Characterization of fuel swelling in helium-bonded carbide fuel pins
Technical Report
·
OSTI ID:6441326
This work is not only the first attempt at characterizing the swelling of (U,Pu)C fuel pellets, but it also represents the only detailed examinations on carbide fuel swelling at high fuel burnups (4 to 16 at. %). This characterization includes the contributions of fission gases, cracks and solid fission products to fuel swelling. Significantly, the contributions of fission gases and cracks were determined by using the image analysis technique (IAT) which allows researchers to take areal measurements of the irradiated fuel porosity and cracks from the photographs of metallographic fuel samples. However, because areal measurements for varying depths in the fuel pellet could not be obtained, the crack areal measurements could not be converted into volumetric quantities. Consequently, in this situation, an areal fuel swelling analysis was used. The macroscopic fission-gas induced fuel swelling (MAS) caused by fission-gas bubbles and pores > 1 m was determined using the measured irradiated fuel porosity because the measuring range of IAT is limited to bubbles and pores >1 m. Conversely, for fuel swelling induced by fission-gas bubbles < 1 m, the microscopic fission-gas induced fuel swelling (MIS) was estimated using an areal fuel swelling model.
- Research Organization:
- Los Alamos National Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 6441326
- Report Number(s):
- LA-11051-T; ON: DE87012983
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis of void volume distribution of oxide fuel pins with high linear rod power
The sodium-bonding pin concept for advanced fuels concept for advanced fuels part 1: swelling of carbide fuel up to 12% burnup
SWELLING IN ALPHA URANIUM DUE TO IRRADIATION
Technical Report
·
Fri Aug 10 00:00:00 EDT 1973
·
OSTI ID:4938202
The sodium-bonding pin concept for advanced fuels concept for advanced fuels part 1: swelling of carbide fuel up to 12% burnup
Journal Article
·
Wed Nov 30 23:00:00 EST 1983
· Nucl. Technol.; (United States)
·
OSTI ID:6474964
SWELLING IN ALPHA URANIUM DUE TO IRRADIATION
Journal Article
·
Sat Jul 01 00:00:00 EDT 1961
· J. Nuclear Materials
·
OSTI ID:4837331
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360203 -- Ceramics
Cermets
& Refractories-- Mechanical Properties
360206 -- Ceramics
Cermets
& Refractories-- Radiation Effects
ACTINIDE COMPOUNDS
BREEDER REACTORS
CARBIDES
CARBON COMPOUNDS
CRACKS
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCTS
FUEL ELEMENTS
FUEL PINS
FUELS
IRRADIATION
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
NUCLEAR FUELS
PHYSICAL RADIATION EFFECTS
PLUTONIUM CARBIDES
PLUTONIUM COMPOUNDS
RADIATION EFFECTS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
SWELLING
TRANSURANIUM COMPOUNDS
URANIUM CARBIDES
URANIUM COMPOUNDS
210500* -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360203 -- Ceramics
Cermets
& Refractories-- Mechanical Properties
360206 -- Ceramics
Cermets
& Refractories-- Radiation Effects
ACTINIDE COMPOUNDS
BREEDER REACTORS
CARBIDES
CARBON COMPOUNDS
CRACKS
ENERGY SOURCES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCTS
FUEL ELEMENTS
FUEL PINS
FUELS
IRRADIATION
ISOTOPES
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
NUCLEAR FUELS
PHYSICAL RADIATION EFFECTS
PLUTONIUM CARBIDES
PLUTONIUM COMPOUNDS
RADIATION EFFECTS
RADIOACTIVE MATERIALS
REACTOR COMPONENTS
REACTOR MATERIALS
REACTORS
SWELLING
TRANSURANIUM COMPOUNDS
URANIUM CARBIDES
URANIUM COMPOUNDS