R&D Category: Decontamination, decommissioning, disassembly
10 documents found
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Decladding of fast breeder reactor fuel elements with lattice spaces. Die Zerlegung von Schnellbrueter-Brennelementen mit Gitterabstandshaltern
Bestenreiner, G. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.))INIS-mf--10197 - German - 1981
Abstract: The method of decladding and desintegration of fuel rods is already applicable. The paper deals with the marginal conditions relevant for the desintegration (deformations, decay heat, decontamination of fuel elements), R and D work performed by INTERATOM so far and related results. The resulting courses of desintegration for SNR-300 Mk Ia or Mk II fuel elements and first practical experience made with the desintegration of KNK-II fuel elements at the KfK's hot cells are discussed. Finally a desintegration device for SNR-300 first core fuel elements designed in accordance with the aforesaid results is presented. (orig./DG)
Key words: fuel assembly dismantling;knk-2 reactor;mechanical decladding;reprocessing;snr reactor;spent fuel elements
Components Category: --Fuel assemblies
display the document: 17054134.pdf
Fuel reprocessing of the first failed KNK-II fuel element in MILLI. Die Wiederaufarbeitung von Brennstoff aus dem ersten defekten KNK II-Brennelementen in der MILLI
Bleyl, H.J. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Heisse Chemie)KFK--3278 - German - 1982
Abstract: In MILLI reprocessing of fuel from 32 KNK II-pins was carried out. 3 extraction cycles were applied: co-decontamination, U-/Pu-separation and purification of uranium. The products were shipped to refabrication of KNK II fuel by Nukem and Alkem companies. (orig.)
Key words: fuel element failure;fuel pins;knk-2 reactor;purex process;solvent extraction
Components Category: --Fuel and cladding
display the document: 13695220.pdf
Experience on fuel recycling. Erfahrungen zur Brennstoff-Rezyklierung
Schneider, V.;Druckenbrodt, W.G. (Alpha Chemie und Metallurgie G.m.b.H.)KFK--3278 - German - 1982
Abstract: The plutonium of the second generation out of the KNK-reactor will be converted at the fuel fabrication by ALKEM by the Au/PuC process. The preliminary tests for the fabrication have been finished and two batches were converted. Up to now the results show no principal difficulties. (orig.)
Key words: fuel fabrication plants;knk-2 reactor;plutonium recycle
Components Category: --Fuel and cladding
display the document: 13695223.pdf
Sodium removal from fuel elements. Die Entfernung des Natriums von Brennelementen
Stade, K.C.;Breitlaender, H. (Kernkraftwerk-Betriebsgesellschaft m.b.H., Eggenstein-Leopoldshafen (Germany, F.R.));Stamm, H.H. (Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Radiochemie)KFK--3278 - German - 1982
Abstract: The steam-nitrogen method was used for the sodium removal from undamaged KNK-I fuel elements. 66 fuel bundles (= 2904 fuel pins) with an average burn-up of 5800 MWd/tsub(HM) were cleaned using this method, four to six months after the final shut-down, during the time from December 1974 to February 1975. The sodium removal was complete. No defects originated from the cleaning procedure. The sodium removal from KNK-II and SNR-300 fuel without cladding failures will be accomplished by the same process. At KNK-II, the existing plant has to be modified before KNK-II elements may be treated. So far, two defective fuel elements (burn-up 17400 MWd/tsub(HM), and 48000 MWd/tsub(HM), respectively) have been removed from the KNK-II core. The limited sodium removal achieved by blowing with hot argon was sufficient for the following dismantling of these bundles in the KfK hot cell laboratories. (orig.)
