High temperature compatibility issues for fusion reactor structural materials

B. A. Pint; J. R. DiStefano; P. F. Tortorelli

doi:10.13182/FST03-A373

High temperature compatibility issues for fusion reactor structural materials

B. A. Pint, J. R. DiStefano, P. F. Tortorelli

Materials Science and Technology Div

Oak Ridge National Laboratory

Research output: Contribution to journal › Article › peer-review

5 Scopus citations

Abstract

The primary functions of the blanket in a deuterium/tritium-fueled fusion reactor are to convert neutron kinetic energy into heat, breed tritium for the fuel cycle and accommodate a heat transfer system. Various blanket concepts have been considered including those incorporating liquid metals, molten salts, water and He. The objective of this review is to outline some of the critical compatibility issues associated with structural materials being considered for designs operating at >500°C. Examples are given for vanadium alloys, magnetohydrodynamic coatings, oxide dispersion strengthened ferritic alloys and silicon carbide composites.

Original language	English
Pages (from-to)	433-440
Number of pages	8
Journal	Fusion Science and Technology
Volume	44
Issue number	2
DOIs	https://doi.org/10.13182/FST03-A373
State	Published - Sep 2003

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AB - The primary functions of the blanket in a deuterium/tritium-fueled fusion reactor are to convert neutron kinetic energy into heat, breed tritium for the fuel cycle and accommodate a heat transfer system. Various blanket concepts have been considered including those incorporating liquid metals, molten salts, water and He. The objective of this review is to outline some of the critical compatibility issues associated with structural materials being considered for designs operating at >500°C. Examples are given for vanadium alloys, magnetohydrodynamic coatings, oxide dispersion strengthened ferritic alloys and silicon carbide composites.

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High temperature compatibility issues for fusion reactor structural materials

Abstract

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