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Repository Source Term for Vitrified High Level Waste

Published online by Cambridge University Press:  26 February 2011

A Hough  and
JAC Marples
A Hough
Affiliation:
Harwell Laboratory, Didcot, Oxon 0X11 ORA, UK.
JAC Marples
Affiliation:
Harwell Laboratory, Didcot, Oxon 0X11 ORA, UK.
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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.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 127: Symposium BERLIN – Scientific Basis for Nuclear Waste Management XII , 1988 , 137
Copyright
Copyright © Materials Research Society 1989

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References

REFERENCES

1 Larkin, MJ, Nuclear Energy 25(1986)343 Google Scholar
2 Roberts, LEJ, Atom (1979)(267)2 Google Scholar
3 Hodgkinson, DP, Lever, DA and Rae, J, Prog. Nucl. Energy 11 (1983)183 Google Scholar
4 Marsh, GP, Pinard-Legry, G, Smailos, E, Casteels, F, Vu Quang, K, Cripps, J and Haijtink, C in Radioactive Waste Management and Disposal 1985, edited by Simon, R, (Cambridge University Press 1986 p 314)Google Scholar
5 Lake, LM, Davies, IL, Gera, F, Jorda, M, McEwen, T, Neerdael, C and Schmidt, MW in Radioactive Waste Management and Disposal 1985, edited by Simon, R (Cambridge University Press, 1986 p 562)Google Scholar
6 Marsh, GP Harwell Laboratory, UK Report No. AERE-R 10439 (1982)Google Scholar
7 Ewart, FT, Howse, RM, Thomason, HP, Williams, SJ and Cross, JE in Scientific Basis for Nuclear Waste Management IX Edited by Werme, LO, Mater. Res. Soc. (1986) Proc. 60 Pittsburgh, PA 1986 p 701 Google Scholar
8 Hall, AR, Boult, KA and Marples, JAC 'Evaluation of Solidified Highly Active Waste: Leaching of MW glass containing Pu and Am'. Harwell Laboratory UK Report No. AERE R-12580 (1987)Google Scholar
9 Marples, JAC Hall, AR, Hough, A and Boult, KA in ‘Testing and Evaluation of Solidified High Level Waste Forms’ Edited by Hall, AR. EUR 10852 (1987)Google Scholar
10 Kendall, GM, Kennedy, BW, Greenhalgh, JR, Adams, N and Fell, TP, National Radiological Protection Board Report NRPB-GS7 (1987)Google Scholar
11 Barbreau, A, Brereton, NR and Peaudecerf, P in Radioactive Waste Management and Disposal 1985 Edited by Simon, R, Cambridge University Press (1986) P 523.Google Scholar