Published October 30, 1974 | Version v1
Report Restricted

Experiment description and safety analysis for the F-3 mixed-oxide fuel rod irradiation in EBR-II

Creators

Description

The F-3 fuel-rod irradiation experiment in EBR-II is a continuation of the GCFR fast-flux fuel irradiation program. The F-3 experiment will provide a fluence-to-burnup ratio and total fluence (1.5 x 1023 n/cm2 at approximately 100,000 MWd/Te) that is more representative of GCFR fuel-rod operating conditions. Cladding temperatures will be in the range 7000 to 7500C with peak linear power generation rates of 14 to 16.5 kW/ft (46 to 54 W/mm). The mixed-oxide (Pu,U)O2 pellets are contained in ribbed, 20 percent cold-worked 316 stainless-steel cladding. Both solid and annular pellets of 1.94 and 1.98 oxygen-to-metal ratio are used. Activated charcoal traps are contained in all fuel rods to determine the effects of fast-neutron irradiation on the sorption characteristics for fission products of the charcoal. Silicon-carbide temperature monitors and both wire and coated U,Th particle dosimeters are contained in each fuel rod. (U.S.)

Availability note (English)

MF available from INIS under the Report Number.

Files

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Additional details

Additional titles

Augmented title (English)
GCFR

Publishing Information

Imprint Pagination
37 p.
Report number
GA-A--13102

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
6210529
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
EBR-2 REACTOR; FUEL ELEMENTS; GCR TYPE REACTORS; PLUTONIUM DIOXIDE; STAINLESS STEEL-316; TESTING; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; ALLOYS; BREEDER REACTORS; CARBON ADDITIONS; CHALCOGENIDES; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-NICKEL STEELS; CORROSION RESISTANT ALLOYS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HEAT RESISTING ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; LIQUID METAL COOLED REACTORS; MOLYBDENUM ALLOYS; NATURAL URANIUM REACTORS; NICKEL ALLOYS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; STAINLESS STEELS; STEELS; TRANSITION ELEMENT ALLOYS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES