journal article·1992-06

Thermal conductivity of (U, Pu)O2−x mixed oxide fuel

Y. Philipponneau

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Abstract

No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.

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Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Radioactive element chemistry and processing

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References (15)

Show source-provided references
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