Solid Radioactive Waste Strategy Report.pdf - UK EPR

EPR UK
N° NESH-G/2008/en/0123
REV. A PAGE 100 / 257
3. Where there are several reactors on the same site or several sites could be dismantled
within a few years of each other, the implementation of a centralised facility for size reduction
and packaging of reactors components may be feasible. This will:
· Use the same installation to dismantle and pack components of several reactors,
several sites;
· Allow development of very specialised / heavy tools;
· Important constraints to deal with the transport of such large components needs to be
taken account of.
4. Final dismantling may be adapted to take advantage of radiological decay (as seen with
the use of interim storage for short lived ILW). In this case, the decommissioning
sequence would be as follows:
· Removal of fissile materials (i.e. spent fuel) and radioactive liquids;
· Survey of this “interim storage nuclear installation.”
TABLE 27: ADVANTAGES AND DISADVANTAGES OF PROLONGING FINAL
DISMANTLING
– Advantages – Disadvantages
· Take advantage of future improvements in
decommissioning technology.
· Allow decay of activated waste to limit
quantity and volume of ILW (which is also the
case with the interim storage requested) and
in general allow some declassification of
waste which will reduce the overall cost.
· Avoid having to complete a full
decontamination of the primary circuit.
· Allow immediate transport of packaged ILW
to the Geological Disposal Facility (if
available).
· Reduce dose uptake of dismantling
operations.
· Reduce the biological protection required (insitu
and for the packaging).
· Reduce the packed volume of waste (where
radiological limits determine packaging
factors) and then the associated cost.
–
8.1.4 Baseline decommissioning scenario
· Increased long term monitoring costs.
· Potential loss of knowledge.
· Constraints on the future development of
the site.
· Financial burden of extended care and
maintenance of a disused facility.
· Need for new handling and process
equipment.
· More stringent regulation.
The decommissioning of a nuclear facility comprises several technical operations and
administrative processes whose end point is the site’s regulatory de-licensing.
The following decommissioning sequence applies and may proceed from the decision to the
permanent shut down of the facility following regulatory consent to proceed:
· Removal of fissile materials and radioactive liquids; post shutdown but with the
nuclear systems still operational, full in-situ decontamination of primary circuit using a
process such as CORD-UV. The removal of fissile materials, radiological liquids and
most of the contamination eliminates the largest part of the radiological hazard.
· Depending on the technical requirements, demolition or refurbishment of the
conventional and non nuclear plant and construction of decommissioning specific
service facilities;
–