Key words: argon;blowers;fuel washers;knk-2 reactor;purification;sodium;spent fuel elements
Components Category: --Fuel assemblies
display the document: 13696678.pdf
Conceptual study on the interim underwater storage of KNK-II fuel elements. Konzeptstudie zur Zwischenlagerung von KNK II-Brennelementen unter Wasser
Wasinger, K. (Kraftwerk Union A.G., Offenbach am Main (Germany, F.R.))KFK--3278 - German - 1982
Abstract: For the intermediate storage of KNK II-fuel in water, Kraftwerk Union AG designed a 'wet storage facility for KNK II-fuel' by order of Kernforschungszentrum Karlsruhe. This wet storage facility is designed as At Reaktor (AR) storage by what the existing infrastructure of KNK II and KfK can be used. The storage of the fuel elements takes place in one storage pool equipped with compact storage racks. The maximum storage capacity is 10 cores of the KNK II. Cooling of the pool water is performed by a cooling system with natural recirculation which transfers the decay heat to the surrounding air. (orig.)
Key words: feasibility studies;knk-2 reactor;planning;spent fuel elements;spent fuel storage;storage;underwater
Components Category: -Fuel storage
display the document: 13696682.pdf
Conceptual design for interim storage of KNK II-fuel elements in a block storage facility. Konzeptstudie zur Zwischenlagerung von KNK II-Brennelementen in einem Blocklager
Arntzen, P.;Gasch, A. (Nuklear-Chemie und -Metallurgie G.m.b.H. (NUKEM), Hanau (Germany, F.R.))KFK--3278 - German - 1982
Abstract: The storage facility is used for aircooled interim storage of irradiated KNK II-fuel elements from 10 reactor core-exchanges. The elements are canned before they are introduced into the storage facility. The heat produced by these elements is dissipated to the atmosphere via an indirect aircooling system. This cooling system is inherent safe and selfregulating. All codes, standards and regulations, relevant for design, are taken into consideration. The storage facility will be constructed on the KNK-site. The storage plant contains an extreme load influence from outside-safe storage part and a non extreme load influence from outside-safe reception and utility-part. (orig.)
Key words: feasibility studies;knk-2 reactor;planning;spent fuel elements;spent fuel storage
Components Category: -Fuel storage
display the document: 13696683.pdf
Concept on the interim storage of KNK-2 spent fuel elements in transport or storage containers. Konzept zur Zwischenlagerung bestrahlter KNK-II-Brennelemente in Transport-/Lagerbehaeltern
Bergmann, W.;Dries, G.;Laug, R. (Transnuklear G.m.b.H., Hanau (Germany, F.R.))KFK--3278 - German - 1982
Abstract: The intented side for a container store is an area on the KfK premises. The immediate vicinity of the KNK II reactor was chosen in order to use the infrastructure, the physical protection and nuclear surveillance of that reactor. Delivery of the total of 315 fuel elements (= 10 core loads) for storage will occur biannually over a period of 20 years. It is proposed to load the containers with a mixture of 7 encapsulated fuel elements, of which a maximum of 2 will be test elements. The container is designed to prevent the release of radioactive materials and to guarantee subcriticality and the removal of decay heat in all possible incidents. The dose rate at the surface of the container is less than 20 mrem/h. Removal of the decay heat is assured by natural convection. The containers will be checked individually for leaktightness. A collective conduit keeps the KNK control room informed about the storage conditions. The storage buildings is divided into two main areas: the storage area, containing the 45 transport and storage containers positioned vertically by means of a 400 kN gantry crane, and the container reception area, containing the lorry entrance, the maintenance room, the measuring laboratory, and an installation room. The storage area is a control area, and the container reception area a surveillance area. (orig./HP)
Key words: containers;knk-2 reactor;spent fuel storage;transport
Components Category: -Fuel storage
display the document: 13696684.pdf
Technical meeting on 'Operational and decommissioning experience with fast reactors'. Working material
International Atomic Energy Agency, Technical Working Group on Fast Reactors, Vienna (Austria)IAEA-TM--25332 - English - 2002
