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Störfall im AKW Krümmel

Eine zweite lose Sicherungsmutter im Bereich der Steuerstäbe im Reaktordruckbehälter wird entdeckt. Ein "Befund mit Hinweis auf systematische Fehler" räumen die Betreiber ein. (Quelle: Geenpeace)

Störfall im AKW Krümmel

Während Revisionsarbeiten, zu denen der Atommeiler seit dem 19.07. abgeschaltet war, wurde das Lösen einer Sicherungsmutter an den Steuerstäben im Reaktordruckbehälter entdeckt. Auch das sie haltende Gewinde war zerstört. Zuvor hatten Sonderprüfungen Hinweise auf erneute Risse an Rohrleitungen im Speisewasser ergeben. (Quelle: Greenpeace)

Atomkraftwerk Isar 1 erhält Rückbaugenehmigung

Erstmals seit dem Atomausstiegsbeschluss von 2011 hat ein AKW in Deutschland eine Rückbaugenehmigung erhalten. Für den Abriss eines Atomkraftwerkes ist eine atomrechtliche Stilllegungsgenehmigung erforderlich, die auf einem komplexen Genehmigungsverfahren beruht. Als erste Behörde hat das Bayerische Staatsministerium für Umwelt und Verbraucherschutz mit Zustimmung des BMUB der Preussen Elektra GmbH am 17. Januar 2017 eine Genehmigung für eine Stilllegung und zum Abbau der Anlage Isar 1 (KKI 1) erteilt. Mit dieser wird der Abbau aller Anlagenteile gestattet, die nicht der Abbauphase 2 (Reaktordruckbehälter und Biologischer Schild) zugeordnet sind. Nach derzeitiger Planung soll die Abbauphase 1 bis zum Jahr 2023 und die Abbauphase 2 bis zum Jahr 2026 abgeschlossen sein.

Antrag nach § 7 Abs. 3 AtG zum weiteren Abbau der Anlage, Phase 2 (2. AG) KKI-1-GEN-2020-01

Am 04.05.2012 hat die damalige E.ON Kernkraft GmbH, seit Juni 2016 PreussenElektra GmbH, einen Antrag nach § 7 Abs. 3 AtG zur Stilllegung und zum Abbau des Kernkraftwerks Isar 1 (KKI 1) beim Bayerischen Staatsministerium für Umwelt und Verbraucherschutz (StMUV) gestellt. Zu diesem Antrag erteilte das StMUV am 17.01.2017 die „Erste Genehmigung nach § 7 Absatz 3 des Atomgesetzes zur Stilllegung und zum Abbau des Kernkraftwerks Isar 1“ (1. SAG), die sich auf das erste von zwei Teilvorhaben der insgesamt geplanten Maßnahmen zur Stilllegung und zum Abbau des KKI 1 bezieht. Am 31.01.2020 hat die PreussenElektra GmbH einen Antrag nach § 7 Abs. 3 AtG zum weiteren Abbau des KKI 1, Phase 2 (2. AG), beim StMUV gestellt. Dieser Antrag bezieht sich auf die Gestattung des Abbaus des Reaktordruckbehälters und des Biologischen Schilds sowie den Umgang mit sonstigen radioaktiven Stoffen aus dem Kernkraftwerk Isar 2 in den Einrichtungen der Reststoffbearbeitung und auf den Pufferlagerflächen des KKI 1. Alle übrigen im Rahmen des weiteren Abbaus des KKI 1 erforderlichen Tätigkeiten erfolgen im Rahmen der Gestattung der weiterhin gültigen 1. SAG.

Antrag nach § 7 Abs. 3 AtG zum weiteren Abbau der Anlage KKG, Phase 2 (2. AG)

Am 28.03.2014 hat die damalige E.ON Kernkraft GmbH, seit Juni 2016 PreussenElektra GmbH, einen Antrag nach § 7 Abs. 3 AtG zur Stilllegung und zum Abbau des Kernkraftwerks Grafenrheinfeld (KKG) beim Bayerischen Staatsministerium für Umwelt und Verbraucherschutz (StMUV) gestellt. Zu diesem Antrag erteilte das StMUV am 11.04.2018 die „Erste Genehmigung nach § 7 Absatz 3 des Atomgesetzes zur Stilllegung und zum Abbau des Kernkraftwerks Grafenrheinfeld“ (1. SAG), die sich auf das erste von zwei Teilvorhaben der insgesamt geplanten Maßnahmen zur Stilllegung und zum Abbau des KKG bezieht. Am 17.12.2019 hat die PreussenElektra GmbH einen Antrag nach § 7 Abs. 3 AtG zum weiteren Abbau des KKG, Phase 2 (2. AG), beim StMUV gestellt. Dieser Antrag bezieht sich auf die Gestattung des Abbaus des Reaktordruckbehälters und des Biologischen Schilds. Alle übrigen im Rahmen des weiteren Abbaus des KKG erforderlichen Tätigkeiten erfolgen im Rahmen der Gestattung der weiterhin gültigen 1. SAG.

