R. Massih, S. Persson, Z. Weiss
Development of the thermal behavior analysis code DIRAD and the fuel design procedure for LMFBR, Pages 331-336, N. Nakae, K. Tanaka, H. Nakajima, M. Matsumoto
Author Index, Pages 337-339
Subject index, Pages 341-348