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U.S. Department of Energy
Office of Scientific and Technical Information

Alloy development for irradiation performance: program strategy

Conference ·
OSTI ID:7073279

The objective of the Alloy Development for Irradiation Performance Program is the development of structural materials for use in the first wall and blanket region of fusion reactors. The goal of the program is a material that will survive an exposure of 40 MWyr/m/sup 2/ at a temperature which will allow use of a liquid-H/sub 2/O heat transport system. Although the ultimate aim of the program is development of materials for commercial reactors by the end of this century, activities are organized to provide materials data for the relatively low performance interim machines that will precede commercial reactors.

Research Organization:
Oak Ridge National Lab., TN (USA); Department of Energy, Washington, DC (USA); Westinghouse Research and Development Center, Pittsburgh, PA (USA); Hanford Engineering Development Lab., Richland, WA (USA); McDonnell Douglas Astronautics Co., St. Louis, MO (USA); Argonne National Lab., IL (USA)
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
7073279
Report Number(s):
CONF-780508-36
Country of Publication:
United States
Language:
English