On the thermal evolution of Pu-rich agglomerates in MOX
Description
From the experience accumulated so far on irradiated MOX fuel, its overall behaviour under irradiation is generally well predicted by existing fuel models. It appears however that additional data are still welcome to properly benchmark fission gas release models, mainly at elevated burnup. To this aim, an international research project, FIGARO, was initiated. Its goal was to provide thermal and fission gas release data og MOX at high burnup. Two MOX fuel rods irradiated to high burnup (50 GWd/tM peak pellet) but at lower power (less than 200 W/cm) were selected for segmentation and instrumentation with central thermocouple and pressure gauge. The instrumented segments were subjected to irradiations at variable linear power in the HALDEN MTR. Both temperature and internal pressure were online monitored during the ramp test. Afterwards, the rod segments were transported and extensively investigated. The paper focuses on the investigation of the evolution of the microstructure of Pu-rich agglomerates as a function of temperature
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Additional details
Publishing Information
- Imprint Title
- Impact of fuel chemistry on fission product behaviour
- Imprint Pagination
- 78 p.
- Journal Page Range
- p. 75-77
- Report number
- BLG--813
Conference
- Title
- Workshop on the impact of fuel chemistry on fission product behaviour
- Dates
- 16-17 Jun 1999
- Place
- Mol (Belgium)
INIS
- Country of Publication
- Belgium
- Country of Input or Organization
- Belgium
- INIS RN
- 39117941
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; FISSION PRODUCTS; MIXED OXIDE FUELS; NUCLEAR CHEMISTRY; PHYSICAL CHEMISTRY; RADIATION CHEMISTRY; SPENT FUEL ELEMENTS
- Descriptors DEC
- CHEMISTRY; ENERGY SOURCES; FUEL ELEMENTS; FUELS; ISOTOPES; MATERIALS; NUCLEAR FUELS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTOR MATERIALS; SOLID FUELS
Optional Information
- Notes
- Imprint:This report consists of the papers presented at the Topical Day on Site Remediation held at the Belgian Nuclear Research Centre SCK-CEN (Mol, Belgium, 18 September 1996)