Thermal properties of high burnup UO2 fuel rods
Description
The report reviews the existing Halden database on high burnup UO2 with respect to fuel thermal conductivity degradation. New irradiation data have been accumulated since a correlation for conductivity degradation was proposed in 1996. These new data include fuel rods pre-irradiated in commercial light water reactors to a burnup of around 60 MWd/kgUO2 (IFA-597.2, IFA-597.3, IFA-610.1) as well as HBWR base irradiated and re instrumented fuel rods (IFA-533.2). In addition, two earlier irradiations reaching intermediate burnups are re-analysed (IFA-432, IFA-552.1). Measured temperature data from these experiments are analysed using the temperature calculation code in use at the Halden project. Using best estimate fuel rod dimensional data, the effect of burnup accumulation on fuel thermal conductivity is estimated. For each of the irradiations, a fit to measured data is sought by adjusting the parameters in the correlation for fuel thermal conductivity degradation. From the cases considered, the degradation parameter of the earlier correlation for thermal conductivity derived from IFA-562 appears to be a lower bound value within the Halden database. With respect to thermal properties, the analysed data seem to converge to a degradation parameter value a=16 (instead of the earlier a=14). An update of the Halden recommendation for the correlation of fuel thermal conductivity degradation with burnup is therefore proposed (author) (ml)
Availability note (English)
Available from IFE, PO Box 173, 1751 Halden NorwayAdditional details
Publishing Information
- Imprint Pagination
- 44 p.
- Report number
- HWR--599
INIS
- Country of Publication
- Norway
- Country of Input or Organization
- Norway
- INIS RN
- 38082992
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Non-conventional Literature, Numerical Data
- Descriptors DEI
- BURNUP; EXPERIMENTAL DATA; FUEL RODS; HBWR REACTOR; IRRADIATION; THERMAL CONDUCTIVITY; THERMAL DEGRADATION; THERMAL TESTING; THERMODYNAMIC PROPERTIES; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; BHWR TYPE REACTORS; CHALCOGENIDES; DATA; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL ELEMENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; MATERIALS TESTING; NONDESTRUCTIVE TESTING; NUMERICAL DATA; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TESTING; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 30 refs., 28 figs., 8 tabs