Abstract: For three decades, several countries had large and vigorous fast breeder reactor development programs. In most cases, fast reactor development programs were at their peaks by 1980. Fast test reactors [Rapsodie (France), KNK-II (Germany), FBTR (India), JOYO (Japan), DFR (UK), BR-10, BOR-60 (Russia), EBR-II, Fermi, FFTF (U.S.A.)] were operating in several countries, with commercial size prototype reactors [Phenix, Superphenix (France), SNR-300 (Germany), MONJU (Japan), PFR (UK), BN-350 (Kazakhstan), BN-600 (Russia)] just under construction or coming on line. From that time onward, fast reactor development in general began to decline. By 1994 in the USA, the Clinch River Breeder Reactor (CRBR) had been cancelled, and the two fast reactor test facilities, FFTF and EBR-II had been shutdown - with EBR-II permanently, and FFTF in a standby condition. Thus, effort essentially disappeared for fast breeder reactor development. Similarly, programs in other nations were terminated or substantially reduced. In France, Superphenix was shut down at the end of 1998. SNR-300 in Germany was completed but not taken into operation, and KNK-II was permanently shut down in 1991 after 17 years of operation, and is scheduled to be dismantled by 2004. In the UK, PFR was shut down in 1994. BN-350 in Kazakhstan was shut down in 1998. It is difficult to argue that fast breeder reactors will be built in the near term when no commercial market exists and there is a plentiful supply of cheap uranium. Nevertheless, it is reasonable to assume that, were nuclear energy to remain an option as part of the long-term world energy supply mix, meeting the sustainability requirements vis-a-vis natural resources and long-lived radioactive waste management will require deploying systems involving several reactor types and fuel cycles operating in symbiosis. Apart from cost effectiveness, simplification, and safety considerations, a basic requirement to these reactor types and fuel cycles will be flexibility to accommodate changing objectives and boundary conditions. This flexibility can only be assured with the deployment of the fast neutron spectrum reactor technology, and reprocessing. At the same time that the interest in the fast reactor waned, also the retirement of many of the developers of this technology reached its peak, between 1990 and 2000, and hiring diminished in parallel. Moreover, R and D programs are being discontinued, and facilities falling in disuse. Under these circumstances, the loss of the fast reactor knowledge base should be taken seriously. One particularly important aspect of this knowledge base is given by the accumulated operational experience. The participants in the 33rd Annual Meeting of the International Working Group on Fast Reactors, 'Technical Committee Meeting on Liquid Metal Fast Reactor Developments' (Vienna, 16-18 May 2000), recommended holding a technical meeting (TM) on 'Feedback from Operational and Decommissioning Experience with Fast Reactors'. At the 34th Annual Meeting of the Technical Working Group on Fast Reactors, 'Technical Committee Meeting on Review of National Programmes on Fast Reactors and ADS' (Almaty/Kurchatov City, Kazakhstan, 14-18 May 2001), it was further recommended to launch a Coordinated Research Program (CRP) on 'Generalisation and Analyses of Operational Experience with Fast Reactor Equipment and Systems' (Preserve Fast Reactor Operation and Decommissioning Experience). It was agreed to structure the TM in such a way that, apart from providing an information exchange opportunity, it would also prepare the grounds for the CRP. The scope of the TM was to provide a global forum for information exchange on fast reactor operational and decommissioning experience. The objectives of the TM were to: exchange detailed technical information on fast reactor operation and/or decommissioning experience with DFR, PFR (UK). KNK-II (Germany). Rapsodie, Phenix, Superphenix (France). BR-10, BOR-60, BN-600 (Russia). BN-350 (Kazakhstan). SEFOR, EBR-II, Fermi, FFTF (U.S.A.). FTBR (India). JOYO, MONJU (Japan). Present the status of the work concerning the knowledge preservation efforts related to the experience accumulated in the various member states from the operation and decommissioning of fast reactors. Start the preparation of the planned Co-ordinated Research Project (CRP) on 'Generalization and Analyses of Operational Experience with Fast Reactor Equipment and Systems' (narrow down scope and objectives of the CRP, propose a detailed work plan)
Key words: beloyarsk-3 reactor;bor-60 reactor;clinch river breeder reactor;coordinated research programs;design;dfr reactor;ebr-2 reactor;enrico fermi-1 reactor;fftf reactor;fuel cycle;iaea;international cooperation;joyo reactor;knk-2 reactor;leading abstract;liquid metals;monju reactor;phenix reactor;planning;radioactive waste management;rapsodie reactor;reactor decommissioning;reactor maintenance;reactor operation;reactor shutdown;reactor technology;snr reactor;super phenix reactor
