Solid Radioactive Waste Strategy Report.pdf - UK EPR

EPR UK
N° NESH-G/2008/en/0123
REV. A PAGE 104 / 257
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Minimisation of operator dose uptake (limitation of required personnel, limitation
of work at contact, minimisation of operation durations, use of mobile radiological
shielding protection);
Use as far as necessary of services like static and/or dynamic containment to
avoid any contamination risk;
Minimisation of dismantling cost;
Limitation of investment cost; use as far as possible existing equipment present
on site from normal operations;
Limitation of technical risk by using existing and proven technologies;
Management of the waste and minimisation of secondary and induced waste
generated.
8.1.5 Raw waste characteristics
8.1.5.1 ILW
8.1.5.1.1 Contaminated ILW
Based on preliminary calculations, the contaminated ILW resulting from the immediate
dismantling of the whole plant (considering classification at the dismantling date) will be limited
to the waste resulting from decontamination of the primary circuit which results in the production
of contaminated ion exchange resins.
This waste amounts to about 30 to 40 m 3 of resins. The β/γ activity on the resins will range
between 1E5 Bq/g and 4.5E5 Bq/g.
Based on 60 years of electricity production for an EPR followed by the immediate dismantling of
a single reactor, the ILW resins will be produced in year 61.
After interim storage up to the 100 years after the beginning of reactor operation (40 years after
reactor shutdown), the activity of these wastes will be significantly reduced and a proportion of
may be reclassified as LLW.
8.1.5.1.2 Activated ILW
Based on preliminary calculations, the ILW resulting from the immediate dismantling of the
whole plant (considering classification at the dismantling date) will be limited, depending of the
decay time considered, to:
· The neutron shield;
· Most of the reactor pressure vessel internals (upper and lower internals, excepted the far
upper sections of these components);
· The core shells of the reactor vessel (part of the reactor vessel located near the core
cavity);
· Part of the concrete of the reactor compartment.
These wastes amount to approximately 450 te of raw solid metallic waste and 180 te of
concrete.