FISSION-GAS-RELEASE FROM UO$sub 2$, INTERIM REPORT NO. 1

Technical Report · Tue Aug 16 04:00:00 EDT 1960

DOI:https://doi.org/10.2172/4068895· OSTI ID:4068895

Morgan, J G; Morgan, M T; Osborne, M F

The evolution of fission products from UO/sub 2/ during irradiation at high temperatures is of primary interest to the Gas-cooled Reactor Project. Fuel tests consisting of UO/sub 2/ pellets encapsulated in Inconel or stainless steel were irradiated in the LITR, ORR, and ETR. The capsules were pierced in hot cells, and the gases collected in evacuated systems. Fractions of this gas, of suitable activity for counting, were taken and then analyzed by gamma spectrometry. Larger fractions of gas were analyzed by mass spectrometry. Percentage of gas release varied widely, increasing with temperature, impurity content, oxygen-to-uranium ratio of the UO/sub 2/, and decreasing with bulk density. For high density, stoichiometric UO/sub 2/, the gas release was generally less than 3% up to a temperature of about 2800 deg F, about which it was greatly accelerated. Fuel burn-ups of up to 22,000 Mwd/MT were obtained. Maximum measured central fuel temperatures of 3150 deg F were reached. The lower- density nonstoichiometric UO/sub 2/ released greater amounts of fission gas, particularly Kr/sup 85/. (auth)

• Research Organization: Oak Ridge National Lab., Tenn. (US)
• Sponsoring Organization: US Atomic Energy Commission (AEC)
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-15-013426
• OSTI ID: 4068895
• Report Number(s): CF-60-7-11
• Country of Publication: United States
• Language: English

Related Subjects

BURNUP
CHROMIUM ALLOYS
DENSITY
DISTRIBUTION
FISSION PRODUCTS
FUEL CANS
FUEL ELEMENTS
GAMMA SPECTROMETERS
GAS COOLANT
GASES
HIGH TEMPERATURE
IMPURITIES
IRRADIATION
KRYPTON 85
LOSSES
MASS SPECTROMETERS
METALS, CERAMICS, AND OTHER MATERIALS
NICKEL ALLOYS
OXYGEN
PELLETS
QUANTITY RATIO
REACTORS
REMOTE HANDLING
SAMPLING
STAINLESS STEELS
TEMPERATURE
TESTING
URANIUM
URANIUM DIOXIDE
VACUUM