Finding UO2 Enrichment Value for MCNP5 Input File

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Discussion Overview

The discussion revolves around finding the density value for uranium dioxide (UO2) enriched to 3.25% - 3.6% for use in an MCNP5 input file. Participants explore various sources and provide insights into the theoretical and practical densities of UO2, as well as references to technical documents.

Discussion Character

  • Technical explanation, Debate/contested, Meta-discussion

Main Points Raised

  • One participant expresses difficulty in finding a specific density value for UO2 enriched to 3.25% - 3.6%.
  • Another participant provides a range for the theoretical density of UO2, noting that practical densities are often lower due to porosity, typically around 95% of theoretical density.
  • Some participants suggest that reliable sources such as textbooks or technical documents should be consulted instead of Wikipedia for accurate data.
  • Links to various IAEA technical documents are shared as potential resources for obtaining density information and other properties of UO2.
  • There is a mention of the variability in UO2 density depending on reactor and cycle/core design.

Areas of Agreement / Disagreement

Participants do not reach a consensus on a specific density value for the enriched UO2, and there are differing opinions on the reliability of Wikipedia as a source. Multiple viewpoints regarding the appropriate sources for density information are presented.

Contextual Notes

Participants note that the density of UO2 can vary based on factors such as porosity and the specific reactor design, and that the information may depend on the definitions used in different contexts.

AlbeFerS
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Hi there,

I´m just finishing an input file for MCNP5 and I can´t find a value of density for UO2 enriched to 3,25% - 3,6%.

Does anyone know it or know where I can find it?

Thanks in advance!

(P.D.: wikipedia is not my friend... )
 
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The theoretical density (TD, 100% dense, or no porosity) of UO2 is approximately 10.96 to 10.98 g/cm3, or 10960 to 10980 kg/m3. In practice, there is always some porosity in a polycrystalline pellet. For a few decades, in LWR fuel, we have used about 95% dense UO2 (10410 kg/m3), but some fuel is made with densities > 95%, and often in the range of 96 to 97% TD (10520 to 10630 kg/m3), and in some cases in might go up to close to 98% TD. It depends on the reactor and cycle/core design.
 
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SteamKing said:
Not even

http://en.wikipedia.org/wiki/Uranium_dioxide

He seems pretty friendly.
Thanks.
I meant that I had seen it and that I don´t trust wikipedia anymore (for this kind of data, even though this time is approximately right)
 
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AlbeFerS said:
Thanks.
I meant that I had seen it and that I don´t trust wikipedia anymore (for this kind of data, even though this time is approximately right)
If one is doing work or school work, one should go to a textbook or other reliable source.

For nuclear fuel properties, one can use MATPRO.

I'll post some links to some technical documents once the websites are up.

The IAEA and INL have changed their websites, so old link may not be viable anymore.

IAEA Technical Documents (TECDOCs) are available here:
http://www-pub.iaea.org/books/IAEABooks/Series/34/Technical-Documents

See -
http://www-pub.iaea.org/books/IAEAB...and-Fuel-Rod-Design-for-Water-Cooled-Reactors

Specifically - http://www-pub.iaea.org/books/IAEAB...Light-Water-Reactors-and-Heavy-Water-Reactors
Section 6.1.1.10 Density of Solid UO2
 
Last edited:
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I´ll check it out.

Thank you again.
 

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