Spent-Fuel Dry-Bath Oxidation Testing
- 1 June 1991
- journal article
- research article
- Published by Taylor & Francis in Nuclear Technology
- Vol. 94 (3) , 383-393
- https://doi.org/10.13182/nt91-a15816
Abstract
Multiple samples of moderate-burnup pressurized water reactor (PWR) and boiling water reactor (BWR) spent fuel are oxidized in controlled atmosphere dry baths at 175, 130, and 110° C. The atmosphere consists of air humidified to a dew point of either—55 or +80°C. These tests are run for up to 18.8 kh. The weight gain data from these tests are analyzed using a mathematical model incorporating the assumption that oxidation occurs by rapid grain-boundary oxygen diffusion, followed by oxidation of the individual fuel grains. The BWR fuel appears to oxidize slightly faster than PWR fuel, and the data suggest a possible increase in oxidation rate in moist air. Reasonable agreement is observed between the oxidation rate constants obtained in these long-term tests and prior short-term thermogravimetric analysis oxidation tests.Keywords
This publication has 14 references indexed in Scilit:
- Formation of uranium trioxide hydrates on UO2 fuel in air-steam mixtures near 200°CJournal of Nuclear Materials, 1989
- Microstructural examination of oxidized spent PWR fuel by transmission electron microscopyJournal of Nuclear Materials, 1989
- Oxidation Behavior of Nonirradiated UO2Nuclear Technology, 1989
- Measurement of the Oxidation of Spent Fuel Between 140 and 225°CNuclear Technology, 1989
- Testing and analyses of the TN-24P PWR spent-fuel dry storage cask loaded with consolidated fuelPublished by Office of Scientific and Technical Information (OSTI) ,1989
- Behavior of Breached Pressurized Water Reactor Spent-Fuel Rods in an Air Atmosphere between 250 and 360°CNuclear Technology, 1986
- Behavior of Breached Light Water Reactor Spent Fuel Rods in Air and Inert Atmospheres at 229°CNuclear Technology, 1985
- Data summary report for the destructive examination of Rods G7, G9, J8, I9, and H6 from Turkey Point Fuel Assembly B17Published by Office of Scientific and Technical Information (OSTI) ,1981
- The oxidation of polycrystalline uranium dioxide in air at room temperatureJournal of Nuclear Materials, 1977
- The kinetics of the oxidation of irradiated uranium dioxide spheres in dry airJournal of Nuclear Materials, 1967