Nuclear fuel performance: Proceedings of the conference held in Stratford-upon-Avon on 25–29 March 1985
Emerald Publishing Limited
ISBN print:
978-0-7277-5161-4
Publication date:
1985
Book Chapter
72. Assessment of the behaviour of irradiated graphite fuel sleeves
By
M. S. Stucke, BSc, PhD, ARSM, DIC;
M. S. Stucke, BSc, PhD, ARSM, DIC
Search for other works by this author on:
A. J. Wickham, BSc, PhD, ARCS, MRSC, CChem
A. J. Wickham, BSc, PhD, ARCS, MRSC, CChem
Search for other works by this author on:
M. S. Stucke, BSc, PhD, ARSM, DIC
M. Jardine, BSc
R. M. Cornell, BSc
F. D. Evans, MRSC, CChem
A. J. Wickham, BSc, PhD, ARCS, MRSC, CChem
© British Nuclear Energy Society
1985
-
Published:1985
Citation
M. S. Stucke, BSc, PhD, ARSM, DIC, M. Jardine, BSc, R. M. Cornell, BSc, F. D. Evans, MRSC, CChem, A. J. Wickham, BSc, PhD, ARCS, MRSC, CChem, 1985. "72. Assessment of the behaviour of irradiated graphite fuel sleeves", Nuclear fuel performance: Proceedings of the conference held in Stratford-upon-Avon on 25–29 March 1985
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© British Nuclear Energy Society
1985
Introduction
Dimensional Changes
Radiolytic Oxidation
Sleeve Leak Rate
Differential Thermal Oxidation
Mechanical Properties
Concluding Remarks
Acknowledgements
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