Hostname: page-component-586b7cd67f-gb8f7 Total loading time: 0 Render date: 2024-11-25T18:04:47.350Z Has data issue: false hasContentIssue false

Source-Term Comparison Using the Arest and Syvac-Vault Models: Effects of Decay-Chain In-Growth and Precipitation

Published online by Cambridge University Press:  26 February 2011

M. J. Apted
Affiliation:
Pacific Northwest Laboratory, Richland, Washington, U. S. A.99352
D. W. Engel
Affiliation:
Pacific Northwest Laboratory, Richland, Washington, U. S. A.99352
N. C. Garisto
Affiliation:
Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, CanadaROE 1 LO.
D. M. Leneveu
Affiliation:
Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, CanadaROE 1 LO.
Get access

Abstract

A series of calculations of radionuclide release was performed with the AREST and SYVAC-Vault models (SVM) in order to assess concurrance. Specifically, the effects of precipitation and decay chain in-growth on the predicted release of nuclides from waste packages containing spent nuclear fuel were compared between each code. The results for maximum release rates generally agreed within a factor of 10. The differences in results can be explained based on the differences in geometry and boundary conditions between the two codes. Both codes showed nearly identical enhancement factors in release rates of uranium-series nuclides (U-238, U-234, Th-230, Ra-226) arising from the effect of decay-chain in-growth. Calculated enhancement factors in release rates for precipitation of a new uranium-bearing solid within the waste package were also in good agreement between AREST and SVM.

Type
Research Article
Copyright
Copyright © Materials Research Society 1989

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

1. Cole, C., PNL-6087 (Pacific Northwest Laboratory, Richland, Washington, 1986).Google Scholar
2. Grundfelt, B., in The HYDROCOIN Proiect-Overview and Results from Level One. Proceedings of GEOVAL-87, (Swedish Nuclear Power Inspectorate, Stockholm, Sweden, 1987).Google Scholar
3. Engel, D. W., Apted, M. J., Garisto, N. C. and LeNeveu, D. M., PNL-SA-15713 (Pacific Northwest Laboratory, Richland, Washington, 1988).Google Scholar
4. LeNeveu, D. M., AECL-8383 (Atomic Energy of Canada, Ltd., Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, Canada, 1986).Google Scholar
5. Liebetrau, A. M., Apted, M. J., Engel, D. W., Altenhofen, M. K., Reid, C. R., Strachan, D. M., Erikson, R. L., and Alexander, D. M., in Waste Management '87, edited by Post, R.G. (University of Arizona, Tucson, Arizona, 1987) pp. 535544.Google Scholar
6. LeNeveu, D. M., Ann. Nucl. Energy 14, 77 (1987).Google Scholar
7. Chambre, P. L., Pigford, T. H., Lee, W. W. -L., Ahn, J., Kajiwara, S., Kim, C. L., Kimura, H., Lung, H., Williams, W. J., and Zavoshy, S. J., LBL-19430 (Lawerence Berkeley Laboratory, Berkeley, California, 1985).Google Scholar
8. Apted, M. J., Liebetrau, A.M. and Engel, D. W., in Waste Management '87, edited by Post, R.G. (University of Arizona, Tucson, Arizona, 1987) pp. 545554.Google Scholar
9. Johnson, L. H., Garisto, N. C. and Stroes-Gascoyne, S., in Waste Management '85. edited by Post, R.G. (University of Arizona, Tucson, Arizona, 1985) pp. 479482.Google Scholar
10. Garisto, N. C. and Garisto, F., Ann. Nucl. Energy 13, 591 (1986).Google Scholar
11. Garisto, N. C. and Garisto, F., AECL-9562 (Atomic Energy of Canada, Ltd., Whiteshell Nuclear Research Establishment, Pinawa, Manitoba, Canada, 1988).Google Scholar
12. Apted, M. J. and Engel, D. W., in Scientific Basis for Nuclear Waste Management XL. edited by Apted, M. J. and Westerman, R. E. (Mater. Res. Soc. Proc. 112, Pittsburgh, PA, 1987) pp. 303312.Google Scholar