Engineered Barriers Studies

We provide assessments, scientific research and consultancy regarding the performance of engineered barriers used in the containment of radioactive wastes, under storage, transportation and disposal conditions.

Engineered barriers include the wasteform in which the waste material may be immobilised, the containers in which wastes are packaged, and backfill and buffer materials used to fill the voids surrounding waste packages in a disposal facility. Work in this area includes the assessment of:

the leakage of dissolved radionuclides from corroding metal containers under a variety of conditions,
the release of radionuclides from different wasteforms (e.g. glasses, spent fuel or grouted solids and liquids),
the degree of containment provided by cementitious backfills used in disposal facilities.

SKB, Sweden: Research into development of stresses in steel/copper spent fuel canisters as a result of corrosion processes, in support of SKB's submissions for the deep disposal of HLW.
PNC, Japan: joint modelling and experimental study of the integrity of proposed carbon steel HLW overpacks, in support of PNC's development of a submission to the Japanese regulatory authorities.
JNFL, Japan: laboratory-based study of candidate cementitious backfill materials proposed for use in Japan in deep disposal of TRU wastes.

Nirex, UK: combined laboratory and modelling studies regarding the corrosion performance of carbon and stainless steel waste containers for the disposal of intermediate and low-level wastes.
Nirex, UK Combined laboratory and modelling studies regarding the chemical conditioning provided by Nirex Reference Vault Backfill.
Nirex, UK Simulation of radionuclide release from waste immobilised in a cementitious grout and packaged within a perforated waste container.

Also for a recent example of our work in the area of radionuclide release from HLW see

A.V. Chambers, T.G. Heath, C.M. Linklater, A.M. Thompson and R. Wiggin, Simulating Radionuclide Release and Water-rock Interactions During the Dissolution of Borosilicate Glass, in Scientific Basis for Nuclear Waste Management XXI, Materials Research Society, Pittsburgh USA, pp391-399, 1998.

Close Case Studies

Serco Assurance can provide an integrated solution, drawing on recognised expertise in laboratory-based studies, theoretical modelling and the provision of performance assessments and associated documentation.

We offer

computer modelling and laboratory-based investigations to study the properties and performance of engineered barriers;
research and development consultancy;
assessments of the performance of engineered barriers over the timescales associated with their use as the principal materials for the storage and emplacement of radioactive waste;
studies on the effect of the release of dissolved and gaseous radioactive and toxic materials, as a consequence of the evolution of the properties of the engineered barrier, e.g., as a function of drum corrosion or backfill leaching.

Benefits

support for submissions to regulatory bodies for permission to construct and operate disposal facilities for radwaste;
guidance to help focus planning and implementation of research and assessment programmes, potentially improving the efficiency and reducing the cost of such programmes;
optimisation of container and repository design.

Last updated: 06-Mar-2003