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Fast Breeder Reactors - 1st Edition - ISBN: 9781483198415, 9781483223445

Fast Breeder Reactors

1st Edition

Proceedings of the London Conference on Fast Breeder Reactors Organized by the British Nuclear Energy Society, 17th–19th May 1966

Editor: P. V. Evans
eBook ISBN: 9781483223445
Imprint: Pergamon
Published Date: 1st January 1967
Page Count: 960
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Fast Breeder Reactors covers the proceedings of the 1966 London Conference on Fast Breeder Reactors, organized by the British Nuclear Energy Society. This conference highlights the technical and commercial aspects of nuclear power. This book is organized into five sections encompassing 37 chapters. The introductory section considers the historical development of British nuclear power technology and its application. This section provides an introduction to the principles of fast breeder reactor. The succeeding sections look into the mode of operation, and the design and physical aspects of prototype fast reactor. These sections also consider the theoretical and experimental works of these reactors in the United States. A description of the irradiation behavior of plutonium-bearing ceramic fuel pins is also included. The concluding section explores the control and instrumentation of the prototype fast reactor. This section specifically evaluates the main engineering equipment and the experimental work carried out in support of the selected designs, and to an explanation of certain problems of sodium technology. The design and experimental works on the main circulating pumps, the intermediate heat exchanger, and the steam generator are also surveyed. This book will prove useful to nuclear physicists, design engineers, and research workers who are interested in nuclear power-related fields.

Table of Contents

Opening Address

Session 1. The Place of the Fast Breeder Reactor in the Energy Programs (including Fuel Cycles)

The Place of the Fast Reactor in the United Kingdom Nuclear Program

A Review of Fast Reactor Development in the Euratom Community

The Place of Fast Reactors in the French Nuclear Program

Fast Breeder Reactor Program in the United States

The Place of the Fast Breeder Reactor in the Reactor Development Program in Japan

Design and Evaluation of a Steam Cooled Fast Breeder Reactor of 1000 MW(e)

Present and Future Types of Fast Breeder Reactors


Session 2. Operating Experience with Fast Reactors

EBR-II Initial Operation—Highlights

A Review of the Operation of the Dounreay Fast Reactor

Experience Gained from the Operation of the BR-5 Reactor, 1964-5

Recent Operating Experience at the Enrico Fermi Atomic Power Plant


Session 3. The Design of Fast Reactor Prototypes and Power Reactors (including Advanced Concepts with Coolants other than Sodium)

The BN-350 and BOR Fast Reactors

Fast Reactor Development in the United States

Design of the Prototype Fast Reactor

Design Studies of Fast Reactors in France

1000 MW(e) Sodium Cooled Fast Breeder Reactor Studies

Large Commercial Sodium Cooled Fast Reactors


Session 4A. Fast Reactor Physics, Part 1

The U.S. Experimental Program for Fast Reactor Physics

Fast Breeder Doppler Effect Investigations in Israel

Experimental and Theoretical Investigations on the Physics of Fast Reactors

Recent Theoretical Work in the United States on Fast Reactor Physics

Theoretical and Experimental Work on the Physics of Fast Reactors


Session 4B. Fuel Technology

Design and Development of Fuel and Fuel Elements for a Prototype Fast Reactor

Some Results of the Development of a Fast Reactor Fuel Element

Technology of Sodium Cooled Fast Reactor Fuels in the U.S.

The Irradiation Behavior of Plutonium-bearing Ceramic Fuel Pins


Session 5A. Fast Reactor Physics, Part 2

Physics, Kinetics, and Shielding of Fast Breeder Reactors—Survey of Recent Work Done in France

Some Physics Studies in Support of PFR Design

Theoretical and Experimental Works on Fast Reactor Physics in Japan

The Calculation of Large Fast Reactors

Control and Instrumentation of the Prototype Fast Reactor


Session 5B. Sodium Technology and Engineering of Fast Reactors

Sodium Technology and Equipment of the BN-350 Installation

Sodium Technology in Japan

Problems in the Selection and Utilization of Materials in Sodium Cooled Fast Reactors

United States Sodium Components Program

Engineering Development for Sodium Systems

Engineering Components for a Sodium Cooled Fast Power Reactor


Concluding Session


Name Index


No. of pages:
© Pergamon 1967
1st January 1967
eBook ISBN:

About the Editor

P. V. Evans

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