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Irradiation performance of LEU fuel particle designs

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5712452
;
None
Research Organization:
Oak Ridge National Laboratory, Oak Ridge, TN 37830
OSTI ID:
5712452
Report Number(s):
CONF-830609-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 44
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
ACTINIDE COMPOUNDS
ACTINIDES
CHALCOGENIDES
COATED FUEL PARTICLES
COUNTING TECHNIQUES
DESIGN
ELEMENTS
ENRICHED URANIUM
FERTILE MATERIALS
FISSILE MATERIALS
FISSIONABLE MATERIALS
FUEL PARTICLES
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
IRRADIATION
ISOTOPE ENRICHED MATERIALS
MATERIALS
MATERIALS TESTING
METALS
NONDESTRUCTIVE TESTING
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
RADIATION ATTENUATION TESTING
RADIOISOTOPE SCANNING
REACTORS
SLIGHTLY ENRICHED URANIUM
TESTING
THORIUM COMPOUNDS
THORIUM OXIDES
URANIUM