Published June 16, 1999 | Version v1
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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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Part of:
Impact of fuel chemistry on fission product behaviour

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)