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Program for alloy development for irradiation performance in fusion reactors

Conference ·
OSTI ID:7210335
;

The use of fission reactors as irradiation test facilities for structural materials for a fusion environment is discussed. A comparison is made of displacement damage and helium production in fast fission and fusion reactors for stainless steel. (MOW)

Research Organization:
Oak Ridge National Lab., TN (USA); Energy Research and Development Administration, Washington, DC (USA). Div. of Magnetic Fusion Energy
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
7210335
Report Number(s):
CONF-770523-10
Country of Publication:
United States
Language:
English

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Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
CHROMIUM ALLOYS
CORROSION RESISTANT ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS TESTING
NEUTRON FLUX
PHYSICAL RADIATION EFFECTS
PLANNING
RADIATION EFFECTS
RADIATION FLUX
RESEARCH PROGRAMS
STAINLESS STEELS
STEELS
TEST FACILITIES
TESTING
THERMONUCLEAR REACTOR MATERIALS