Inventory of Radioactive Waste

Transcription

1 Inventory of Radioactive Waste Current Inventory as at 31 December 2014 and Prediction August 2015 In the event of discrepancies between this translation and the original German version, the latter shall prevail

2 Contents 1. Introduction Summarising evaluation Scope of the data comprised Classification and categorisation of the radioactive waste Inventory of spent fuel and waste from reprocessing Inventory of other radioactive waste Waste inventories at the different sites Sites in Baden-Württemberg Karlsruhe Central Decontamination Department (Hauptabteilung Dekontaminationsbetriebe HDB) within the grounds of the Karlsruhe Institute of Technology (KIT) Campus North Neckarwestheim nuclear power plant Obrigheim nuclear power plant Philippsburg nuclear power plant Land collecting facility Baden-Württemberg Sites in Bavaria Garching Technische Universität München Karlstein Siemens AG Grafenrheinfeld nuclear power plant Gundremmingen nuclear power plant Isar nuclear power plant Mitterteich Power utilities storage facility Mitterteich Land collecting facility Bavaria Sites in Berlin Berlin Helmholtz-Zentrum für Materialien und Energie GmbH Berlin Land collecting facility Sites in Brandenburg Rheinsberg nuclear power plant Land collecting facility Brandenburg Sites in Bremen Land collecting facility Bremen Sites in Hamburg Land collecting facility Hamburg Sites in Hesse Ebsdorfergrund Land collecting facility Hesse Hanau NUCLEAR CARGO + SERVICE Biblis nuclear power plant Sites in Mecklenburg-Western Pomerania Greifswald nuclear power plant Rubenow Land collecting facility Mecklenburg-Western Pomerania

3 3.8.3 Rubenow Zwischenlager Nord storage facility Sites in Lower Saxony Braunschweig Eckert & Ziegler Nuclitec GmbH Braunschweig Research and measuring reactor Gorleben Storage facility Emsland nuclear power plant Grohnde nuclear power plant Lingen nuclear power plant Stade nuclear power plant Unterweser nuclear power plant Land collecting facility Lower Saxony Leese external storage facility for radioactive waste Lingen Fuel fabrication plant Munster central collecting facility of the German Armed Forces (Bundeswehr) Sites in North Rhine-Westphalia Ahaus Transport Cask Storage Facility Ahaus Duisburg Gesellschaft für Nuklearservice mbh Gronau Uranium enrichment plant Hamm-Uentrop High temperature reactor nuclear power plant Jülich Nuclear research reactor Jülich Research centre Jülich Gesellschaft für Nuklear-Service mbh Jülich Land collecting facility North Rhine-Westphalia Würgassen nuclear power plant Krefeld Siempelkamp Nukleartechnik GmbH Sites in Rhineland-Palatinate Ellweiler Land collecting facility Rhineland-Palatinate Mülheim-Kärlich nuclear power plant Mainz TRIGA Research Reactor Mainz Sites in Saarland Elm-Derlen Land collecting facility Saarland Sites in Saxony Rossendorf Land collecting facility Saxony Rossendorf VKTA Strahlenschutz, Analytik & Entsorgung Rossendorf e. V Sites in Saxony-Anhalt Land collecting facility Saxony-Anhalt Sites in Schleswig-Holstein Geesthacht Helmholtz-Zentrum Geesthacht Centre for Materials and Coastal Research GmbH Geesthacht Land collecting facility Brokdorf nuclear power plant Brunsbüttel nuclear power plant Krümmel nuclear power plant Sites in Thuringia Land collecting facility Thuringia

4 3.17 Sites abroad Disposed-of radioactive waste Radioactive waste prediction Predicted amounts of spent fuel and waste from reprocessing Predicted amounts of other radioactive waste Asse II mine

5 1. Introduction Residual radioactive material generated during the handling of radioactive material as well as disassembled or dismantled radioactive components shall be utilised without detrimental effects or disposed of as radioactive waste in a controlled manner. In the Federal Republic of Germany, radioactive waste is generated in connection with the operation of nuclear power plants and experimental, demonstration and research reactors, in connection with the decommissioning of nuclear power plants and experimental and demonstration reactors, of research and training reactors, and of other nuclear facilities, in connection with uranium enrichment and the fabrication of fuel assemblies (nuclear industry), in connection with basic and applied research, in connection with the use of radioisotopes in other research institutions, universities, trade and industry companies, hospitals and medical practices, in connection with other waste originators, such as e.g. the military sector, in future in connection with the conditioning of spent fuel intended for direct disposal. The Inventory of Radioactive Waste provides an overview of the inventory of radioactive waste and spent fuel assemblies in Germany which have been generated and are to be disposed of or have already been disposed of as at 31 December 2014 and a prediction of the expected volume of radioactive waste that will have arisen by the year It represents one of the bases for the planning of waste management and for the preparation of the National Programme. By indicating which radioactive waste is present in which location, the Federal Ministry for the Environment, Nature Conservation, Building and Nuclear Safety (Bundesministerium für Umwelt, Naturschutz, Bau und Reaktorsicherheit BMUB) complies with the required reporting to the EU Commission according to Directive 2011/70/Euratom on behalf of the Federal Republic of Germany. The inventory of radioactive waste is subject to constant change, which is why the Inventory of Radioactive Waste can only reflect the status at a specific point in time and will therefore be updated every three years. 5

6 2. Summarising evaluation 2.1 Scope of the data comprised The Inventory of Radioactive Waste comprises spent fuel and radioactive waste from reprocessing abroad in Europe that had already been returned by the reference date of 31 December 2014 as well as all types of radioactive waste to be disposed of in the Federal Republic of Germany. Radioactive waste from industrial, medical and research applications that has to be delivered to a Land collecting facility rather than directly to a federal disposal facility will only be taken into account once it has been delivered to a Land collecting facility. 2.2 Classification and categorisation of the radioactive waste For the purpose of representation in the Inventory of Radioactive Waste, a general distinction is made between: spent fuel and radioactive waste from reprocessing, and other radioactive waste. Due to their high level of decay heat, the former count as heat-generating waste and can be allocated for the largest part to the category of high-level waste according to the IAEA classification. With a few exceptions, the other radioactive waste belongs to the waste with negligible heat generation and is classified as low-level and intermediate-level waste according to the IAEA. The other radioactive waste (radioactive waste with negligible heat generation) is categorised 1) according to its processing condition for representation in the Inventory of Radioactive Waste: Raw waste is radioactive waste in its form of origin. Pretreated waste has been pretreated for better handling or storage. For its disposal, however, it has to be further conditioned. Conditioned waste products are waste in inner containers (e.g. drums) that have been conditioned to such an extent that any further treatment will no longer change its product properties. However, this waste will still have to be packaged in a disposal cask prior to its disposal. Disposal Containers are waste products in a type of container intended for disposal. 6

7 1) Here, the category system as defined in Appendix X of the German Radiation Protection Ordinance (StrlSchV) using primary waste (R), intermediate product (Z) and conditioned waste (K) for the purpose of inventorying the radioactive waste is replaced by the category system below. The comparison of the category systems is shown in Table 2.1. For the purpose of inventorying the radioactive waste, the waste is divided according to its state of processing into raw waste (RA), i.e. waste in its original form, and pretreated waste (VA), which e.g. has undergone preconditioning for better handling. For storage, waste will generally be conditioned. The conditioning process normally generates waste products that are usually stored in i.e. drums (as inner containers for future disposal containers) (P1) or already in disposal containers that are intended for the Konrad repository (G1). The product properties of this waste are generally not to be altered until its disposal. In the course of the product control by the Federal Office for Radiation Protection (BfS) it has to be ascertained that the waste product, if it meets the waste acceptance requirements, is suitable for emplacement in the Konrad repository. If this is the case at least for the radiological aspects, a product-controlled waste product (P2) is generated from the waste product of the P1 category. The waste products of the P2 category will then be inserted into Konrad containers for disposal and, if necessary, grouted in concrete (G1). If suitability of the disposal container (G1) for disposal is confirmed by the BfS, it will be categorised as a product-controlled disposal container (G2) which can be enrolled and requested for emplacement in the Konrad repository. A disposal container does not necessarily run through all steps from RA to G2; however, only G2 packages may be disposed of in the Konrad repository. Table 2.1: Correlation between the former and the more recent category system Primary waste Intermediate product Conditioned waste Raw waste and pretreated waste Conditioned waste products Disposal containers RA VA P1 P2 G1 G2 X X X X X X X X X In the Inventory of Radioactive Waste, RA and VA are summarised in one category, P1 and P2 are summarised as waste products, and G1 and G2 as disposal containers for reasons of clarity. 7

8 2.3 Inventory of spent fuel and waste from reprocessing At the reference date of 31 December 2014, about 8,380 Mg HM 2 had been generated from the operation of nuclear power plants 3 in the Federal Republic of Germany in the form of spent fuel assemblies (FA), which will have to be disposed of in Germany. Table 2.2: Inventory of spent fuel from German nuclear power plants, stored in Germany, as at 31 December 2014 Storage location Containers Fuel assemblies Nuclear power plant storage pools* 14,013 FA 4,258 Mg HM Dry cask storage in on-site storage facilities 352 9,638 FA 3,444 Mg HM Dry cask storage in the Ahaus and Gorleben storage 76 5,343 FA 677 Mg HM facilities and the Zwischenlager Nord storage facility 28,994 FA 8,379 Mg HM * including the wet storage facility at the site of the Obrigheim nuclear power plant, which is being decommissioned, and the reactor core of the permanently closed down Brunsbüttel nuclear power plant Radioactive waste that has been returned from reprocessing abroad in Europe and high-level vitrified waste that has been generated in Germany is stored in the Gorleben and Zwischenlager Nord storage facilities in the form of 3,164 canisters in 113 casks. The amount of spent fuel from German experimental and demonstration reactors yet to be disposed of are in dry storage in 461 casks in the Ahaus storage facility, at the research centre Forschungszentrum Jülich, and in the Zwischenlager Nord storage facility. The amount of spent fuel from research reactors is less by several orders of magnitude than the amount from nuclear power plants and is stored by the research reactors in Berlin, Garching and Mainz as well as in 18 casks in the Ahaus storage facility. 2.4 Inventory of other radioactive waste The inventory of other radioactive waste is given in Table 2.3. The distribution of the around 117,000 m³ of conditioned radioactive waste present at the reference date of 31 December 2014 between the groups of waste originators can be taken from Fig Megagram of heavy metal (Mg HM) is the unit of the mass of heavy metal and hence a measure for the fuel content (uranium, plutonium and thorium) of a fuel assembly. 3 Nuclear power plant in this context describes an installation for the fission of nuclear fuel for the commercial generation of electricity. 8

9 Fig. 2.1: Breakdown of the current inventory of other conditioned radioactive waste by groups of waste originators as at 31 December 2014 Reprocessing in Gemany 13% Land collecting facilities 3% Nuclear power plants in in postoperational phase or under decommissioning 31% Research institutions 37% Nuclear power plants in operation 7% Nuclear industry 9% Table 2.3: Current inventory of other radioactive waste (as at 31 December 2014) 4 Processing condition /Volume 5 21,662 Mg Conditioned waste products 16,908 m 3 Disposal Containers 100,288 m 3 The volume of raw waste and pretreated waste is given as their mass since the volume of this waste is usually reduced by conditioning and therefore does not allow any conclusions as to the volume to be disposed of. The conditioned waste is given as waste volume since in this case, the expected volume to be disposed of will usually only grow by the packaging of the waste products in disposal containers, but not by any changes of the waste product itself. Before a disposal container can be accepted for emplacement in the Konrad repository, the product control process has to be concluded. In this process, the disposal container's compliance with the requirements for disposal is verified. So far, approx. 3,000 m³ of radioactive waste have been ascertained to comply with the requirements for disposal in the Konrad repository and hence have been cleared for enrollment for emplacement in the Konrad repository by the Federal Office for Radiation Protection (BfS). 4 Differences to other publications are due to the processing of data with the focus on the storage facility site instead of on the waste owners. 5 Including other radioactive waste stored abroad. 9

10 3. Waste inventories at the different sites For representation in the Inventory of Radioactive Waste, the waste was grouped by the storage sites on 31 December 2014 as notified by the waste originators. The licence holder of a facility is not necessarily identical with the originator (owner) of the waste. Since according to 78 of the Radiation Protection Ordinance (StrlSchV) storage may be executed jointly by several waste originators or by third parties, the owner of the waste is not necessarily the proprietor. Conditioning facilities that are not clearly physically separated from the storage facilities are included in the lists of the respective sites, with the amount of waste in the process of being conditioned not explicitly shown. In the case of external conditioning facilities, the waste in the process of being conditioned there is listed. Once conditioning has been completed, the waste is moved to waste storage facilities. Fig. 3.1 gives an overview of the sites of the reactors, transport cask storage facilities, waste storage facilities, Land collecting facilities and conditioning facilities in the Federal Republic of Germany. 10

11 Fig. 3.1: Sites of the reactors, transport cask storage facilities, waste storage facilities, Land collecting facilities and conditioning facilities for radioactive waste in the Federal Republic of Germany 11

12 Regarding fuel assemblies, their dimensions and fuel content differ from reactor type to reactor type. In general, the information on the number of fuel assemblies provided in the Inventory of Radioactive Waste represents the corroborated and reliable figures. Since the associated mass of heavy metal i.e. a measure for the fuel content (uranium, plutonium and thorium) is also of interest in connection with many other issues, this is also indicated. These data were obtained by calculations. For this purpose, the number of fuel assemblies was multiplied by an average mass of heavy metal per fuel assembly. It has to be noted in this context that on the one hand, over the years the mass of heavy metal per fuel assembly had been subjected to changes during production and on the other hand that it decreases as a result of burn-up. The calculated masses of heavy metal can therefore only serve as guide values and are not exactly identical with the actual masses in the spent fuel assemblies. It has to be noted here that only little amounts of uranium and plutonium are present in the waste from reprocessing as these were separated and reused. The raw waste and the pretreated waste is differentiated by its chemical form, based on Appendix X Part A No. 2 of the Radiation Protection Ordinance (StrlSchV). The conditioned waste products are differentiated by the type and volume of the package 6). 6 The package volumes indicated are the gross volumes of the packages. The respective typical volumes can be taken from the table below. Container Gross volume Container Gross volume 200-l drum 0.27 m³ Cast-iron container Type III 1.00 m³ 280-l drum 0.38 m³ Container Type I 3.90 m³ 400-l drum 0.52 m³ Container Type I (Type KfK) 3.80 m³ 570-l drum 0.75 m³ Container Type II 4.60 m³ Concrete container Type I 1.20 m³ Container Type III 8.70 m³ Concrete container Type II 1.30 m³ Container Type IV 7.40 m³ Cast-iron container Type I 0.70 m³ Container Type IV (Type KfK) 7.14 m³ Cast-iron container Type II 1.30 m³ Container Type V m³ Cast-iron container Type II (Type KfK) 1.20 m³ Container Type VI 5.40 m³ 12

13 3.1 Sites in Baden-Württemberg Karlsruhe Central Decontamination Department (Hauptabteilung Dekontaminationsbetriebe HDB) within the grounds of the Karlsruhe Institute of Technology (KIT) Campus North Facility sections: WAK GmbH WAK GmbH Storage facilities > unlimited licence Conditioning facilities > unlimited licence Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Liquid waste, organic Mixed waste Radiation sources 2,722.1 Mg 75.6 Mg 64.0 Mg 2.9 Mg Mg 5.3 Mg 2,985.1 Mg 200-l drum 6,942 1,874 m³ 280-l drum m³ 400-l drum m³ 570-l drum m³ Concrete container Type II 1 1 m³ Container Type IV (Type KfK) m³ Cast-iron container Type II m³ 7,903 2,461 m³ Disposal containers Number Volume Concrete container Type I 7,102 8,522 m³ Concrete container Type II m³ Container Type IV 9 67 m³ Container Type IV (Type KfK) 6,517 46,546 m³ Cast-iron container Type II m³ Cast-iron container Type II (Type KfK) m³ Other 274 1,203 m³ 14,332 56,869 m³ 13

14 3.1.2 Neckarwestheim nuclear power plant Facility sections: EnBW Kernkraft GmbH Neckarwestheim nuclear power plant Unit I > post-operational phase Unit II > in operation, power operating licence expires on 31 December 2022 On-site storage facility > storage limited to 40 years after first emplacement (6 December 2006) Spent fuel and vitrified waste from reprocessing Fuel assemblies Net mass Storage pool 824 FA 385 Mg HM Storage facility - 44 Castor V/ FA 405 Mg HM 1,660 FA 790 Mg HM Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Liquid waste, organic Mixed waste Radiation source Mg 48.7 Mg 0.6 Mg 1.3 Mg 6.5 Mg <0.1 Mg Mg 200-l drum m³ 280-l drum 4 2 m³ m³ 14

15 Disposal containers Number Volume Concrete container Type II m³ Container Type IV 1 7 m³ Cast-iron container Type II m³ m³ 15

16 3.1.3 Obrigheim nuclear power plant Facility sections: EnBW Kernkraft GmbH Obrigheim nuclear power plant Nuclear power plant > under decommissioning Wet fuel assembly storage facility > unlimited licence Spent fuel and vitrified waste from reprocessing Fuel assemblies Net mass Wet fuel assembly storage facility 342 FA 100 Mg HM 342 FA 100 Mg HM Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Mixed waste 96.8 Mg 15.1 Mg 1.4 Mg 16.9 Mg Mg 200-l drum 1 <1 m³ Other m³ m³ Disposal containers Number Volume Concrete container Type II 4 5 m³ Container Type II m³ Container Type III 3 26 m³ Container Type IV m³ Container Type V m³ Cast-iron container Type II m³ m³ 16

17 3.1.4 Philippsburg nuclear power plant Facility sections: EnBW Kernkraft GmbH Philippsburg nuclear power plant Unit 1 > post-operational phase Unit 2 > in operation, power operating licence expires on 31 December 2019 On-site storage facility > storage limited to 40 years after first emplacement (19 March 2007) Conditioning facilities > unlimited licence Spent fuel and vitrified waste from reprocessing Fuel assemblies Net mass Storage pool 1,427 FA 448 Mg HM Storage facility - 25 Castor V/19-11 Castor V/ FA 257 Mg HM 572 FA 100 Mg HM 2,474 FA 805 Mg HM Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Liquid waste, organic Mixed waste 90.4 Mg 43.7 Mg 1.9 Mg 0.2 Mg 31.9 Mg Mg 200-l drum 3, m³ 400-l drum m³ 3, m³ 17

18 Disposal containers Number Volume Concrete container Type I m³ Concrete container Type II m³ Container Type III m³ Cast-iron container Type II m³ m³ 18

19 3.1.5 Land collecting facility Baden-Württemberg The radioactive waste of the Land collecting facility Baden-Württemberg is stored at the site of the WAK Decommissioning and Waste Management Company (Wiederaufarbeitungsanlage Karlsruhe Rückbau- und Entsorgungs-GmbH) in Karlsruhe. 19

20 3.2 Sites in Bavaria Garching Technische Universität München Facility sections: Technische Universität München Technische Universität München Research Reactor Munich > under decommissioning FRM II (Forschungs-Neutronenquelle Heinz Maier-Leibnitz) (in operation) > unlimited licence Institute of Radiochemistry > unlimited licence Spent fuel and vitrified waste from reprocessing Rack in the set-down pool of the FRM II Fuel assemblies Net mass 35 FA kg uranium 35 FA kg uranium Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Mixed waste 28.1 Mg 2.0 Mg 2.7 Mg 0.7 Mg 33.5 Mg 200-l drum 4 1 m³ Cast-iron container Type II 1 1 m³ 5 2 m³ 20

21 3.2.2 Karlstein Siemens AG Facility sections: Siemens AG, Energy Sector Siemens AG Nuclear energy experimental facility and service centre > unlimited licence Storage facilities > unlimited licence Conditioning facilities > unlimited licence Solid waste, inorganic Solid waste, organic 29.0 Mg 0.2 Mg 29.2 Mg 200-l drum 4 1 m³ 280-l drum 1 <1 m³ 400-l drum 1 1 m³ Cast-iron container Type II 4 5 m³ 10 7 m³ Disposal containers Number Volume Container Type III m³ Container Type IV (Type KfK) m³ Container Type VI 236 1,274 m³ 394 2,455 m³ 21

22 3.2.3 Grafenrheinfeld nuclear power plant Facility sections: E.ON Kernkraft GmbH Grafenrheinfeld nuclear power plant Nuclear power plant > in operation, power operation licence expires on 31 December 2015 On-site storage facility > storage limited to 40 years after first emplacement (27 February 2006) Spent fuel and vitrified waste from reprocessing Fuel assemblies Net mass Storage pool 404 FA 217 Mg HM Storage facility - 21 Castor V/ FA 214 Mg HM 803 FA 431 Mg HM Solid waste, inorganic Solid waste, organic Liquid waste, inorganic 11.3 Mg 17.2 Mg 0.5 Mg 29.0 Mg 200-l drum m³ m³ Disposal containers Number Volume Cast-iron container Type II m³ m³ 22

