Properties of Fuels for High-temperature Reactor Concepts

Roy W. Endebrock

Battelle Memorial Institute, 1962 - Gas cooled reactors

Contents

• PREFACE: 1
• GENERAL: 20
• PLUTONIUM DIOXIDE: 26
• THORIUM URANIUM BORIDE: 32
• THORIUM URANIUM DICARBIDE: 40
• URANIUM MONONITRIDE: 57
• URANIUM SILICIDE: 97
• UO2A1203 DISPERSIONS: 101
• UO2BEO DISPERSIONS: 109
• UO2MgO DISPERSIONS: 127
• STAINLESS STEELUO2 DISPERSION FUEL: 156
• 78: 169

Bibliographic information

• Title: Properties of Fuels for High-temperature Reactor Concepts; BMI (Series); UC (Series). 25, Metallurgy, Ceramics and Materials
• Editor: Roy W. Endebrock
• Contributors: Battelle Memorial Institute, U.S. Atomic Energy Commission
• Publisher: Battelle Memorial Institute, 1962
• Original from: the University of Michigan
• Digitized: Jul 29, 2014