IN-PILE FISSION-GAS-RELEASE BEHAVIOR OF ALUMINA-COATED UO$sub 2$ PARTICLES IRRADIATED TO HIGH BURNUP
Technical Report
·
OSTI ID:4832208
coated-graphite fuel elements were irradiated at temperatures up to about 1350 deg F to a total uranium burnup of about 6 at.%. The fission-gas- release behavior of one of these materials, 100 to 140- mu -diameter UO/sub 2/ particles coated with 40 mu of vapor-deposited Al/sub 2/O/sub 3/, was studied in detail. The fission gas released by this material was brought by a flowing stream of helium from the specimen to a point where it was sampled intermittently so that the amount released could be determined. Stainless steel mesh traps were placed close to the capsule from time to time to trap the solid decay products of the short-lived fission gases. good at low burnup when the particle coatings were intact. Deterioration was first noted at 1 at.% burnup, and became relatiyely severe at between 3 and 5 at.% burnup. Cracking of particle coatings was the cause of deterioration. Fission-gas release inltially was approximately 10/sup - 7/ and at about 6 at.% burnup was 10/sub -2/ for the long-lived fission gases and below 10/sup -4/ for most of the shorter lived ones. (auth)
- Research Organization:
- Battelle Memorial Inst., Columbus, Ohio
- DOE Contract Number:
- W-7405-ENG-92
- NSA Number:
- NSA-16-003520
- OSTI ID:
- 4832208
- Report Number(s):
- BMI-1552
- Country of Publication:
- United States
- Language:
- English
Similar Records
EVALUATION OF IRRADIATED ALUMINA-COATED UO$sub 2$ PARTICLES DISPERSED IN GRAPHITE SPHERES
ALUMINA COATING OF UO$sup 2$ SHOT BY HYDROLYSIS OF ALUMINUM CHLORIDE VAPOR
Short Communication: Observation of Initial Burst Release of Fission Gas from High-Burnup UO2 Nuclear Fuel During Thermal Transient
Technical Report
·
Wed Mar 21 23:00:00 EST 1962
·
OSTI ID:4796483
ALUMINA COATING OF UO$sup 2$ SHOT BY HYDROLYSIS OF ALUMINUM CHLORIDE VAPOR
Technical Report
·
Tue Oct 25 00:00:00 EDT 1960
·
OSTI ID:4121300
Short Communication: Observation of Initial Burst Release of Fission Gas from High-Burnup UO2 Nuclear Fuel During Thermal Transient
Journal Article
·
Wed Jun 14 20:00:00 EDT 2023
· Journal of Nuclear Materials
·
OSTI ID:1986224