How Does Temperature Affect the Thermal Conductivity of UO2?

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SUMMARY

The discussion focuses on calculating the average thermal conductivity of UO2 as a function of temperature using the formula 1/(To-Tf) * ∫To->Tf dT K(T). Participants shared resources for thermal conductivity data, including the MATPRO library, which provides material property subroutines for light-water-reactor accident analysis. Additionally, references to the FRAPCON 3.4 manual and IAEA TECDOC publications were provided for further material properties, including Zircaloy-4. The melting point of Zircaloy-4 was also queried, emphasizing its relevance in the context of UO2 thermal properties.

PREREQUISITES
  • Understanding of thermal conductivity and its calculation methods
  • Familiarity with UO2 and its applications in nuclear reactors
  • Knowledge of the MATPRO material property library
  • Access to FRAPCON 3.4 for fuel crack modeling
NEXT STEPS
  • Research the MATPRO library for detailed thermal properties of UO2
  • Study the FRAPCON 3.4 manual for fuel crack modeling techniques
  • Explore IAEA TECDOC-1496 for thermophysical properties of reactor materials
  • Investigate the melting point and properties of Zircaloy-4 in reactor applications
USEFUL FOR

Nuclear engineers, materials scientists, and researchers involved in reactor safety and thermal analysis will benefit from this discussion.

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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
 
Last edited:
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/
 
Last edited:

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