23 3.2.4 Gundremmingen nuclear power plant Facility sections: RWE Power AG Gundremmingen nuclear power plant Unit A > under decommissioning Unit B > in operation, power operation licence expires on 31 December 2017 Unit C > in operation, power operation licence expires on 31 December 2021 On-site storage facility > storage limited to 40 years after first emplacement (25 August 2006) Conditioning facilities > unlimited licence Spent fuel and vitrified waste from reprocessing Fuel assemblies Net mass Storage pool 4,410 FA 767 Mg HM Storage facility - 42 Castor V/52 2,184 FA 380 Mg HM 6,594 FA 1,147 Mg HM Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Liquid waste, organic Mixed waste 48.5 Mg 1.4 Mg 4.4 Mg 0.5 Mg 19.4 Mg 74.2 Mg 200-l drum m³ m³ 23

24 Disposal containers Number Volume Container Type IV m³ Cast-iron container Type II m³ m³ 24

25 3.2.5 Isar nuclear power plant Facility sections: E.ON Kernkraft GmbH Isar nuclear power plant Isar 1 > post-operational phase Isar 2 > in operation, power operation licence expires on 31 December 2022 On-site storage facility > storage limited to 40 years after first emplacement (12 March 2007) Spent fuel and vitrified waste from reprocessing Fuel assemblies Net mass Storage pool 2,172 FA 536 Mg HM Storage facility - 25 Castor V/19-9 Castor V/ FA 254 Mg HM 468 FA 81 Mg HM 3,115 FA 871 Mg HM Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Mixed waste Mg 18.7 Mg 0.9 Mg < 1 Mg Mg 200-l drum m³ 280-l drum 17 6 m³ 400-l drum m³ 570-l drum 5 4 m³ m³ 25

26 Disposal containers Number Volume Concrete container Type II 3 4 m³ Cast-iron container Type I 2 1 m³ Cast-iron container Type II m³ m³ 26

27 3.2.6 Mitterteich Power utilities storage facility GRB Sammelstelle Bayern für radioaktive Stoffe GmbH Power utilities storage facility Mitterteich > Licence limited until 31 December l drum 11,899 3,213 m³ 280-l drum m³ 400-l drum m³ 570-l drum m³ Other 5 14 m³ 12,323 3,411 m³ Disposal containers Number Volume Concrete container Type I m³ Concrete container Type II m³ Container Type I 6 23 m³ Container Type III 1 9 m³ Container Type IV 164 1,214 m³ Container Type V m³ Cast-iron container Type II 1,993 2,591 m³ 2,452 4,306 m³ 27

28 3.2.7 Mitterteich Land collecting facility Bavaria GRB Sammelstelle Bayern für radioaktive Stoffe GmbH Land collecting facility Bavaria > Licence limited until 31 December 2028 Note: Raw waste is also accepted at the Neuherberg outpost. Mixed waste Radiation sources 7.2 Mg <0.1 Mg 7.2 Mg 200-l drum m³ 280-l drum 6 2 m³ 400-l drum 10 5 m³ m³ 28

29 3.3 Sites in Berlin Berlin Helmholtz-Zentrum für Materialien und Energie GmbH Helmholtz-Zentrum für Materialien und Energie GmbH Berliner-Experimentier-Reaktor II > Operation will cease on 31 December 2019 Spent fuel and vitrified waste from reprocessing Fuel assemblies Net mass Set-down racks 57 FA 77.4 kg SM 57 FA 77.4 kg SM Solid waste, inorganic 0.3 Mg 0.3 Mg 29

30 3.3.2 Berlin Land collecting facility Facility sections: Helmholtz-Zentrum für Materialien und Energie GmbH Land collecting facility Berlin Land collecting facility > unlimited licence Conditioning facilities > unlimited licence Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Liquid waste, organic Gaseous waste Mixed waste Radiation sources 76.2 Mg 3.7 Mg Mg 0.5 Mg <0.1 Mg 27.9 Mg 2.8 Mg Mg 200-l drum m³ 400-l drum 12 6 m³ m³ Disposal containers Number Volume Container Type IV m³ m³ 30

31 3.4 Sites in Brandenburg Rheinsberg nuclear power plant Facility sections: EWN GmbH Rheinsberg nuclear power plant Nuclear power plant > under decommissioning Conditioning facilities > unlimited licence Solid waste, inorganic Liquid waste, organic Mixed waste Mg 3.0 Mg 40.5 Mg Mg 200-l drum m³ 570-l drum 1 1 m³ m³ Disposal containers Number Volume Concrete container Type I m³ Concrete container Type II 6 8 m³ m³ 31

32 3.4.2 Land collecting facility Brandenburg The radioactive waste of the Land collecting facility is stored together with the waste of the Land collecting facility Mecklenburg-Western Pomerania in the Zwischenlager Nord storage facility. 32

33 3.5 Sites in Bremen Land collecting facility Bremen The radioactive waste of the Land collecting facility is stored together with the waste of the Land collecting facilities Hamburg, Lower Saxony and Schleswig-Holstein at the Helmholtz-Zentrum Geesthacht Centre for Materials and Coastal Research GmbH in Geesthacht. 33

34 3.6 Sites in Hamburg Land collecting facility Hamburg The radioactive waste of the Land collecting facility is stored together with the waste of the Land collecting facilities Bremen, Lower Saxony and Schleswig-Holstein at the Helmholtz-Zentrum Geesthacht Centre for Materials and Coastal Research GmbH in Geesthacht. 34

35 3.7 Sites in Hesse Ebsdorfergrund Land collecting facility Hesse Hessian Agency for the Environment and Geology Land collecting facility Hesse unlimited licence Mixed waste Mg Mg 200-l drum m³ m³ 35

36 3.7.2 Hanau NUCLEAR CARGO + SERVICE Facility sections: NUCLEAR CARGO + SERVICE GmbH NUCLEAR CARGO + SERVICE GmbH two storage facilities > unlimited licence Solid waste, inorganic 0.4 Mg 0.4 Mg 200-l drum m³ 280-l drum 2 1 m³ 400-l drum m³ 570-l drum 5 4 m³ m³ Disposal containers Number Volume Concrete container Type I m³ Concrete container Type II 6 8 m³ Cast-iron container Type II 4 5 m³ Container Type IV 1 7 m³ Container Type IV (Type KfK) 278 1,985 m³ Container Type V m³ Container Type VI 954 5,152 m³ 1,405 7,633 m³ 36

37 3.7.3 Biblis nuclear power plant Facility sections: RWE Power AG Biblis nuclear power plant Unit A and B > post-operational phase Waste storage depot (LAW storage) > unlimited licence On-site storage facility > storage limited to 40 years after first emplacement (18 May 2006) > since the 3 rd modification licence of 16 June 2014, the mixed storage of transport and storage casks and up to 252 Mosaik containers has been possible in storage hall No. 2 Spent fueland vitrified waste from reprocessing Fuel assemblies Net mass Storage pool 946 FA 506 Mg HM Storage facility - 51 Castor V/ FA 519 Mg HM 1,915 FA 1,025 Mg HM Solid waste, inorganic Solid waste, organic Liquid waste, organic Mixed waste Radiation sources 84.5 Mg 21.7 Mg 2.9 Mg 8.8 Mg <0.1 Mg Mg 200-l drum m³ 280-l drum 24 9 m³ 400-l drum m³ 570-l drum 3 2 m³ m³ 37

38 Disposal containers Number Volume Concrete container Type I m³ Concrete container Type II m³ Cast-iron container Type I m³ Cast-iron container Type II m³ Cast-iron container Type III m³ 1,777 2,052 m³ 38