Stilllegung und Abbau des Kernkraftwerkes ISAR 2 (KKI 2)

Die PreussenElektra GmbH (Tresckowstraße 5, 30457 Hannover) hat mit Schreiben vom 1. Juli 2019 die Genehmigung zur Stilllegung und zum Abbau des Kernkraftwerks Isar 2 (KKI 2) nach § 7 Abs. 3 Atomgesetz (AtG) in der Fassung der Bekanntmachung vom 15. Juli 1985 (BGBl. I S. 1565), zuletzt geändert durch Artikel 3 des Gesetzes vom 20. Mai 2021 (BGBl. I S. 1194), beantragt. Die Mitgenehmigungsinhaberin Stadtwerke München GmbH (Emmy-Noether-Straße 2, 80992 München) ist diesem Antrag mit Schreiben vom 17. Juli 2019 beigetreten. Die Anlage KKI 2 umfasst einen Druckwasserreaktorblock am Standort Dammstraße, 84051 Essenbach. Der Antrag ist auf die Erteilung einer Ersten Genehmigung nach § 7 Abs. 3 AtG gerichtet. Das zugrundeliegende Vorhaben beinhaltet unter Einbeziehung der insgesamt geplanten Maßnahmen zu Stilllegung und Abbau von KKI 2 die erste Abbauphase mit dem Abbau von Anlagenteilen des KKI 2, während sich noch Brennstoff im Brennelementlagerbecken des KKI 2 befindet. In einer zweiten und separat zu genehmigenden Abbauphase sollen später auch der Abbau des Reaktordruckbehälters und des biologischen Schilds erfolgen und die Anlage KKI 2 schließlich nach erfolgter Dekontamination und Freigabe nach den Regelungen des Strahlenschutzrechts aus der atomrechtlichen Überwachung entlassen werden.

Investigations of viscous venting and treatment of releases

Das Projekt "Investigations of viscous venting and treatment of releases" wird vom Umweltbundesamt gefördert und von Technische Universität Hamburg-Harburg, Forschungsschwerpunkt Bautechnik und Meerestechnik, Arbeitsbereich Strömungsmechanik durchgeführt. General Information: Polymerization reactors are widely used throughout the industrialized world in the production processes of many common materials such as polystyrene, polyvinylchloride (PVC) and polyacrylates (e.g. plexiglass). A survey carried out in 1990 by the UK Health and Safety Executive showed that, over period up to 1987, an average of five serious industrial incidents due to runaway polymerization reactions occurred every two years. Against this background, and in the framework of reduction of risks to human health and the environment, many of Europe's leading chemical companies have expressed a strong need to improve the modelling capability available for the design of emergency pressure relief systems for such reactors. The present proposal is focussed on this area and is characterised by a problem-solving approach. Many runaway reactions that are of greatest concern are those that involve highly-viscous multiphase fluids (viscosities typically greater than 1000cP). There are considerable uncertainties in specifying the required safety valve and pipe sizes to handle such fluids so that, if activated, the emergency pressure relief systems will be able to discharge reactor contents at a rate that will prevent a dangerous build-up of pressure and temperature in the reactor vessel. However, the basic hindrance to the development of improved modelling techniques is the extremely limited experimental database on the flow of highly-viscous multiphase fluids (reacting and non-reacting) in vessels, safety valves and piping. In view of the variety of polymerization processes, it is necessary for this project to adopt a generic approach, i.e. to perform experiments that allow high-viscosity effects to be studied systematically and, on this basis, to develop generalised physical models for emergency pressure relief system design. The INOVVATOR Project has the following objectives: 1. To complement the very limited experimental database on high-viscosity multiphase flows by performing a number of experiments designed to fill certain critical knowledge gaps such as liquid-vapour distribution in reactor vessels, the pressure drop characteristics of safety valves and associated pipe systems and corresponding mass discharge rates. 2. To create a computer database containing these and other available experimental data related to high- viscosity multiphase flows. 3. To develop or improve the modelling technology for highly-viscous flows used in the design of emergency pressure relief systems. This would be validated against the above database. 4. To exploit and disseminate the products of the project, e.g. by publications, presentations at industrial working groups and by incorporating the improved models in existing design software. The resources necessary to achieve these objectives demand a trans-national approach. ... Prime Contractor: Commission of the European Communities, Institute of Systems, Informatics and Safety; Barasso; Italy.

