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
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Related Subjects
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
BREEDING BLANKETS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYOGENIC FLUIDS
ELEMENTS
FIRST WALL
FLUIDS
HEAT RESISTING ALLOYS
HELIUM
HYDROGEN COMPOUNDS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METALS
LIQUIDS
MATERIALS TESTING
METALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NONMETALS
OXYGEN COMPOUNDS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RARE GASES
REACTOR COMPONENTS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
SWELLING
TESTING
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS
TITANIUM ALLOYS
TRANSITION ELEMENTS
VANADIUM
WATER
360106 -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
BREEDING BLANKETS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYOGENIC FLUIDS
ELEMENTS
FIRST WALL
FLUIDS
HEAT RESISTING ALLOYS
HELIUM
HYDROGEN COMPOUNDS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METALS
LIQUIDS
MATERIALS TESTING
METALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NONMETALS
OXYGEN COMPOUNDS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RARE GASES
REACTOR COMPONENTS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
SWELLING
TESTING
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS
TITANIUM ALLOYS
TRANSITION ELEMENTS
VANADIUM
WATER