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Room Closure Response to Gas Generation and Mechanical Strength of Different Waste Forms in a Bedded Salt Repository

Published online by Cambridge University Press:  25 February 2011

F. T. Mendenhall  and
C.M. Stone
F. T. Mendenhall
Affiliation:
Sandia National Laboratories, PO Box 5800, Albuquerque, NM 87185.
C.M. Stone
Affiliation:
Sandia National Laboratories, PO Box 5800, Albuquerque, NM 87185.
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Abstract

Finite element calculations of the porosity history of a nuclear waste disposal room for transuranic (TRU) waste in a bedded salt formation have been completed. The analyses include a reduced elastic/secondary creep model for the host halite and a nonlinear consolidation model for the crushed salt backfill. Separate gas generation and constitutive models were used for three distinct hypothetical waste forms: 1) unaltered defense-related, contact-handled transuranic (CH-TRU) waste, 2) shredded and cemented CH-TRU waste, and 3) incinerated and vitrified CH-TRU waste. Histories were determined for a 2000 year time period starting from the emplacement of room seals. The resulting final room porosities varied from roughly 55% to less than 10%, according to waste forms.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 333: Symposium V – Scientific Basis for Nuclear Waste Management XVII , 1993 , 247
Copyright
Copyright © Materials Research Society 1994

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References

REFERENCES

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