Irradiation behavior of the CNEA's experimental uranium silicide dispersion fuel plates

Conference · Fri Jan 01 00:00:00 EST 1988

OSTI ID:5412094

Hofman, G L; Marajofsky, A; Kohut, C ^[1]

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1. Argonne National Lab., IL (USA)

Since 1978 the CNEA ECBE project has been involved in the development of dispersion fuel plates with four types of fuel materials -- UAl{sub x}, U{sub 3}O{sub 8}, U{sub 3}Si, and U{sub 3}Si{sub 2} -- to be used in low enriched (LEU < 20% {sup 235}U) fuel elements for research reactors. Miniplates with these fuel materials were manufactured at CNEA and were irradiated in the ORR in three series of irradiations as part of the RERTR miniplate irradiation program. The first irradiation contained U{sub 3}O{sub 8} and UAl{sub x} fuel, the second U{sub 3}O{sub 8}, UAl{sub x} and U{sub 3}Si, while the third irradiation test consisted of six U{sub 3}Si{sub 2} miniplates and one U{sub 3}Si miniplate. This third test is the subject of this paper. The present results compare favorably with other irradiations performed in the RERTR program{sup 1,2} showing in particular the excellent behavior of the U{sub 3}Si{sub 2}. The overall data accumulated support the qualification of the CNEA fabrication techniques. 5 refs., 13 figs., 3 tabs.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5412094
• Report Number(s): CONF-8809221-7; ON: DE90003800; TRN: 90-001109
• Resource Relation: Conference: International meeting on reduced enrichment for research and test reactors (RERTR), San Diego, CA (USA), 18-24 Sep 1988
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
42 ENGINEERING
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ORR REACTOR
IRRADIATION
ALUMINIUM ALLOYS
BLISTERS
BUBBLES
BURNUP
CLADDING
DATA ACQUISITION
FUEL ELEMENTS
MATERIALS TESTING
MEASURING METHODS
METALLOGRAPHY
PERFORMANCE TESTING
PLANNING
PLATES
POROSITY
POST-IRRADIATION EXAMINATION
RECOMMENDATIONS
SPECTROSCOPY
SWELLING
TEMPERATURE EFFECTS
URANIUM ALLOYS
URANIUM COMPOUNDS
ACTINIDE ALLOYS
ACTINIDE COMPOUNDS
ALLOYS
DEPOSITION
ENRICHED URANIUM REACTORS
REACTOR COMPONENTS
REACTORS
SURFACE COATING
TANK TYPE REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test &amp; Experimental Reactors
420500 - Engineering- Materials Testing
050700 - Nuclear Fuels- Fuels Production &amp; Properties