Solid Radioactive Waste Strategy Report.pdf - UK EPR

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EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 134 / 257 9.3.1.1.3 Comparison of Dry and Underwater Unloading Technologies The principal distinguishing features of the two options are compared in the following table. TABLE 40: MAIN ADVANTAGES AND DISADVANTAGES OF UNLOADING OPTIONS Dry unloading Underwater unloading Safety and radiological issues Environmental issues Performance issues Height differences in the unloading sequence are smaller, leading to a reduced risk from dropped loads. Operator doses tend to be lower when operations are undertaken in an active cell. Dry unloading is a faster operation leading to a lower exposure time. "Dry" unloading does not entirely remove the need for water as there is still a need for sipping tests and for cooling/rinsing of the transport container. There is a reduced need for transport container decontamination, leading to a reduction in associated wastes. Transport container unloading is much quicker as there are fewer handling and decontamination operations. The need for additional decontamination and the generation of additional liquid waste will lead to increased operator doses. This option requires the use of large volumes of water leading to increased secondary waste management issues. The existing underwater facilities are more flexible and can handle a range of transport container types. Although this should not be a significant issue as transport containers should be of a single design. The need for an unloading pool and for effluent management facilities leads to increased financial burden for outlay and operations. Depending on specific requirements, either wet or dry unloading technology can be selected. For the purpose of this report, dry unloading is the selected option as it presents much smaller secondary waste arisings and the reduced exposure to operators. This solution also provides adequate flexibility and ease of handling of different spent fuel packages.
EPR UK N° NESH-G/2008/en/0123 REV. A PAGE 135 / 257 9.3.1.2 Overview of Spent Fuel Storage Technologies After the initial cooling phase an interim storage period is required before spent fuel can be disposed. This interim storage facility may be located on site as defined by the base case or off the reactor site, serving several nuclear power plants. The storage facility can involve either dry or wet technology, and will be designed to meet the following requirements: o o o o o To ensure safe operations (e.g. by preventing a criticality incident and maintaining effective containment); To provide radiological protection to public, workers and the environment at all times in compliance with dose limits and ensuring that all doses are As Low As Reasonably Practicable; To ensure thermal cooling to maintain spent fuel integrity; To facilitate fuel assembly monitoring and retrievability; To maintain spent fuel in a condition appropriate for final disposal. Five interim storage solutions (based on AREVA proven technologies) are discussed in detail below: · Underwater storage; · Dry storage in a metal flask; · Dry storage in concrete storage modules (e.g.Nuhoms); · Dry storage in TN NOVA (Nuhoms evolution); · Dry storage in a vault. Among these 5 options, one wet and two dry solutions have been identified and assessed for the UK EPR. They are described in chapter 13. 9.3.1.2.1 Spent fuel Underwater Storage Underwater Spent Fuel Storage in GÖSGEN A further example of spent fuel storage in a pool is the GÖSGEN facility located on the GÖSGEN nuclear power plant in Switzerland. This Wet Spent Fuel Storage Facility can accommodate both uranium and MOX Fuel assemblies and is an independent extension of the existing spent fuel storage reactor pool. One of the main characteristics of this new storage facility is the almost exclusive use of passive cooling for the pool, based on natural air convection, which means that no active components are implemented (such as pumps). In its final configuration, the wet storage facility accommodates up to 1000 irradiated fuel assemblies stored in racks. The facility consists of the storage building, an adjacent service structure and two cooling towers. The storage building houses the fuel assemblies storage pool and the cask pool: it is a cubical, steel reinforced concrete structure of 17 m X 35 m X 25 m total height.
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