39 3.8 Sites in Mecklenburg-Western Pomerania Greifswald nuclear power plant Facility sections: Energiewerke Nord GmbH Greifswald nuclear power plant Nuclear power plant Units 1-6 > under decommissioning Conditioning facilities > unlimited licence Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Liquid waste, organic Mixed waste 89.2 Mg 17.3 Mg Mg 4.5 Mg Mg Mg 200-l drum m³ m³ 39

40 3.8.2 Rubenow Land collecting facility Mecklenburg-Western Pomerania ZLN GmbH and EWN GmbH Land collecting facility for radioactive waste of the Land of Mecklenburg-Western Pomerania > unlimited licence Note: The waste of the Land collecting facility for radioactive waste of the Land of Mecklenburg- Western Pomerania is stored together with the waste of the Land collecting facility of the Land of Brandenburg in the Zwischenlager Nord storage facility. Solid waste, inorganic 1.3 Mg 1.3 Mg 40

41 3.8.3 Rubenow Zwischenlager Nord storage facility Facility sections: EWN GmbH, ZLN GmbH Zwischenlager Nord Storage for radioactive waste > unlimited licence Storage facility > Storage limited until 31 October 2039 Conditioning facilities > unlimited licence Spent fuel and vitrified waste from reprocessing Storage facility - 62 Castor 440/84 and 3 Castor KRB-MOX - 4 Castor KNK - 5 Castor HAW 20/28 CG with vitrified fission product solutions Fuel assemblies and canisters FA 2,413 fuel rods 140 canisters 5,048 FA 2,413 fuel rods 140 canisters Net mass 584 Mg HM 0.5 Mg HM Mg HM Solid waste, inorganic Liquid waste, inorganic Mixed waste Radiation sources 3,756.5 Mg 14.6 Mg 8.6 Mg 1.4 Mg 3,781.1 Mg 200-l drum 10,614 2,866 m³ 280-l drum m³ 400-l drum m³ 570-l drum m³ 10,780 2,952 m³ 41

42 Disposal containers Number Volume Concrete container Type I m³ Container Type IV m³ Container Type IV (Type KfK) 477 3,406 m³ Cast-iron container Type II m³ 565 3,631 m³ 42

43 3.9 Sites in Lower Saxony Braunschweig Eckert & Ziegler Nuclitec GmbH Eckert & Ziegler Nuclitec GmbH Conditioning facilities > unlimited licence Solid waste, inorganic Mixed waste Radiation sources 8.1 Mg 31.4 Mg 6.6 Mg 46.1 Mg 43

44 3.9.2 Braunschweig Research and measuring reactor Facility sections: Physikalisch-Technische Bundesanstalt Research and measuring reactor Braunschweig Research reactor > dismantled, released from nuclear supervision with the exception of the storage facility > licence limited until emplacement in a federal disposal facility is possible, with additional adequate time for work related to the delivery to the disposal facility 200-l drum m³ 400-l drum m³ 570-l drum 2 2 m³ m³ Disposal containers Number Volume Concrete container Type I 7 8 m³ 7 8 m³ 44

45 3.9.3 Gorleben Storage facility Facility sections: BLG Brennelementlager Gorleben GmbH, GNS Gesellschaft für Nuklear-Service mbh Storage facility Gorleben Gorleben waste storage facility > unlimited handling licence Transport cask storage facility > storage licence limited until 31 December 2034 Spent fueland vitrified waste from reprocessing Storage facility - 3 Castor V/19-1 Castor Ic - 1 Castor IIa - 74 Castor HAW 20/28 CG with vitrified fission product solutions - 12 TN 85 with vitrified fission product solutions - 1 TS 28 V with vitrified fission product solutions - 21 Castor HAW28M with vitrified fission product solutions Fuel assemblies and canisters 57 FA 16 FA 9 FA 2,072 canisters 336 canisters 28 canisters 588 canisters 82 FA 3,024 canisters Net mass 30 Mg HM 3 Mg HM 5 Mg HM 38 Mg HM 200-l drum 1, m³ 280-l drum m³ 400-l drum m³ Concrete container Type II 8 10 m³ Cast-iron container Type II 3 4 m³ 1, m³ 45

46 Disposal containers Number Volume Concrete container Type I m³ Concrete container Type II m³ Container Type III m³ Container Type IV m³ Container Type V 301 3,281 m³ Container Type VI m³ Cast-iron container Type II 1,015 1,320 m³ Cast-iron container Type III m³ 2,078 6,676 m³ 46

47 3.9.4 Emsland nuclear power plant Facility sections: Kernkraftwerke Lippe-Ems GmbH Emsland nuclear power plant Nuclear power plant > in operation, power operation licence expires on 31. December 2022 On-site storage facility > storage limited to 40 years after first emplacement (10 December 2002) Spent fuel and vitrified waste from reprocessing Fuel assemblies Net mass Storage pool 510 FA 274 Mg HM Storage facility - 32 Castor V/ FA 327 Mg HM 1,118 FA 601 Mg HM Solid waste, inorganic Solid waste, organic 7.4 Mg 17.3 Mg 24.7 Mg 200-l drum m³ m³ Disposal containers Number Volume Cast-iron container Type II m³ m³ 47

48 3.9.5 Grohnde nuclear power plant Facility sections: E.ON Kernkraft GmbH Grohnde nuclear power plant Nuclear power plant > in operation, power operation licence expires on 31 December 2021 On-site storage facility > storage limited to 40 years after first emplacement (27 April 2006) Spent fuel and vitrified waste from reprocessing Fuel assemblies Net mass Storage pool 502 FA 274 Mg HM Storage facility - 22 Castor V/ FA 228 Mg HM 920 FA 502 Mg HM Solid waste, inorganic Solid waste, organic Liquid waste, organic Mixed waste 5.0 Mg 33.4 Mg 0.7 Mg 17.0 Mg 56.1 Mg 200-l drum m³ 400-l drum 5 3 m³ m³ Disposal containers Number Volume Cast-iron container Type II m³ m³ 48

49 3.9.6 Lingen nuclear power plant Kernkraftwerk Lingen GmbH Lingen nuclear power plant > in safe enclosure, transition to dismantling Solid waste, inorganic Mixed waste Mg 19.3 Mg Mg 200-l drum m³ 280-l drum m³ m³ Disposal containers Number Volume Cast-iron container Type II m³ m³ 49

50 3.9.7 Stade nuclear power plant Facility sections: E.ON Kernkraft GmbH Stade nuclear power plant Nuclear power plant > under decommissioning Storage for radioactive waste (LarA) > to be cleared out once the Konrad repository is in operation, therefore limited to a maximum of 40 years from date of commissioning (July 2007) Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Mixed waste Mg 4.2 Mg 0.6 Mg 6.0 Mg Mg 200-l drum m³ 280-l drum 9 3 m³ m³ Disposal containers Number Volume Container Type III m³ Container Type IV 183 1,354 m³ Container Type V 191 2,082 m³ Cast-iron container Type II m³ 722 4,088 m³ 50

