How Does Temperature Affect the Thermal Conductivity of UO2?

AI Thread Summary
The discussion focuses on calculating the average thermal conductivity of UO2 using a specific integral formula and seeks data on its thermal conductivity as a function of temperature. Participants reference various resources, including the MATPRO library and the FRAPCON 3.4 manual, which provide thermophysical properties of materials used in light-water reactors. Additionally, the melting point of Zircaloy-4 is inquired about, with links to relevant databases and documents provided for further research. Access to the FRAPCON 3.4 code for fuel crack model calculations is also discussed, indicating its availability through the US NRC and Pacific Northwest National Laboratory. The conversation emphasizes the importance of these resources for accurate thermal property analysis in nuclear materials.
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I want to calculate the average thermal conductivity of UO2 by :

1/(To-Tf) * ∫To->Tf dT K(T)

any one can provide me anything about the thermal conductivity of UO2 as function of temperature or any measured data in a range of temperature.
 
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Zircaloy-4 melting point

what is the melting temperature of Zircaloy-4 ?
..
 
Look here for thermophysical properties of LWR fuel and core component materials.

Volume 4: MATPRO- A Library of Materials Properties for Light-Water-Reactor Accident Analysis
http://www.inl.gov/relap5/scdap/smanuals.htm (Vol 4)
Describes the material property library, MATPRO. This library contains material property subroutines available for accident analysis.

Download the pdf (Vol 4).

See also the FRAPCON 3.4 manual for the latest material properties.
http://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr7022/
http://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr7024/

It has some Zircaloy-4 properties as well.

See also -
IAEA TECDOC-1496. Thermophysical properties database of materials for light water reactors and heavy water reactors.
http://www-pub.iaea.org/MTCD/publications/PDF/te_1496_web.pdf

and the older TECDOC-949. Thermophysical properties of materials for water cooled reactors.
http://www-pub.iaea.org/MTCD/publications/PDF/te_949_prn.pdf
 
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Thank you very much that helped a lot. :)
 
tank's Astronuc
it's so useful for me too;
How can access to FRAPCON 3.4 code for calculation fuel crack models?
 
sh_saeed said:
tank's Astronuc
it's so useful for me too;
How can access to FRAPCON 3.4 code for calculation fuel crack models?
As far as I know, the code is available through the US NRC and Pacific Northwest National Laboratory.

Try this - http://frapcon.labworks.org/
 
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