Irradiation test OF-2: high-temperature irradiation behavior of LASL-made fuel rods and LASL-made coated particles. [ZrC coated particles]
Three LASL-made, substoichiometric ZrC-coated particles with inert kernels, and two high-density molded graphite fuel rods that contained LASL-made, ZrC-coated fissile particles were irradiated in the Oak Ridge Research Reactor test OF-2. The severest test conditions were 8.36 x 10/sup 21/ nvt (E greater than 0.18 MeV) at 1350/sup 0/C. The graphite matrix showed no effect of the irradiation. There was no interaction between the matrix and any of the particle coats. The loose ZrC coated particles with inert kernels showed no irradiation effects. The graded ZrC-C coats on the fissile particles were cracked. It is postulated that the cracking is associated with the low LTI deposition rate and is not related to the ZrC.
- Research Organization:
- Los Alamos Scientific Lab., N.Mex. (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 5444080
- Report Number(s):
- LA-6988-MS
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
CARBIDES
CARBON
CARBON COMPOUNDS
COATED FUEL PARTICLES
ELEMENTS
FUEL ELEMENTS
FUEL PARTICLES
FUEL RODS
GAS COOLED REACTORS
GRAPHITE
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
NONMETALS
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
TESTING
TRANSITION ELEMENT COMPOUNDS
VERY HIGH TEMPERATURE
ZIRCONIUM CARBIDES
ZIRCONIUM COMPOUNDS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
CARBIDES
CARBON
CARBON COMPOUNDS
COATED FUEL PARTICLES
ELEMENTS
FUEL ELEMENTS
FUEL PARTICLES
FUEL RODS
GAS COOLED REACTORS
GRAPHITE
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
NONMETALS
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
TESTING
TRANSITION ELEMENT COMPOUNDS
VERY HIGH TEMPERATURE
ZIRCONIUM CARBIDES
ZIRCONIUM COMPOUNDS