51 3.9.8 Unterweser nuclear power plant Facility sections: E.ON Kernkraft GmbH Unterweser nuclear power plant Nuclear power plant > post-operational phase Storage facility Unterweser > unlimited licence On-site storage facility > storage limited to 40 years after first emplacement (18 June 2007) Spent fuel and vitrified waste from reprocessing Fuel assemblies Net mass Storage pool 413 FA 222 Mg HM Storage facility - 16 Castor V/ FA 164 Mg HM 717 FA 386 Mg HM Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Mixed waste 30.2 Mg 13.1 Mg 0.4 Mg 0.4 Mg 44.1 Mg 200-l drum 1, m³ 280-l drum m³ 400-l drum m³ 570-l drum m³ 1, m³ 51

52 Disposal containers Number Volume Concrete container Type I m³ Concrete container Type II m³ Container Type IV m³ Container Type V m³ Cast-iron container Type I m³ Cast-iron container Type II m³ m³ 52

53 3.9.9 Land collecting facility Lower Saxony Since 2002, the Land collecting facility Lower Saxony has been operated by Gesellschaft für Nuklear- Service (GNS). GNS accepts the raw waste intended for the Land collecting facility Lower Saxony and conditions it at its facility within the grounds of the research centre Forschungszentrum Jülich. After conditioning and packaging in line with the requirements for disposal, the waste is transported to the storage facility of the Eckert & Ziegler Nuclitec company in Leese and emplaced there. In addition, there are 4, liter drums in the Leese storage facility which were accepted by the Land collecting facility Lower Saxony prior to Old waste of the Land collecting facility Lower Saxony is furthermore stored together with waste of the Land collecting facilities of Bremen, Hamburg and Schleswig-Holstein at the Helmholtz-Zentrum Geesthacht Centre for Materials and Coastal Research GmbH in Geesthacht. 53

54 Leese external storage facility for radioactive waste Eckert & Ziegler Nuclitec GmbH Leese external storage facility for radioactive waste > unlimited licence 200-l drum 4,885 1,319 m³ 4,885 1,319 m³ Disposal containers Number Volume Container Type IV 5 37 m³ 5 37 m³ 54

55 Lingen Fuel fabrication plant Facility sections: Advanced Nuclear Fuels GmbH Fuel fabrication plant Fabrication plant for fuel assemblies > unlimited licence Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Liquid waste, organic Radiation sources 87.6 Mg 8.2 Mg 0.4 Mg 3.6 Mg 0.2 Mg Mg 55

56 Munster central collecting facility of the German Armed Forces (Bundeswehr) Bundeswehr Research Institute for Protective Technologies and NBC Protection (WIS) in Munster Central Collecting Point for Bundeswehr radioactive waste > unlimited licence Solid waste, inorganic Solid waste, organic Radiation sources Mg 0.6 Mg 0.2 Mg Mg 56

57 3.10 Sites in North Rhine-Westphalia Ahaus Transport Cask Storage Facility Ahaus GNS Gesellschaft für Nuklear-Service mbh, Brennelement- Zwischenlager Ahaus GmbH Transport Cask Storage Facility Ahaus Storage limited until 31 December 2036, storage licence according to 7 StrlSchV limited to 10 years after first emplacement (21 July 2010) Spent fuel and vitrified waste from reprocessing Storage facility - 3 Castor V/19-3 Castor V/ Castor THTR/AVR - 18 Castor MTR 2 Fuel assemblies 57 FA 156 FA 617,606 FA spheres 951 FA 1,164 FA and 617,606 FA spheres Net mass 29 Mg HM 26 Mg HM 7 Mg HM 2 Mg * 62 Mg HM 2 Mg* * Gross mass of fuel assemblies at the time of allocation for disposal. Apart from the total mass of the fuel, it also comprises the mass of non-separable cladding and construction materials. The separable top and bottom end pieces are not considered here. Disposal Containers Number Volume Container Type III m³ Container Type IV m³ Container Type V m³ 142 1,347 m³ 57

58 Duisburg Gesellschaft für Nuklearservice mbh GNS Gesellschaft für Nuklear-Service mbh Conditioning facilities > Licence limited until 31 December 2022 Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Mixed waste Mg 5.5 Mg 0.3 Mg Mg Mg 200-l drum m³ m³ 58

59 Gronau Uranium enrichment plant Facility sections: URENCO Deutschland GmbH Uranium enrichment plant Plant > unlimited licence Conditioning facilities > unlimited licence Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Liquid waste, organic 4.3 Mg 2.3 Mg < 0.1 Mg < 0.1 Mg 6.6 Mg 200-l drum m³ m³ Disposal containers Number Volume Container Type V 3 33 m³ 3 33 m³ 59

60 Hamm-Uentrop High temperature reactor nuclear power plant Hochtemperatur Kernkraftwerk GmbH (HKG) Thorium High Temperature Reactor (THTR) > in safe enclosure Solid waste, inorganic Solid waste, organic Mg 4.7 Mg Mg 200-l drum m³ Container Type IV 2 15 m³ m³ 60

61 Jülich Nuclear research reactor Facility sections: Arbeitsgemeinschaft Versuchsreaktor GmbH Jülich nuclear research reactor Research reactor > under decommissioning Solid waste, inorganic Solid waste, organic Mixed waste Mg 9.0 Mg 15.5 Mg Mg 200-l drum m³ m³ 61

62 Jülich Research centre Facility sections: Forschungszentrum Jülich GmbH Forschungszentrum Jülich Research reactor 2 > under decommissioning Storage facility > Clear-out ordered Waste storage facility > unlimited licence Conditioning facilities > unlimited licence Spent fuel and vitrified waste from reprocessing Fuel assemblies Storage facility Castor THTR/AVR approx. 290,000 AVR FA spheres approx. 290,000 AVR FA spheres Net mass 2 Mg HM 2 Mg HM Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Liquid waste, organic Mixed waste Mg 75.9 Mg 6.3 Mg 5.6 Mg 4,226.9 Mg 4,437.2 Mg 200-l drum m³ m³ Disposal containers Number Volume Container Type IV m³ Container Type IV (Type KfK) m³ Container Type V m³ m³ 62

63 Jülich Gesellschaft für Nuklear-Service mbh GNS Gesellschaft für Nuklear-Service mbh Conditioning facilities > unlimited licence Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Liquid waste, organic Mixed waste Radiation source Mg 18.1 Mg 1.1 Mg 0.5 Mg 7.4 Mg 1.4 Mg Mg 200-l drum 1, m³ 280-l drum 2 1 m³ 400-l drum 5 3 m³ Other 3 2 m³ 1, m³ Disposal containers Number Volume Concrete container Type II 1 1 m³ Container Type V m³ m³ 63

64 Jülich Land collecting facility North Rhine-Westphalia Cologne district government Land collecting facility North Rhine-Westphalia > unlimited licence Solid waste, inorganic 1.2 Mg 1.2 Mg 200-l drum m³ 280-l drum m³ 1, m³ 64

65 Würgassen nuclear power plant Facility sections: E.ON Kernkraft GmbH Würgassen nuclear power plant Nuclear power plant > under decommissioning UNS storage facility > in 7 AtG licence of the nuclear power plant included, albeit limited until 31 December 2033 Transport preparation hall > limited licence until 31 December 2045 Solid waste, inorganic Mixed waste 28.1 Mg 47.0 Mg 75.1 Mg 200-l drum 1, m³ 280-l drum 1, m³ 2, m³ Disposal containers Number Volume Concrete container Type II 3 4 m³ Container Type II m³ Container Type III 136 1,183 m³ Container Type V 124 1,352 m³ Cast-iron container Type II m³ 295 2,643 m³ 65

