Radiation facilities for fusion-reactor first-wall and blanket structural-materials development

Technical Report · Tue Dec 01 00:00:00 EST 1981

DOI:https://doi.org/10.2172/5606747· OSTI ID:5606747

Klueh, R L; Bloom, E E

Present and future irradiation facilities for the study of fusion reactor irradiation damage are reviewed. Present studies are centered on irradiation in accelerator-based neutron sources, fast- and mixed-spectrum fission reactors, and ion accelerators. The accelerator-based neutron sources are used to demonstrate damage equivalence between high-energy neutrons and fission reactor neutrons. Once equivalence is demonstrated, the large volume of test space available in fission reactors can be used to study displacement damage, and in some instances, the effects of high-helium concentrations and the interaction of displacement damage and helium on properties. Ion bombardment can be used to study the mechanisms of damage evolution and the interaction of displacement damage and helium. These techniques are reviewed, and typical results obtained from such studies are examined. Finally, future techniques and facilities for developing damage levels that more closely approach those expected in an operating fusion reactor are discussed.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5606747
• Report Number(s): ORNL-5830; ON: DE82004557; TRN: 82-006965
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
THERMONUCLEAR REACTOR MATERIALS
TEST FACILITIES
BREEDING BLANKETS
FIRST WALL
HELIUM
IRRADIATION
MATERIALS TESTING
NEUTRON SOURCES
THERMONUCLEAR REACTORS
ELEMENTS
FLUIDS
GASES
MATERIALS
NONMETALS
PARTICLE SOURCES
RADIATION SOURCES
RARE GASES
REACTOR COMPONENTS
TESTING
THERMONUCLEAR REACTOR WALLS
700209* - Fusion Power Plant Technology- Component Development & Materials Testing