Hostname: page-component-745bb68f8f-mzp66 Total loading time: 0 Render date: 2025-02-04T16:03:59.816Z Has data issue: false hasContentIssue false
  • English
  • Français

Leach Rates of High Level Waste and Spent Fuel. - Limiting Rates as Determined By Backfill and Bedrock Conditions.

Published online by Cambridge University Press:  15 February 2011

Ivars Neretnieks
Ivars Neretnieks*
Affiliation:
Department of Chemical Engineering Royal Institute of TechnologyS-100 44 Stockholm, Sweden
Get access

Abstract

The release rate of radionuclides from a degraded canister containing radioactive waste is controlled by diffusion through the backfill and by diffusion into the water flowing past the canister. In low porosity low permeability bedrock like the Swedish granites the amount of water which can be contaminated may be very small. Two sample cases are calculated. One uses the conditions for a repository for vitrified high level waste, the other applies to a repository for spent fuel. The small amount of water which can carry the waste in combination with the low solubilities for the major longlived actinides limit the release rate from the repositories to very small values.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 11: Symposium – Scientific Basis for Nuclear Waste Management V , 1981 , 559
Copyright
Copyright © Materials Research Society 1982

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. Allard, B. Solubilities of Actinides in Neutral or Basic Solutions. Proc. Actinides 81. Asilomar Sept. 10–15 1981. in press.Google Scholar
2. Andersson, G., Rasmuson, A., Neretnieks, I. Model for Near Field Migration. This publication.Google Scholar
3. Bird, R.B., Stewart, W.F., Lightfoot, E.N. Transport Phenomena. John Wiley N.Y. 1960.Google Scholar
4. Christensen, H, Studsvik Energiteknik AB, Studsvik Sweden. Personal Communication 1982.Google Scholar
5. Freeze, A. R., Cherry, J. A., Groundwater, Prentice Hall Inc. 1979.Google Scholar
6. KBS-1977. Handling of Spent Nuclear Fuel and Final Storage of Vitrified High-level Reprocessing Waste. Vol. IV Safety Analysis. KBS-Report, Stockholm 1977.Google Scholar
7. KBS-1978. Handling and Final Storage of Unreprocessed Spent Nuclear Fuel, Vol. II, Technical. KBS-Report, Stockholm 1978.Google Scholar
8. Nerenieks, I. Retardation of Escaping Nuclides from a Final Repository. KBS-Technical Report 30, 1977.Google Scholar
9. Neretnieks, I. Transport of Oxidants and Radionuclides through a Clay Barrier. KBS-Technical Report 79, 1978.Google Scholar
10. Neretnieks, I. Transport Mechanisms and Rates of Transport of Radionuclides in the Geosphere as Related to the Swedish KBS concept. IAEA publ. SM-243/108 IAEA Vienna, 1980.Google Scholar
11. Pusch, R. Highly Compacted Bentonite as a Buffer Substance. KBSTechnical Report 74, 1978.Google Scholar
12. Tietjens, O. Strömungslehre. Springer 1960.Google Scholar