Solid Radioactive Waste Strategy Report.pdf - UK EPR

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EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 82 / 257 has been implemented. In particular the use of stellite for hard facing surfaces has been minimised. Where complete elimination of cobalt containing materials cannot be achieved, low cobalt content alloys have been selected. Alloy 690 has been selected instead of alloy 600 for the steam generator tubes. This minimises the quantity of cobalt in the corrosion products circulating in the primary system. The amount of cobalt in some steel components has been limited to 6 ppm. 8.1.1.2 Optimisation Of Neutron Shielding Shielding and barriers have been optimised to minimise the activation and contamination of equipment. For example, the UK EPR design incorporates neutron shielding around the core. This shielding reduces neutron activation of material and equipment in the vicinity of the core and thereby simplifies the clean-up of the structure while minimising the volume of active waste. The neutron shield will become activated during service. The neutron shield is modular by conception and has been designed for ease of removal from the reactor core. 8.1.1.3 Optimisation Of Access Routes To Nuclear Areas The design of access points in nuclear areas, handling equipment and access routes has been optimised in order to reduce the expected duration of exposure of workers (provisions facilitating removal of components and structure, and facilitating personnel access). The design makes use of international experience from past reactor decommissioning projects and measures taken to facilitate maintenance (for example, feedback from the replacement of steam generators in currently operating PWR plants). 8.1.1.4 Reactor Systems Design The design of reactor systems (core instrumentation, steam generators, reactor coolant pumps, pressuriser, heat exchangers etc.) has been optimised to facilitate decommissioning. Systems have been designed to minimise the creation, transportation and deposition of contamination. 8.1.1.5 Ease Of Removal Of Major Process Components The major process components within the reactor building (and reactor building access routes) have been designed to allow their removal from the reactor building each as a single item without the need for size reduction. This can allow their removal to other facilities for size reduction, waste conditioning and packaging. 8.1.1.6 Submerged Disassembly Of Reactor Pressure Vessel The design of the reactor compartment (fitted with a lost steel framework embedded in the concrete) makes it possible to fill the reactor compartment with water to allow the pressure vessel to be disassembled whilst submerged. The reactor compartment is lined with decontaminable steel to prevent contamination of its concrete structure.
EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 83 / 257 8.1.1.7 Modular Thermal Insulation Modular assembly of the thermal insulation on the main primary circuit allows its easy removal. The lagging which clips put into place reduces time required for its removal and therefore reduce dose uptake by operators. 8.1.1.8 Fuel Cladding Integrity Improvement of fuel cladding to further reduce the low likelihood of fuel leakages thus minimising the probability of the release of alpha and beta emitters into the primary circuit, minimising the extent of primary circuit contamination. 8.1.1.9 Design For Decontamination Design arrangements facilitate the decontamination of room and equipment: · Placing of injection seals, drainage lines and tanks, and sampling points to aid post operational clean-out and use of decontamination techniques; · Provision of coating or lining of walls. For example, the presence of a metal liner on the internal wall of the reactor building protects the reinforced concrete against contamination and will aid the clean-up operations and the subsequent demolition of the reactor building. 8.1.1.10 Prevention Of Contamination Spread The spread of contamination is minimised by appropriate measures such as containment, zoning, ventilation and segregated drains. 8.1.1.11 Minimisation Of Hazardous Materials The use of materials constituting controlled industrial waste is minimised as far as possible. 8.1.1.12 Summary Of Design Principles In summary, the design of the EPR reactor includes measures which will: · Minimise the volume of radioactive waste; · Minimise the toxicity of the waste; · Minimise the activity level of irradiated components; · Minimise the spread of contamination; · Permit easy decontamination; · Facilitate the access of personnel and machines and the removal of waste from the reactor building; · Reduce the operator intervention time. These measures optimise the dismantling of the reactor, limit the dose uptake for the corresponding operations and limit the quantity and activity of the nuclear waste produced in comparison to earlier PWR designs, which did not plan or consider decommissioning at the design stage.
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Solid Radioactive Waste Strategy Report.pdf - UK EPR

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