Measurement of Irradiation-Enhanced Creep in Nuclear Materials - 1st Edition - ISBN: 9780720405729, 9781483163901

Measurement of Irradiation-Enhanced Creep in Nuclear Materials

1st Edition

Proceedings of an International Conference Organized by the Commission of the European Communities at the Joint Research Centre, Petten, The Netherlands, May 5–6, 1976

Editors: M.R. Cundy P. Von der Hardt R.H. Loelgen
eBook ISBN: 9781483163901
Imprint: North Holland
Published Date: 1st January 1977
Page Count: 350
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Measurement of Irradiation-Enhanced Creep in Nuclear Materials covers the proceedings of an international conference organized by the commission of the European communities. The book presents 37 papers that are organized according to the session of the conference. Each session focuses on various topics that relate to the irradiation creep of a specific material, which are ceramic nuclear fuels, graphite, and non-fissile metal and alloys. The text will be of great use for researchers and professionals whose work involves quantifying irradiation creep in nuclear materials.

Table of Contents

Introduction/Preface List of Participants Session I: Irradiation Creep of Ceramic Nuclear Fuels Irradiation Induced Creep of Ceramic Nuclear Fuels Oxide Fuel In-Reactor Creep - LMFBR Design Aspects Interpreting and Predicting Irradiation Creep by Fuel Element Modeling Creep Properties of Oxide and Carbide Fuels Under Irradiation In-Pile Creep Study On Mixed Oxide (U,Pu)O2 In-Pile Measurement of Fission Enhanced Creep and Swelling of Uranium Nitride Measurement of the Diametral Evolution of a Fuel Element during Its Irradiation. The MEDINA Device Irradiation Devices for the Study of Creep and Swelling in Ceramic Fuels Session II: Irradiation Creep of Graphite Radiation Creep of Graphite. An Introduction UKAEA Reactor Group Studies of Irradiation-Induced Creep in Graphite Review of a Test Program on Irradiation Creep of Graphites and Systemization of Results Design, Operation, and Initial Results from a Series of Graphite Creep Irradiation Experiments Joint Program of Uni-Axial Creep Measurements of HTR Compacts and Matrix Material under Tensile Load at 900°C The Creep Strain Limit Experiment Reloadable Graphite Creep Facility for Tensile or Compressive Experiments Graphite High Temperature Creep Rigs Uni-Axial Tensile Graphite Creep Capsules with Continuous Strain Registration Session III: Irradiation Creep in Non-Fissile Metals and Alloys Irradiation Creep in Non-Fissile Metals and Alloys Void Swelling and Irradiation Creep Relationships The Temperature Dependence of Irradiation Creep Requirements for In-Reactor Zircaloy Creep Measurements for Application in the Design of PWR Fuel Irradiation Enhanced Creep in LMFBR Fuel Element Cladding Dependence of Irradiation Creep on Temperature and Atom Displacements in 20% Cold Worked 316 Type Stainless Steel In-Reactor Deformation of Solution Annealed Type 304L Stainless Steel


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© North Holland 1977
North Holland
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About the Editor

M.R. Cundy

P. Von der Hardt

R.H. Loelgen

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