In situ observation of axial irradiation growth in liquid-metal reactor metal fuel

Conference · Sun Jan 01 00:00:00 EST 1989 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6530621

Cramer, E R; Pitner, A L

Effects of the rapid early-in-life expansion of metal fuel were measured in an irradiation experiment in the Fast Flux Test Facility (FFTF). This important performance/design information was obtainable through the unique combination of a dimensionally stable FFTF oxide core and the calibrated proximity instrumentation associated with the test. These results delineate the time dependence of metal-fuel swelling and provide quantitative estimates of the magnitude of axial fuel swelling in full-length metal-fuel assemblies. Final posttest examination results will define actual fuel column growth levels.

• OSTI ID: 6530621
• Report Number(s): CONF-891103-; CODEN: TANSA; TRN: 90-035267
• Journal Information: Transactions of the American Nuclear Society; (USA), Vol. 60; Conference: Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit, San Francisco, CA (USA), 26-30 Nov 1989; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
FUEL ELEMENTS
RESEARCH PROGRAMS
LMFBR TYPE REACTORS
NUCLEAR FUELS
PHYSICAL RADIATION EFFECTS
ALLOY-HT-9
BURNUP
CALIBRATION
DEFORMATION
DESIGN
FFTF REACTOR
IRRADIATION
POST-IRRADIATION EXAMINATION
QUANTITY RATIO
REACTOR INSTRUMENTATION
STABILITY
SWELLING
TIME DEPENDENCE
URANIUM
ZIRCONIUM
ACTINIDES
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CORROSION RESISTANT ALLOYS
ELEMENTS
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUELS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MARTENSITIC STEELS
MATERIALS
METALS
MOLYBDEN
MOLYBDENUM ADDITIONS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
STAINLESS STEELS
STEEL-CR12MOV
STEELS
TEST REACTORS
TRANSITION ELEMENTS
210500* - Power Reactors
Breeding
360106 - Metals & Alloys- Radiation Effects