Technology and Operation - Kernkraftwerk Gösgen

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Nuclear fuel cycle of plutonium which was used in the KKG reactor in the form of MOX fuel assemblies over the period 1997 to 2007. Reprocessing Irradiated fuel assemblies contain approximately 95 % uranium, 1 % plutonium and 4 % fission products. The precise composition depends on the discharge burn-up of the fuel assemblies. During the reprocessing operation, the structural materials are separated from the fuel. The fuel is split into uranium, plutonium and fission products by chemical means. The extracted energy carriers of uranium and plutonium are reused in fuel fabrication and recycled in the reactor. The fission products are embedded in a glass matrix, which is then welded into a steel container. These fission products form the highlevel waste. The structural materials from the irradiated fuel assemblies are processed into intermediate-level waste. Each year, 3.7 cubic metres of high-level waste and 3 cubic metres of intermediate-level waste are produced through the operation of the KKG. Irradiated fuel assemblies can be disposed of either with or without reprocessing. Whether the uranium and plutonium are recycled or not is subject to political influences. In Switzerland, for example, a ten-year moratorium came into effect in 2006 prohibiting the transport of irradiated fuel assemblies to reprocessing sites. Transport of irradiated fuel assemblies The transport of irradiated fuel assemblies and other radioactive materials is subject to statutory regulations, which are based on recommendations issued by the International Atomic Energy Agency (IAEA). The regulations are designed to protect people and the environment from harmful radiation and to protect the material being transported from external impacts. In the case of irradiated fuel assemblies that are being transported to a reprocessing site or to an interim storage facility, the requisite protection is provided by transport casks which constitute a radiation shield. Prior to certification, proof must be submitted of the fact that the casks can withstand the most severe of accident scenarios and remain completely tight. Interim storage The Central Interim Storage Facility in Würenlingen (ZZL) can take high-level, intermediate-level and low-level radioactive waste. This also includes the vitrified high-level and intermediate-level waste from reprocessing and from irradiated fuel assemblies from the nuclear power plants. Prior to transfer into a final repository, all high-level waste needs to be placed in interim storage (i.e. cooled) for 30 to 40 years on purely physical grounds in order to remove decay heat. The ZZL has sufficient capacity for an even longer period of storage. Geological repository After more than 30 years of investigations and research, comprehensive knowledge and a basis for decision-making have now been acquired for the establishment of repositories in deep geological formations that are required for radioactive waste. At the end of June 2006, the Federal Council approved the «Demonstration of Disposal Feasibility» for � � � � �50 � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � �
Reprocessing plant La Hague Fuel element assembly, Lingen (Photo: Areva) high-level radioactive waste issued by Nagra (National Co-operative for the Disposal of Radioactive Waste). This then provided conclusive evidence of the basic feasibility of permanent, safe disposal of all the nuclear waste in Switzerland. In April 2008, the Federal Council approved the «Deep Geological Repository Plan», a land-use-planning instrument which specifies the site selection procedure for deep geological repositories. Nuclear fuel cycle Fuel assemblies Fabrication of uranium fuel assemblies Enrichment Conversion Extraction and Purification Depleted uranium Fuel assemblies Fabrication of mixed oxide (MOX) fuel assemblies Plutonium Uranium Nuclear fuel cycle Different potential sites were identified, marking the first step towards site selection. Site selection will be conducted in a transparent and democratically supported process. Radioactive waste Uranium ore Repository � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � � �51 � � � � � � � Fuel assemblies Reprocessing of fuel assemblies Gösgen NPP Interim storage facility for fuel assemblies and radioactive waste Radioactive waste Fuel assemblies Conditioning Interim storage facility (ZZL) Würenlingen Rock laboratory Mont Terri (Photo: BGR)
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Technology and Operation Gösgen nu
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Page 25 and 26: Treatment of liquid radioactive was
Page 27 and 28: Safety barriers Nuclear fuel matrix
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Page 31 and 32: Containment venting system 1 Contai
Page 33 and 34: An extensive retrofit of the pressu
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Page 61 and 62: Characteristics HP = High-pressure
Page 63 and 64: Internet addresses � Swiss Federa
Page 65 and 66: Key technical data Power Gross elec
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Technology and Operation - Kernkraftwerk Gösgen

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