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Nuclear Fuel Performance
Author and Other Information
Emerald Publishing Limited
DOI:
https://doi.org/10.1680/nfp.48977
ISBN print:
978-0-7277-5160-7
Publication date:
1973
Book Chapter

2. Performance of the tubular fuel elements of the French natural uranium, graphite moderated gas-cooled reactors

By
B. Boudouresques;
B. Boudouresques
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H. Ollier;
H. Ollier
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J. Garaud;
J. Garaud
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P. Bournay
P. Bournay
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Author and Other Information
B. Boudouresques
H. Ollier
J. Garaud
P. Bournay
Doi:
https://doi.org/10.1680/nfp.48977.0077
  • Published:
    1973

  • 1. Introduction

  • 2. Behaviour of the Sleeve

  • 3. Can

  • 4. U-Mo 1.1% Elements

  • 5. “Graphite Core” Sicral F1 Elements

  • 6. Can Ruptures

  • 7. Conclusions

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