Skip to main content
Log in

Repository Source Term for Vitrified High Level Waste

  • Published:
MRS Online Proceedings Library Aims and scope

Abstract

Using doped glasses, the concentrations in aqueous solutions of Tc, Np, Pu and Am have been measured, over periods of up to 12 months, in the presence of various possible components of a future repository for vitrified high-level waste. The experiments were carried out under the reducing conditions anticipated in a repository. One possible repository design would incorporate a 20cm thick iron ‘overpack’ round the glass cylinders and a backfill of Ordinary Portland Cement (OPC) and Pulverised Fuel Ash (PFA). With this combination, the concentrations of Tc, Np, Pu and Am in the ‘repository’, after an 0.45um filtration, were respectively 7×10−9M, 7×10−10M, 2×10−12M and 2×10−12M i.e 0.1, 4, 1 and 45 times the ‘Limiting Concentration’ which, if present in drinking water, would lead to an annual dose of lmSv to someone drinking 2 litres per day.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Similar content being viewed by others

References

  1. MJ Larkin, Nuclear Energy 25(1986)343

    CAS  Google Scholar 

  2. LEJ Roberts, Atom(1979)(267)2

    Google Scholar 

  3. DP Hodgkinson, DA Lever and J Rae, Prog.Nucl. Energy 11.(1983) 183

    Article  CAS  Google Scholar 

  4. GP Marsh, G Pinard-Legry, E Smailos, F Casteels, K Vu Quang, J Cripps and B Haijtink in Radioactive Waste Management and Disposal 1985, edited by R Simon, (Cambridge University Press 1986 p314)

  5. LM Lake, IL Davies, F Gera, M Jorda, T McEwen, B Neerdael and MW Schmidt in Radioactive Waste Management and Disposal 1985, edited by R Simon (Cambridge University Press, 1986 p562)

  6. GP Marsh Harwell Laboratory, UK Report No. AERE-R 10439 (1982)

  7. FT Ewart, RM Howse, HP Thomason, SJ Williams and JE Cross in Scientific Basis for Nuclear Waste Management IX Edited by LO Werme, Mater. Res. Soc. (1986) Proc.60 Pittsburgh, PA 1986 p701

  8. AR Hall, KA Boult and JAC Marples ‘Evaluation of Solidified Highly Active Waste: Leaching of MW glass containing Pu and Am’. Harwell Laboratory UK Report No. AERE R-12580 (1987)

  9. JAC Marples AR Hall, A Hough and KA Boult in ‘Testing and Evaluation of Solidified High Level Waste Forms’ Edited by AR Hall. EUR 10852 (1987)

  10. GM Kendall, BW Kennedy, JR Greenhalgh, N Adams and TP Fell, National Radiological Protection Board Report NRPB-GS7(1987)

  11. A Barbreau, NR Brereton and P Peaudecerf in Radioactive Waste Management and Disposal 1985 Edited by R Simon, Cambridge University Press (1986) P 523.

Download references

Author information

Authors and Affiliations

Authors

Rights and permissions

Reprints and permissions

About this article

Cite this article

Hough, A., Marples, J. Repository Source Term for Vitrified High Level Waste. MRS Online Proceedings Library 127, 137–144 (1988). https://doi.org/10.1557/PROC-127-137

Download citation

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1557/PROC-127-137

Navigation