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The “Source Term” for Safety Assessments of the Disposal of Vitrified High-Level Radioactive Waste

Published online by Cambridge University Press:  28 February 2011

A. Hough ,
J. A. C. Marples  and
I. Handyside
A. Hough
Affiliation:
AERE Harwell, Didcot, Oxon, OXI1 ORA, UK.
J. A. C. Marples
Affiliation:
AERE Harwell, Didcot, Oxon, OXI1 ORA, UK.
I. Handyside
Affiliation:
Dept. of the Environment, Romney House, 43 Marsham Street, London, SWI 3PY. UK.
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Abstract

Two series of experiments have been carried out In an attempt to derive a source term for the release of some radioisotopes from vitrified high-level waste after disposal In hard rock. In the first type of experiment, the repository was modelled In miniature and the release of the isotopes was measured after they had leached from the glass and diffused through the backfill. In the second type. the “solubilities” of the isotopes were measured In the presence of the constituents of the repository.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 50: Symposium STOCKHOLM – Scientific Basis for Nuclear Waste Management IX , 1985 , 493
Copyright
Copyright © Materials Research Society 1985

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References

1 Statement from the 1983 Washington Meeting of the International Commission on Radiological Protection. Ann. ICPR 14 (1) 1984Google Scholar
2 International Commission on Radiological Protection. Ann ICPR 2(3/4).3, 4 (3/4).5. 6(2/3), 7.8.Google Scholar
3 National Radiological Protection Board Report NRPB-GS3 (1984)Google Scholar
4 DP HodgkInson. Private Communlalion (0985)Google Scholar