Thermal conductivity of UO2

In summary, the conversation discusses the calculation of the average thermal conductivity of UO2 and the melting temperature of Zircaloy-4. The participants also share resources for accessing material properties data and the FRAPCON 3.4 code for calculating fuel crack models. The conversation references several manuals and databases, including MATPRO and IAEA TECDOC-1496 and TECDOC-949.
  • #1
Nucengable
42
0
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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  • #2
Zircaloy-4 melting point

what is the melting temperature of Zircaloy-4 ?
..
 
  • #3
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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  • #4
Thank you very much that helped a lot. :)
 
  • #5
tank's Astronuc
it's so useful for me too;
How can access to FRAPCON 3.4 code for calculation fuel crack models?
 
  • #6
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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1. What is thermal conductivity?

Thermal conductivity is the measure of a material's ability to transfer heat. It is typically measured in watts per meter-kelvin (W/mK) and is influenced by factors such as temperature, density, and composition.

2. How is the thermal conductivity of UO2 determined?

The thermal conductivity of UO2 is typically determined through experiments that measure the rate of heat flow through a sample of the material. This data is then used to calculate the thermal conductivity value using specific equations and models.

3. What factors affect the thermal conductivity of UO2?

The thermal conductivity of UO2 is affected by several factors including temperature, density, porosity, microstructure, and impurities. These factors can influence the movement of heat through the material and therefore impact its overall thermal conductivity.

4. How does the thermal conductivity of UO2 compare to other materials?

The thermal conductivity of UO2 is relatively low compared to other materials, such as metals. This is due to its ceramic nature and the presence of voids and impurities in the material. However, UO2 is still considered a good thermal insulator and is commonly used in nuclear fuel rods.

5. Can the thermal conductivity of UO2 be altered?

Yes, the thermal conductivity of UO2 can be altered through various methods such as changing the material's composition, microstructure, and grain size. These alterations can be made during the manufacturing process to tailor the material's thermal conductivity for specific applications.

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