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Long-Term In-Package Spent Fuel Criticality Calculations

[+] Author Affiliations
Olivier Wantz

Université Libre de Bruxelles, Brussels, Belgium

Olivier Smidts

Association Vinçotte Nuclear, Brussels, Belgium

Alain Dubus, R. Beauwens

Service de Metrologie Nucleaire, Brussels, Belgium

Paper No. ICEM2003-4575, pp. 1625-1630; 6 pages
doi:10.1115/ICEM2003-4575
From:
  • ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation
  • 9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3
  • Oxford, England, September 21–25, 2003
  • Conference Sponsors: Nuclear Engineering Division and Environmental Engineering Division
  • ISBN: 0-7918-3732-7 | eISBN: 0-7918-3731-9
  • Copyright © 2003 by ASME

abstract

This paper presents MCNP criticality calculations for both UOX and MOX disrupted fuel assemblies canisters systems in the reference Belgian disposal concept and one of its variant. We examine the influence of different parameters (water moderation and geometry alteration) on the neutron multiplication factor, keff . In all the studied cases, the reference concept does not present criticality risks. The variant concept sometimes presents criticality risks. The present results only concern fresh UOX and MOX fuel assemblies. Further developments of this work will include irradiated (UOX and MOX) fuels.

Copyright © 2003 by ASME

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