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A Comparison of Site Characterisation Data and Modelling Results from a Radiological Assessment of the Drigg Low Level Radioactive Waste Disposal Site

Published online by Cambridge University Press:  01 February 2011

J. S. Small
Affiliation:
BNFL, Research and Technology, Risley, Warrington WA3 6AS, UK
P. K. Abraitis
Affiliation:
BNFL, Research and Technology, Risley, Warrington WA3 6AS, UK
I. R. Beadle
Affiliation:
BNFL, Research and Technology, Risley, Warrington WA3 6AS, UK
T. L. Johnstone
Affiliation:
BNFL, Research and Technology, Risley, Warrington WA3 6AS, UK
P. Kelly
Affiliation:
BNFL, Research and Technology, Risley, Warrington WA3 6AS, UK
C. L. Pettit
Affiliation:
BNFL, Research and Technology, Risley, Warrington WA3 6AS, UK
G. A. Stevens
Affiliation:
BNFL, Research and Technology, Risley, Warrington WA3 6AS, UK
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Abstract

The biogeochemical processes controlling release of radionuclides from solid low level radioactive waste (LLW) disposed at the Drigg site have been represented in a computational model in order to determine the effects of varying major element chemical parameters and solubility limits of radionuclides. The model is used to provide a source term for radiological safety assessment calculations for the groundwater pathway. Site data has been compared to the results for the initial stages of the model in order to build confidence in the conceptual and mathematical model used to derive the source term for 234U, the key dose contributor, and other radionuclides which are influenced by the biogeochemical processes. Measured aqueous concentrations of radionuclides whose release from LLW is sorption controlled are compared to the model results as a basis to discuss the uncertainty in sorption input parameters used.

Type
Research Article
Copyright
Copyright © Materials Research Society 2004

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References

REFERENCES

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