66 Krefeld Siempelkamp Nukleartechnik GmbH Siempelkamp Nukleartechnik GmbH CARLA melting facility > Licence limited until 31 December 2015 Solid waste, inorganic Solid waste, organic Mixed waste 2,147.8 Mg 1.1 Mg 5.8 Mg 2,154.7 Mg 200-l drum m³ m³ 66

67 3.11 Sites in Rhineland-Palatinate Ellweiler Land collecting facility Rhineland-Palatinate Landesamt für Umwelt, Wasserwirtschaft und Gewerbeaufsicht Rheinland-Pfalz Land collecting facility Rhineland-Palatinate unlimited licence Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Mixed waste Radiation sources 7.4 Mg 2.8 Mg 0.2 Mg Mg 0.6 Mg Mg 200-l drum 35 9 m³ 35 9 m³ 67

68 Mülheim-Kärlich nuclear power plant RWE Power AG Mülheim-Kärlich nuclear power plant > under decommissioning Solid waste, inorganic Solid waste, organic Liquid waste, inorganic 2.2 Mg 11.6 Mg 41.0 Mg 54.8 Mg 68

69 Mainz TRIGA Research Reactor Mainz Mainz University TRIGA Research Reactor Mainz > in operation, unlimited licence Spent fuel and vitrified waste from reprocessing Fuel assemblies Net mass Wet/dry storage facility 4 FA 764 g uranium 4 FA 764 g uranium 69

70 3.12 Sites in Saarland Elm-Derlen Land collecting facility Saarland Ministry of Environment and Consumer Protection Land collecting facility Saarland unlimited licence The waste of the Land collecting facility Saarland is currently being conditioned in compliance with the requirements for disposal by Eckert & Ziegler Nuclitec GmbH. 70

71 3.13 Sites in Saxony Rossendorf Land collecting facility Saxony VKTA Strahlenschutz, Analytik & Entsorgung Rossendorf e.v. Land collecting facility of the Free State of Saxony for radioactive waste > unlimited licence Liquid waste, inorganic Liquid waste, organic Mixed waste Radiation sources 1.3 Mg 1.1 Mg 76.0 Mg <0.1 Mg 78.4 Mg 200-l drum 17 5 m³ 280-l drum 11 4 m³ 28 9 m³ 71

72 Rossendorf VKTA Strahlenschutz, Analytik & Entsorgung Rossendorf e. V. VKTA Strahlenschutz, Analytik & Entsorgung Rossendorf e. V. Research centre Research centre with the Rossendorf research and zeroload reactors, et al. > under decommissioning Facility sections: Rossendorf storage facility > unlimited licence Conditioning facilities > unlimited licence Mixed waste Mg Mg 200-l drum 29 8 m³ Concrete container Type I m³ Cast-iron container Type II 4 5 m³ m³ Disposal containers Number Volume Concrete container Type I m³ Container Type IV (Type KfK) m³ m³ 72

73 3.14 Sites in Saxony-Anhalt Land collecting facility Saxony-Anhalt The radioactive waste of the Land collecting facility Saxony-Anhalt is stored together with the waste of the Land collecting facility Thuringia at the Land collecting facility Saxony in Rossendorf. 73

74 3.15 Sites in Schleswig-Holstein Geesthacht Helmholtz-Zentrum Geesthacht Centre for Materials and Coastal Research GmbH Facility sections Helmholtz-Zentrum Geesthacht Centre for Materials and Coastal Research GmbH Research centre Preparation hall > limited until 8 February 2017 Storage facility for components of the nuclear vessel "Otto Hahn" for scientific follow-up examinations (HAKONA) > unlimited licence Collecting facility > unlimited licence Solid waste, inorganic 3.2 Mg 3.2 Mg 200-l drum m³ 280-l drum m³ 400-l drum m³ 570-l drum 12 9 m³ Other 3 3 m³ 1, m³ 74

75 Geesthacht Land collecting facility Helmholtz-Zentrum Geesthacht Centre for Materials and Coastal Research GmbH Land collecting facility Schleswig-Holstein, Bremen, Hamburg, Niedersachsen > unlimited licence 200-l drum m³ 280-l drum 4 2 m³ 400-l drum 14 7 m³ m³ 75

76 Brokdorf nuclear power plant Facility sections: Kernkraftwerk Brokdorf GmbH & Co. OHG Brokdorf nuclear power plant Nuclear power plant > in operation, power operation licence expires on 31 December 2021 On-site storage facility > storage limited to 40 years after first emplacement (5 March 2007) Spent fuel and vitrified waste from reprocessing Fuel assemblies Net mass Storage pool 452 FA 245 Mg HM Storage facility - 26 Castor V/ FA 267 Mg HM 946 FA 512 Mg HM Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Liquid waste, organic 42.9 Mg 27.7 Mg 24.3 Mg 5.6 Mg Mg 400-l drum 1 1 m³ 1 1 m³ 76

77 Brunsbüttel nuclear power plant Facility sections: Kernkraftwerk Brunsbüttel GmbH & Co. ohg Brunsbüttel nuclear power plant Nuclear power plant > post-operational phase On-site storage facility > regulatory action for storage limited until 16 January 2018 Spent fuel and vitrified waste from reprocessing Fuel assemblies Net mass Reactor pressure vessel 517 FA 90 Mg HM Storage facility - 9 Castor V/ FA 73 Mg HM 965 FA 163 Mg HM Solid waste, inorganic Solid waste, organic Liquid waste, inorganic Mixed waste Mg 65.7 Mg 31.3 Mg 21.0 Mg Mg 200-l drum 2 1 m³ 280-l drum m³ m³ Disposal containers Number Volume Concrete container Type I m³ Concrete container Type II m³ Container Type IV m³ Container Type V m³ Container Type VI m³ Cast-iron container Type II m³ 914 2,209 m³ 77

78 Krümmel nuclear power plant Facility sections: Kernkraftwerk Krümmel GmbH & Co. ohg Krümmel nuclear power plant Nuclear power plant > post-operational phase On-site storage facility > storage limited to 40 years after first emplacement (14 November 2006) Spent fuel and vitrified waste from reprocessing Fuel assemblies Net mass Storage pool 1,094 FA 194 Mg HM Storage facility - 19 Castor V/ FA 175 Mg HM 2,082 Fa 369 Mg HM Solid waste, inorganic Solid waste, organic Mixed waste 7.2 Mg 22.3 Mg 3.1 Mg 32.6 Mg 200-l drum 1, m³ 280-l drum 1 <1 m³ 400-l drum m³ 1, m³ 78

79 3.16 Sites in Thuringia Land collecting facility Thuringia The radioactive waste of the Land collecting facility Thuringia is stored together with the waste of the Land collecting facility Saxony-Anhalt in the Land collecting facility Saxony in Rossendorf. 79

