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Metal Matrix Integrity and Related Technology Development in the Canadian Nuclear Fuel Waste Management Program

Published online by Cambridge University Press:  25 February 2011

P. Mani Mathew  and
Paul A. Krueger
P. Mani Mathew
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, ROE ILO, Canada.
Paul A. Krueger
Affiliation:
Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, ROE ILO, Canada.
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Abstract

One of the concepts under development as a nuclear fuel waste isolation container is a thin-wall corrosion-resistant shell, supported internally by a cast metal matrix in which intact used fuel bundles are invested. The integrity of the metal matrix can be influenced by metallurgical factors and by process parameters. Finite element solidification modelling and laboratory experiments with lead as an investment material have shown the influence of heat transfer parameters on matrix integrity. Controlled cooling of the container walls, for example, can be used to reduce the interaction time between the molten matrix, the fuel sheathing and the container wall, and achieve a void-free matrix. The results of the computer simulations have been used to design an improved casting system, based on controlled wall cooling, for investing nuclear fuel waste containers. Ultrasonic testing of bonds between some candidate container and metal matrix materials, in combination with the metallurgical characterization of the interface region, has allowed differentiation between bonded and unbonded regions. Matrix cracking near bonded interfaces was identified as a potential problem, which could limit the use of the ultrasonic scanning technique for matrix inspection. To produce a high quality interface with good chemical bonding, induction skin melting looks promising and is being further evaluated.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 26: Symposium D – Scientific Basis for Nuclear Waste Management VII , 1983 , 583
Copyright
Copyright © Materials Research Society 1984

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References

REFERENCES

1. Cameron, D.J., “Fuel Isolation Research for the Canadian Nuclear Fuel Waste Management Program”, Atomic Energy of Canada Limited Report, AECL-6834 (1982).Google Scholar
2. Mathew, P.M., Nadeau, J.S., Weinberg, F., Chaklader, A.C.D. and Nuttall, K., Can. Met. Quart. 22, 107 (1983).CrossRefGoogle Scholar
3. Mathew, P.M., Weinberg, F., Nadeau, J.S. and Chaklader, A.C.D., Metals Tech. 9, 375 (1982).Google Scholar
4. Pehlke, R.D. and Bement, A.L. Jr., Trans. Met. Soc. AIME 224, 1237 (1962).Google Scholar
5. McConnell, D.B., “Supply and Cost Factors for Metals in the Canadian Nuclear Fuel Waste Immobilization Program”, Atomic Energy of Canada Limited Report, AECL-6839 (1982).Google Scholar
6. Mathew, P.M., von Massow, R. and Bean, D., “Application of Finite Element Methods in the Process Development of Metal-Matrixed Nuclear Fuel Waste Containers”, Proceedings Fifth International Symposium on Finite Element Methods in Flow Problems, Austin, Texas, 1984 January 23–26.Google Scholar
7. McAdams, W.H., Heat Transmission, 3rd Edition (McGraw-Hill, New York, 1954).Google Scholar
8. Schankula, J.J., “Development of Ultrasonic Immersion Inspection Technique for Spent Fuel Canisters”, Atomic Energy of Canada Limited Report, AECL-7752 (1982).Google Scholar