RD&D-Programme 2004 - SKB

Alternative methods. SKB is following the development of two alternatives to the KBS-3
concept: partitioning and transmutation (P&T) and disposal in boreholes several kilometres
deep, see Chapter 23. It is far from certain that either of these two methods will ever be
practical, but it may nevertheless be useful to follow what is being done internationally.
Basic research on P&T is being conducted in Sweden with SKB’s support. The researchers
are participating in the international projects and thereby helping SKB to keep track of
developments in the field.
Decommissioning. Decontamination and decommissioning (including dismantling) of
end-of-life installations is ultimately the responsibility of the owner. When it comes to the
nuclear power plants, SKB has been assigned the task of conducting general studies of
decommissioning in order to ensure that the necessary competence exists and that costs are
estimated correctly. Then the NPPs themselves are responsible for planning, licensing and
making sure that the plant is decontaminated and decommissioned. SKB helps to dispose of the
decommissioning waste, see Chapter 24. A method for dry interim storage of core components
has been developed, along with a system for registration of waste intended for disposal in future
repositories. Major decommissioning activities are not expected to begin before 2020 at the
earliest.
Low- and intermediate-level waste. In terms of volume, most of the waste from the NPPs is
short-lived low- and intermediate-level waste (LILW). It arises both during operation and when
the plant is finally shut down. This waste goes to SFR in Forsmark, which has been in operation
since 1988. There the operational waste from the NPPs is disposed of, together with a smaller
fraction of radioactive waste from research, medicine and industry that is delivered via an
interim storage facility in Studsvik. The short-lived waste from decommissioning is planned
to be disposed of in a future extension of SFR.
When the NPPs are decommissioned, even larger quantities of long-lived scrap from reactor
internals and core components will have to be disposed of, together with long-lived waste from
research and industry. The repository does not have to be sited and built for another 30 years at
least, so for the time being activities are limited to research in preparation for future assessments
of long-term safety, see Chapter 25.
8 RD&D-Programme 2004