Measurement of Irradiation-Enhanced Creep in Nuclear Materials

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

1st Edition - January 1, 1977
Editors: M.R. Cundy, P. Von der Hardt, R.H. Loelgen
Language: English
eBook ISBN:
9 7 8 - 1 - 4 8 3 1 - 6 3 9 0 - 1

Measurement of Irradiation-Enhanced Creep in Nuclear Materials covers the proceedings of an international conference organized by the commission of the European communities. The… Read more

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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.

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

Results of In-Pile Creep Measurements on Pressurized Capsules Made of Stabilized Stainless Steels WNr.1.4981, CW and WNr.1.4970, CW,A

Irradiation Creep of Stainless Steel in Bending

In-Reactor Stress Relaxation in Bending of 20% Cold-Worked 316 Stainless Steel

Irradiation Induced Creep Experiments in the BR2 Reactor Using the Resonant Cavity Method

Irradiation Creep in Zr Single Crystals

Volumetric Creep in Nickel: The Influence of Stress on Swelling

Irradiation Creep Data in Support of LMFBR Core Design

The Irradiation Creep of Nickel and AISI 321 Stainless Steel during 4 MeV Proton Bombardment

Electron Induced Irradiation Creep and Direct Observation of the Underlying Dislocation Processes Involved

Design of an Irradiation Device for the Determination of the In-Pile Creep Behavior of Zircaloy Cladding Tubes under Internal and External Over-Pressure, in FRG-2

In-Pile Creep Measuring Rigs for Metallic Specimens

The Dounreay Fast-Reactor Uniaxial Creep-Measuring Machine

Zircaloy-2 Irradiation Creep Strain Measurement Techniques

Author Index