80 3.17 Sites abroad Processing and conditioning of radioactive waste that has arisen in Germany may also be carried out abroad. The radioactive waste arising in this process is returned to the waste originators and disposed of in Germany. The most important service providers in this respect are waste treatment plants in Sweden, France, and the USA. Solid waste, inorganic Solid waste, organic Liquid waste, organic Mixed waste 2,023.7 Mg 26.7 Mg 3.2 Mg 23.3 Mg 2,076.9 Mg 200-l drum m³ m³ 80

81 4. Disposed-of radioactive waste In the former GDR, construction of the Morsleben Repository for Radioactive Waste (ERAM) was begun in Following a test phase, emplacement operation took place initially under a licence that was granted in 1981 and limited to five years; in 1986, an unlimited operating licence for the acceptance and disposal of low- and intermediate-level waste was granted. After German reunification, the facility became the responsibility of the Federal Republic of Germany, and the Federal Office for Radiation Protection (BfS) became the operator of the disposal facility. From 1994 until September 1998, the ERAM took in low- and intermediatelevel waste from the entire German territory. During the whole period from 1971 until 1998, a total waste volume of 36,754 m³ was disposed of there. The waste in question comprises solid as well as solidified waste and 6,621 radiation sources with a total activity in the order of magnitude of Bq. The radioactive waste emplaced is generally packed in standardised containers, e.g. 200-l to 570-l drums and cylindrical concrete containers. Besides the radioactive waste emplaced, sealed cobalt radiation sources, several caesium radiation sources and small amounts of solid intermediate-level waste in seven special containers (steel cylinders) with a volume of 4 l each disposed of in level boreholes as well as one 280-l drum containing radium-226 waste have been emplaced. The sealed radiation sources have not been treated any further and are only packed in small welded containers. According to 57a of the Atomic Energy Act (AtG), which was added due to the Unification Treaty, and as a result of the amendment of the AtG of 6 April 1998, the permanent operating licence for the ERAM continued to be valid until 30 June 2005 as licence (plan approval) according to 9b AtG. With the AtG amendment of 22 April 2002, the limit on the continued validity of the permanent operating licence application ceased to apply with the provison that as of 27 April 2002, the acceptance of further radioactive waste or its emplacement for the purpose of disposal or the acceptance of further nuclear fuels or other radioactive substances for the purpose of safekeeping or storage would no longer be permitted. Since the end of emplacement operation, the licensing (plan approval) procedure for the decommissioning of the ERAM has been pursued. An application was also made as part of this procedure to eventually dispose of the stored waste in this facility. 81

82 5. Radioactive waste prediction For the activities in connection with the planning of disposal facilities it is necessary to make predictions of the expected volume of waste. All predictions include the radioactive waste that has already arisen to this date. 5.1 Predicted amounts of spent fuel and waste from reprocessing In all, the assumption is that about 10,500 Mg HM in the form of spent fuel assemblies will be generated in nuclear power plants and will have to be disposed of in the Federal Republic of Germany. This amount will be stored in about 1,100 storage casks. The amounts of waste expected from reprocessing that will have to be disposed of in the Federal Republic of Germany are shown in Table 5.1. Table 5.1: Prediction of the amounts of waste expected from reprocessing that will have to be disposed of in the Federal Republic of Germany (as at 31 December 2014) Canisters Containers Vitrified High-level radioactive waste from France (CSD-V) 3, Vitrified intermediate-level radioactive waste from France (CSD-B) Intermediate-level radioactive waste from France compacted under high pressure (CSD-C) Vitrified high-level radioactive waste from the United Kingdom (UK- HAW) Vitrified high-level radioactive waste from reprocessing at Karlsruhe (HAW-WAK) 4, Total 7, From the research, development and demonstration reactors, an amount within the range of 10 to 12 Mg HM is expected. As regards the BER II in Berlin, contracts exist governing the return shipment of spent fuel to the country of origin. 5.2 Predicted amounts of other radioactive waste For the prediction of the volume of other radioactive waste, the waste originators were asked to provide data. The information provided by the waste originators also includes the predicted volumes of waste that will arise in connection with the decommissioning and 82

83 dismantling of nuclear facilities, respectively. The data in question are planning levels which are subject to uncertainties. The figures provided by the waste originators were translated into the numbers of containers suitable for emplacement in the Konrad repository in order to be able to indicate the waste package volume. Regarding the Land collecting facilities, the estimate was carried out by the Federal Office for Radiation Protection (BfS) on the basis of the volume of waste of the past years. The time pattern of the cumulated amount of radioactive in the future as it is expected by the waste originators is shown in Fig. 5.1; the waste to be retrieved from the Asse II mine is not included. It becomes clear from this figure that no further large amounts of waste are expected to arise from the decommissioning of the nuclear power plants after the year Figure 5.1: The time pattern of the cumulated amount of radioactive waste with negligible heat generation as it is expected by the waste originators and which according to the valid license (plan approval) are to be emplaced in the Konrad disposal facility, shown as waste packages volume until the year 2080, * this also includes the waste volumes of the federally-owned Energiewerke Nord GmbH 5.3 Asse II mine In the Federal Republic of Germany, disposal began with the rededication of the Asse II former salt mine in Between 1967 and the end of 1978, about 47,000 m³ of low- and intermediate-level waste were emplaced here in different types of containers. The current inventory lists indicate that the following waste containers were emplaced: 83

84 124,494 packages as low-level radioactive waste with a total activity of about Bq (as at 31 December 2012). According to the current state of knowledge, 14,779 of them are so-called "Lost Concrete Shieldings" (VBA) containing waste with higher activity. Altogether, the containers contain about 80 % of the total activity in the Asse II mine and are distributed over eleven chambers at the 750-m level and one chamber at the 725-m level. 1,293 drums holding intermediate-level waste with a total activity of about Bq (as at 31 December 2012). These represent about 20 % of the total activity and are stored at the 511-m level. Additionally, eight drums with lowlevel radioactive waste are also stored there. The latter were emplaced to test a new shielded cask type. The low-level radioactive waste emplaced contains solidified or dried waste, such as evaporator concentrates, filter residues, sludge, ion-exchanger resins, furthermore solid waste such as scrap, rubble and mixed waste. As regards the intermediate-level radioactive waste, metal scrap, filters and solidified waste was emplaced. According to the current state of knowledge, no high-level radioactive waste was emplaced in the Asse II mine. Eight drums filled with intermediate-level radioactive waste from the research centre Forschungszentrum Jülich contain parts of new or briefly irradiated fuel rod segments or AVR fuel spheres with, in some cases, enriched uranium. Since 1988, there has been a continuous inflow of groundwater from the overburden into the mine. At the same time, the stability of the mine started to deteriorate successively due to the pressure of the overlying overburden and the decreasing load-carrying capacity of the mine workings. According to 57b AtG, the Asse II mine must therefore be closed immediately. Closure is to take place once the radioactive waste has been retrieved. The concept for the retrieval of the radioactive waste provides for recovering all the waste, to transport it above ground in transport containers and to condition it there in order to dispose of it then. Retrieval according to 57b AtG shall be discontinued if its performance is not acceptable for the population and the employees for radiological or other safetyrelevant reasons. The retrieval is planned on the basis of the assumption that the entire waste as well as an additional amount of contaminated salt breeze will have to be treated and stored. Current estimates reckon with at least 90,000 Mg of unconditioned waste and a waste volume of conditioned waste of approx. 175,000 to 220,000 m³ for later disposal. 84