Solid Radioactive Waste Strategy Report.pdf - UK EPR

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EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 80 / 257 The total quantity of the operational waste produced for interim storage and disposal highly depends on the conditioning and packaging processes selected. FIGURE 22: COMPARISON OF ESTIMATED 60 YEAR VOLUMES FOR INTERIM STORAGE AND FINAL DISPOSAL The conditioned volumes were calculated using average values based on similar wastes conditioned. The waste container packaging efficiency is assumed at 90%. It should be noted, that the interim storage volume highly depends on the handling strategy and the timing of final conditioning. ILW that will meet the LLW threshold limits during the timescales for decay storage on site prior to disposal off-site may be packaged in primary containers only.
EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 81 / 257 8 DECOMMISSIONING WASTE This section examines the nature and quantity of radioactive waste to be generated through the decommissioning of the nuclear island of a single UK EPR unit. The decommissioning methodology is outlined. It is explained how the design of the UK EPR will facilitate its decommissioning. This study does not take into account the conventional waste or nonradioactive waste generated from the dismantling of the conventional island plant (principally the turbine house and electrical switchgear) or the administrative buildings and non-nuclear site infrastructure. This section does not take into account decommissioning of the ILW and Spent Fuel Interim Stores. 8.1 EPR Plant Inventory and Radiological Characteristics After 60 Years of Operation 8.1.1 EPR Design Features for Decommissioning The UK EPR has been designed with maintenance and decommissioning in mind. The future decommissioning of the EPR has been planned and optimised at the design stage. Thus the design will enable decommissioning to be performed to minimise radiation doses to workers and minimise radioactive waste generation. In particular, the design incorporates the following features: · Choice of materials of construction to minimise activation; · Optimisation of neutron shielding; · Optimisation of access routes to nuclear areas; · Reactor systems design; · Ease of removal of major process components; · Submerged disassembly of reactor pressure vessel; · Modular thermal insulation; · Fuel cladding integrity; · Design for decontamination; · Prevention of contamination spread; · Minimisation of hazardous materials; · Summary of design principles. These are discussed in more detail below. 8.1.1.1 Choice Of Materials Of Construction To Minimise Neutron Activation Materials with a minimum propensity to become radioactive through activation (directly or through their corrosion products) have been selected for equipment subjected to irradiation. Cobalt-59, a stable isotope, is present in stainless steel and other alloys. Upon activation by neutrons it transmutes into cobalt-60 which is an intense gamma radiation emitter. Although cobalt-60 has a relatively short half life of 5.27 years, its presence is significant for decommissioning, if not for long term waste management. Therefore, elimination, wherever possible, of the use of alloys containing high cobalt levels in areas subject to neutron irradiation
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A 2008-11-26 Sarah Greenwood Gary C
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