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/9/1/012008

Additional 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