Thermal Diffusivity Of Homogeneous SBR MOX Fuel With A Burn-up of 35 MWd/kgHM

Conference · Sun Jul 01 00:00:00 EDT 2007

OSTI ID:21229290

Staicu, D; Pagliosa, G; Papaioannou, D; Rondinella, V V; Cozzo, C; Konings, R; Walker, C T ^[1]; Barker, M ^[2]; Weston, R ^[3]

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1. European Commission, Joint Research Centre, Institute for Transuranium Element, P.O. Box 2340, D-76125 Karlsruhe (Germany)
2. Nexia Solutions, Sellafield, Seascale, Cumbria, CA20 1PG (United Kingdom)
3. British Nuclear Group Sellafield Ltd, Sellafield, Seascale, Cumbria, CA20 1PG (United Kingdom)

New thermal diffusivity results obtained on SBR MOX fuel with a pellet burn-up of 35 MWd/kgHM are reported. The thermal diffusivity measurements were carried out at three radial positions using a shielded 'laser-flash' device and show that the thermal diffusivity increases from the pellet periphery to the centre. Comparison shows that the thermal conductivity is in the same range than of UO{sub 2} of similar burn-up. The annealing behaviour was characterized in order to identify the degradation due to the out-of pile auto-irradiation. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21229290
• Resource Relation: Conference: 2007 LWR Fuel Performance Meeting / TopFuel 2007, San Francisco, CA (United States), 30 Sep - 3 Oct 2007; Other Information: Country of input: France; 12 refs; Related Information: In: Proceedings of the 2007 LWR Fuel Performance Meeting / TopFuel 2007 'Zero by 2010', 683 pages.
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ANNEALING
BURNUP
IRRADIATION
MIXED OXIDE FUELS
PELLETS
THERMAL CONDUCTIVITY
THERMAL DIFFUSIVITY
URANIUM DIOXIDE