Published July 2001 | Version v1
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Thermal diffusivity measurements on oxidised irradiated urania fuel up to 900 deg. C

  • 1. AEA Technology, Windscale, Seascale, Cumbria (United Kingdom)

Description

There is a limited amount of available data on the thermal conductivity of oxidised fuel, and none on oxidised irradiated fuel. In this work oxidised samples of irradiated fuel have been prepared and out-of-pile thermal diffusivity measurements have been performed. The usual way to prepare oxidised samples is to anneal at high temperature in a controlled oxygen potential, typically at temperatures ≥ 200 deg. C in CO/CO2 atmospheres. However, such conditions are not suitable for irradiated UO2 because of the restructuring processes that occur above ∼900 deg. C and which could confound the thermal diffusivity measurement results. Therefore a low temperature anneal in air at 460 deg. C for 5 minutes was used to oxidise fragments of irradiated UO2. The results are be reported and compared with oxidation data from different sources and as these cannot be reconciled solely on stoichiometry variation, it is suggested that the method used to produce oxidised samples may be an important contributor. This could explain the difficulty in reconciling Conductivity Integral to Melt data with low temperature measurements. Plans to perform integral oxidation and thermal diffusivity measurements to investigate this phenomenon are being considered. (author)

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Nuclear fuel behaviour modelling at high burnup and its experimental support. Proceedings of a technical committee meeting

Additional details

Publishing Information

Imprint Title
Nuclear fuel behaviour modelling at high burnup and its experimental support. Proceedings of a technical committee meeting
Imprint Pagination
451 p.
Journal Page Range
p. 31-42
ISSN
1011-4289
Report number
IAEA-TECDOC--1233

Conference

Title
Technical committee meeting on nuclear fuel behaviour modelling at high burnup and its experimental support
Dates
19-23 Jun 2000
Place
Windermere (United Kingdom)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
32044054
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BURNUP; EXPERIMENTAL DATA; MELTING; NUCLEAR FUELS; OXIDATION; OXYGEN POTENTIAL; STOICHIOMETRY; TEMPERATURE DEPENDENCE; THERMAL CONDUCTIVITY; THERMAL DIFFUSIVITY; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; CHALCOGENIDES; CHEMICAL REACTIONS; DATA; ENERGY; ENERGY SOURCES; FREE ENTHALPY; FUELS; INFORMATION; MATERIALS; NUMERICAL DATA; OXIDES; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; REACTOR MATERIALS; THERMODYNAMIC PROPERTIES; URANIUM COMPOUNDS; URANIUM OXIDES

Optional Information

Notes
16 refs, 8 figs