Published March 2010
| Version v1
Journal article
Recovery behaviours of thermal conductivities in self-irradiated MOX fuel
- 1. Nuclear Fuel Cycle Engineering Laboratories, Japan Atomic Energy Agency, 4-33, Muramatsu, Tokai-mura, Naka-gun, Ibaraki, 319-1194 JAPAN (Japan)
- 2. Inspection Development Company Ltd., 4-33, Muramatsu, Tokai-mura, Naka-gun, Ibaraki 319-1194 (Japan)
Description
The thermal conductivities of MOX fuel pellets stored for about 15 years and their recovery behaviours by pre-heating were investigated in two types of experiments. The experimental thermal conductivities approached the analytical curve derived from the thermal conductivities of non-self-irradiated specimens with an increase of pre-heating temperature. The experimental results were analyzed by the modified classical phonon transport model. The recovery processes between the thermal conductivities in this study and the lattice parameters of UO2 and PuO2 were compared. It was found that both recovery processes were similar to each other.
Availability note (English)
Available from http://dx.doi.org/10.1088/1757-899X/9/1/012008Additional details
Identifiers
Publishing Information
- Journal Title
- IOP Conference Series. Materials Science and Engineering (Online)
- Journal Volume
- 9
- Journal Issue
- 1
- Journal Page Range
- [8 p.]
- ISSN
- 1757-899X
Conference
- Title
- 8. international conference on actinide science
- Acronym
- Actinides 2009
- Dates
- 12-17 Jul 2009
- Place
- San Francisco, CA (United States)
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43018887
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- LATTICE PARAMETERS; MIXED OXIDE FUELS; PELLETS; PHONONS; PLUTONIUM OXIDES; THERMAL CONDUCTIVITY; TRANSPORT THEORY; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHALCOGENIDES; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; PLUTONIUM COMPOUNDS; QUASI PARTICLES; REACTOR MATERIALS; SOLID FUELS; THERMODYNAMIC PROPERTIES; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES