Published March 1984
| Version v1
Report
Behavior in air at 175 to 2500C of UO2 fuel fragments extracted from irradiated elements
Creators
- 1. Ontario Hydro, Toronto
- 2. Atomic Energy of Canada Ltd., Chalk River, Ontario
Description
UO2 fuel fragments extracted from intact and defected irradiated CANDU elements were heated in air. The temperature range was 175 to 2500C for times in excess of 1200 h. Maximum pre-test burnups and linear powers were 190 MW.h/kg U (8000 MW.d/TeU) and 45 kW/m, respectively. Rates of weight gain varied from about 10-4 wt %/h to 2 x 10-2 wt %/h at 175 and 2500C respectively. All data are described by a process with an activation energy of about 130 kJ/mol. Irradiation and fragment size had significant effects on the rate of weight increase. The results have application to the station handling, transport and dry storage of irradiated nuclear fuel in the temperature range to 2500C. 6 references, 7 figures, 2 tables
Additional details
Publishing Information
- Imprint Title
- Workshop on spent fuel/cladding reaction during dry storage
- Journal Page Range
- p. B1-B6.
- Report number
- NUREG/CP--0049
Conference
- Title
- NRC workshop on spent fuel/cladding reactions during dry storage.
- Dates
- 17 Sep - 18 Aug 1983.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16002580
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- DEFECTS; DRY STORAGE; EXPERIMENTAL DATA; HIGH TEMPERATURE; OXIDATION; POST-IRRADIATION EXAMINATION; SPENT FUEL ELEMENTS; TEMPERATURE DEPENDENCE; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; DATA; FUEL ELEMENTS; INFORMATION; NUMERICAL DATA; OXIDES; OXYGEN COMPOUNDS; REACTOR COMPONENTS; STORAGE; URANIUM COMPOUNDS; URANIUM OXIDES