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Radioactive Waste Management: Disposal Concepts
UNDERGROUND DISPOSAL CONCEPTS
NRG conducts research and advices on surface and underground disposal concepts.
On this page the current situation with respect to disposal is discussed.
Current situation - World
Most radiological waste is in interim storage facilities, some more or less permanent solutions exist, but
solutions for high-level waste are in an experimental stage.
- On several locations experimental underground research facilities exist. They are used to assess the feasibility of the
underground disposal option(s). Examples of such facilities can be found in France, Belgium, Germany and the United States,
to name a few countries.
- On some locations sub-surface facilities are operated (shallow burial) for low-active waste (France, Spain, United States, etc.)
- Some deep underground disposal pilot facilities exist for high level waste (like the WIPP in the USA and a facility in Sweden).
- Some special cases exist: liquid radwaste has been injected into deep clay layers and low active waste
has been disposed of in former mines.
Current situation - Netherlands
All radioactive waste is in an interim storage facility with COVRA.
Research into deep underground waste disposal has a long tradition in the Netherlands. Co-operations exist with partner in Germany (e.g. GSF) and Belgium (e.g. SCK-CEN).
Initially research focussed on disposal in salt formations. The so-called 'van Hattum and Blankevoort' design of a special
mine for disposal of high active waste was a result of the OPLA research programme. During the succeeding CORA
research programme the design was modified to make retrievability a feasible option.
For the study of disposal in clay the SCK-CEN design was used. Modifications were made to facilitate retrievability.
For detailed information on the national waste management policy and research policy, refer to our page on policy and research programs.
Retrievability
Retrievability places two main requirements on the design:
- the disposal cells have to be designed such that the waste container can be retrieved easily from the
disposal cell, i.e. the retrieval should not be much more complicated than the emplacement of the container;
- the access shafts and access galleries cannot be sealed and closed while the retrievability requirement
persists. After closure and sealing, the only way to retrieve the waste would be to build new accesses
from the surface. The figure shows schematically the procedure to retrieve a canister from a disposal cell.

Figure 1 Retrieval of a canister with high level waste in four steps:
(1) remove the plug with a standard drill, (2) free the waste container and a thin layer
of surrounding material using a 'core-drill', (3) pull the container into a shielded container
on the transport vehicle, (4) close the shutter system on the transport vehicle to provide
radiation shielding during subsequent movement.
More information:
NRG, Radiation & Environment
Mr. A.D. Poley, PO Box 25, 1755 ZG Petten, Netherlands
Tel +31-224564333, Fax +31-224568491, Email: poley@nrg.eu
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