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Mechanical properties of transient-tested irradiated fast reactor cladding

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6433285
;
None
Research Organization:
Hanford Engineering Development Lab., Richland, WA
OSTI ID:
6433285
Report Number(s):
CONF-7811109-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 30
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL CANS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MATERIALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRESSES
SWELLING
TEST REACTORS
TRANSIENTS