Components Category: any or undefined
display the document: 34029219.pdf
Concept for dismantling the reactor vessel and the biological shield of the compact sodium-cooled nuclear reactor facility (KNK)
Hillebrand, I. (Forschungszentrum Karlsruhe (Germany));Benkert, J. (Westinghouse Reaktor (Germany))IAEA-TM--25332 - English - 2002
Abstract: The Compact Sodium-cooled Nuclear Reactor Facility (KNK) was an experimental nuclear power plant of 20 MW electric power erected on the premises of the Karlsruhe Research Center. The plant was initially run as KNK I with a thermal core between 1971 and 1974 and then, between 1977 and 1991, with a fast core as the KNK II fast breeder plant. Under the decommissioning concept, the plant is to be decommissioned completely to green field conditions at the end of 2005 in ten steps, i.e. under the corresponding ten decommissioning permits. To this day, nine decommissioning permits have been issued, the first one in 1993 and the most recent one, number nine, in 2001. The decommissioning and demolition activities covered by decommissioning permits 1 to 7 have been completed. Under the 8th Decommissioning Permit, the components of the primary system and the rotating reactor top shield are to be removed by late 2001. Under the 9th Decommissioning Permit, the reactor vessel with its internals, the primary shield, and the biological shield are to be dismantled. The residual sodium volume in the reactor vessel was estimated to amount to approx. 30 1. The maximum Co-60 activation is on the order of 107-108 Bq/g. The maximum dose rate in the middle of the vessel was measured in April 1997 to be 55 Sv/h. The difficulty involved especially in dismantling KNK, on the one hand, is posed by the residual sodium in the plant, which determines the choice of neither wet nor thermical techniques to be used in disassembly. Another difficulty is caused by the depth of activation by fast neutrons, as a result of which not only the reactor vessel proper, but also the entire primary shield (60 cm of grey cast iron) and large parts of the biological shield must be disassembled and disposed of under remote control. (author)
Key words: activity levels;biological shields;cast iron;knk-2 reactor;licensing procedures;planning;reactor decommissioning;reactor dismantling;reactor vessels;remote control
Components Category: Reactor components
display the document: 34029242.pdf
Concept for dismantling the reactor vessel and the biological shield of the compact sodium-cooled nuclear reactor facility (KNK) (viewgraphs)
Pfeifer, W.;Hillebrand, I. (Forschungszentrum Karlsruhe GmbH (Germany))IAEA-TM--25332 - English - 2002
Abstract: This presentation covers the following: Time Schedule Decommissioning KNK. Steps of Dismantling and Decommissioning Procedure. It shows: Packaging of the Primary Sodium (1997). Disassembly of the Turbine Hall (1998). Break through the Wall to the Primary Purification Cell (07/2000). Disassembly of the Ceiling above the Primary Cell (finished 02/2000). Semi manual dismantlement of the heat exchanger tube bundle. Cutting thick-walled components with the band saw. Transportation of the Primary Sodium Dump Tank (03/2001). It describes: Concept for Dismantling of the Reactor Vessel Lid. Removing of the Large and the small Rotating Plug Removing of the Large Rotating Plug from the reactor vessel. Shut of the reactor vessel. View into the Storage for Fuel Elements after Removal of the Lid (06/2001). Video Inspection of the Storage for Fuel Elements (05/2000). Fuel Storage. Vessel cleaning. Transportation Logistics. Dismantling the Reactor Vessel. Disassembly of the primary shield, of the biological Shield. Decontamination of the site. Radioactive Waste Processing. And the costs for the removal of the reactor-vessel, the primary shield and the biological shield. Important Points for a Successful Decommissioning recommended are: Remove the fuel as soon as possible. Minimize surveillance and maintenance for reducing the costs. Start decommissioning as long as there are workers with operation know-how in the company. Learn from decommissioning of the secondary system for using the right methods for the primary system. Do not change the staff, even if they are contractors
Key words: biological shields;cost;decontamination;knk-2 reactor;licensing regulations;radioactive waste processing;reactor decommissioning;reactor dismantling;reactor vessels;sodium
Components Category: any or undefined
display the document: 34029243.pdf