Published October 2015
| Version v1
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Evaluation of thermal conductivity of multi-component and multi-phase nuclear fuels by the finite element method
Description
The effects of the shape and distribution state of voids on the thermal conductivity of UO2, and the temperature distribution and heat flow within the irradiated MOX fuel were evaluated by finite element analysis. Although the work is still in progress, some preliminary results are presented. (author)
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Additional details
Publishing Information
- Imprint Title
- State-of-the-Art Report on Multi-scale Modelling of Nuclear Fuels
- Imprint Pagination
- 380 p.
- Journal Page Range
- p. 346-353
- Report number
- NEA-NSC-R--2015-5
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 47032429
- Subject category
- S36: MATERIALS SCIENCE; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Descriptors DEI
- COMPUTERIZED SIMULATION; FINITE ELEMENT METHOD; FUEL PELLETS; HEAT FLUX; MIXED OXIDE FUELS; POROSITY; TEMPERATURE DEPENDENCE; TEMPERATURE DISTRIBUTION; THERMAL CONDUCTIVITY; URANIUM DIOXIDE; VOIDS
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; ENERGY SOURCES; FUELS; MATERIALS; MATHEMATICAL SOLUTIONS; NUCLEAR FUELS; NUMERICAL SOLUTION; OXIDES; OXYGEN COMPOUNDS; PELLETS; PHYSICAL PROPERTIES; REACTOR MATERIALS; SIMULATION; SOLID FUELS; THERMODYNAMIC PROPERTIES; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 8 refs. Imprint:1158 refs.