Solid Radioactive Waste Strategy Report.pdf - UK EPR

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EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 204 / 257 Dry unloading will ensure: · Increased speed of transport container turnover resulting from fewer handling and decontamination operations; · Reduced liquid effluent and waste production as a result of simpler operations prior to and following transport container unloading; · No requirement for a specific unloading pool which reduces the overall height of the facility; · Ability to undertake operations remotely resulting in reduced personnel exposure. The baseline strategy is that the interim storage facility will be located on the reactor site. However, given the flexibility of the modular construction of a spent fuel storage facility, further consideration will be given elsewhere to the option of a centralised facility to accommodate spent fuel from several reactors, either on the site of one of the reactors or at a separate site. For example, where the spent fuel back end solution could be implemented (reprocessing or disposal). For that purpose and as an example, the vault storage technology is presented and sized for both one or several NPPs. 13.1.4 General Design data Considering the 241 fuel assemblies contained in the reactor core and the core renewal rate over the 60 years of the reactor service life, including periodic shutdowns for maintenance, about 3400 spent fuel assemblies will be produced and will require interim storage. This equates to a mass of about 1800 tonnes of enriched uranium to be stored per reactor. Taking into account a 10 year cooling period inside the reactor pool, the thermal output of a single spent fuel assembly arriving at the interim storage facility is calculated to be 1400 Watts (2000 Watts if using reprocessed fuel). Whatever technology and/or location is selected, all spent fuel storage facilities must meet the following safety requirements: · Ensure criticality control; · Provide radiation protection; · Provide safe and secure containment of radioactive material; · Ensure the integrity of the spent fuel assemblies; · Maintain adequate cooling of the spent fuel assemblies; · Facilitate retrieval of the spent fuel assemblies. This chapter assumes that a dry unloading technology would be implemented, although wet unloading remains a possible option and further analysis will be required before the final selection is made. In addition to spent fuel, the interim storage facilities may be used for activated core components such as the RCCas. RCCAs can be transferred from the reactor pool to the spent fuel interim storage facility using the same route as per the spent fuel for further decay.
EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 205 / 257 13.2 Wet Interim Storage Facility 13.2.1 Design Data The design of the wet storage facility for EPR spent fuel is based on the last generation of La Hague complex storage pools. The PWR spent fuel assemblies stored in each of the four La Hague pools are loaded into individual 9-cell storage baskets. To assist in criticality control, the baskets are made of boronated stainless steel. They are handled using a mast crane. The description of the wet storage technology provided hereafter is based on the use of spent fuel baskets. Rack technology could also be used which may slightly modify facility dimensions and handling requirements but would not result in a significant change to the overall process description. The interim storage pool for one EPR reactor shall be designed on the baseline of 380 baskets, each containing 9 fuel assemblies and generating a total less than 5 MW of residual heat. The main design objectives of the interim storage pool are: · To ensure containment of radioactive materials; · To ensure the removal of heat generated by the stored fuel; · To ensure the continuous cleaning of the pool water. 13.2.2 Functions and Process systems The wet interim storage facility is composed of three main building areas: · A reception hall for fuel assembly transport container receipt and preparation for unloading and shipping; · A process and utilities building for loading fuel assemblies into baskets and providing all necessary utilities for the storage process; · A pool building, including an entry channel for the baskets. The main mechanical functions performed in the facility are described below. 13.2.2.1 Transport Container Reception, Preparation And Shipping The reception hall takes delivery of the transport container, internal transfer of the container to the preparation areas before fuel unloading and stores or exports the empty transport containers for return to the reactor fuel building. When a fuel assembly is to be exported from the facility (i.e. for final disposal) the reverse operation will take place after loading the fuel assembly into a transport container. This part of the facility comprises the transport container reception hall, the preparation rooms and the process air lock area and is connected to the fuel assemblies unloading unit. a) Transport container arrival The transport container carriage or trailer will arrive in the reception hall. The reception hall doors, which can only be operated after clearance from the control room, will be opened to receive the transport container and the transport container will be transferred to its specific re-handling location where an external contamination check will be performed.
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