Pilot dismantling of the KRB-A BWR. Dismantling of contaminated components of the reactor building and to activated internals of the reactor pressure vessel - Development and application of concrete sawing and melt encapsulation (Onion packa)

Das Projekt "Pilot dismantling of the KRB-A BWR. Dismantling of contaminated components of the reactor building and to activated internals of the reactor pressure vessel - Development and application of concrete sawing and melt encapsulation (Onion packa)" wird vom Umweltbundesamt gefördert und von Kernkraftwerk RWE-Bayernwerk GmbH durchgeführt. Objective: The prototype Boiling Water Reactor Gundremmingen A (KRB-A BWR) of the Kernkraftwerk RWE-Bayernwerk GmbH (KRB) had a capacity of 250 MWe and was operated from 1966 to 1977. Dismantling work has been started for some time (especially the turbine hall has been dismantled), and complete removal of the power station is foreseen to be completed by 2000. The 2 foregoing EC programmes have been involved by 4 R and D contracts in the past dismantling work on KRB-A. KRB-A dismantling is a European undertaking according to the definition of the Euratom Treaty. Considering that the experience to be gained from the dismantling of the first representative nuclear installations in the Community should be made available to all Member States, the Commission selected KRB-A as a pilot dismantling project for the 1989-93 R and D programme on the decommissioning of nuclear installations. The Commission, through shared-cost participation in specific parts of the project, intends promoting the use of advanced techniques and the performance of collateral investigations, in order to enhance the generation of useful knowledge and experience to serve in subsequent decommissioning tasks. In particular, the generation of specific data on costs, working hours and job doses as well as on the amount of created secondary waste is considered as an important objective of this project. The assessment of techniques and procedures will be performed in collaboration with CEN/SCK Mol and VAK-GmbH, which are decommissioning the Pressurised Water Reactor BR-3 and the VAK BWR, respectively. The results and conclusions of the assessment work undertaken in contract FI2D0002 are taken into account for the implementation of work in this contract. As a BWR, KRB-A is representative for such reactors, existing elsewhere in the Community. The first phase of the contract involves the dismantling and segmenting of contaminated components of the reactor building in air (partly with subsequent decontamination), and of activated internals of the reactor pressure vessel (RPV) in remotely controlled underwater operation. Estimations of maximal values for specific contamination or activation are in the order of 10 superscript 4 and 10 superscript 6 Bq/square cm, respectively. The second phase contains the development of specific tools and the segmentation of further steel components and concrete structures as well as the development of procedures for the conditioning of molten steel (onion package) and of decontamination waste. General Information: WORK PROGRAMME. 1. Dismantling in air of contaminated and low-activated components of the reactor building, partly with subsequent decontaminating/melting. 1.1. Dismantling of a secondary steam generator with various tools (band saw, flame cutting). 1.2. Dismantling of a primary circulation pump by band saw. 1.3. Dismantling of a primary clean-up cooler with various tools (band saw, diamond-tipped wire saw). 1.4. Dismantling of a shutdown ...

Development of segmenting tools and remote handling systeme sand application to the dismantling of VAK BWR reactor pressure vessel internals

Das Projekt "Development of segmenting tools and remote handling systeme sand application to the dismantling of VAK BWR reactor pressure vessel internals" wird vom Umweltbundesamt gefördert und von Versuchsatomkraftwerk Kahl durchgeführt. Objective: The experimental Boiling Water Reactor Kahl (VAK-BWR) of 16 MWe has been shut down after 25 years of operation. Dismantling has been going on for some time. The present estimation of the radioactive inventory of the reactor is in the order of 5E15 Bq. The aim of the present contract is the development, qualification and practical application of different underwater (UW) segmenting and remote handling techniques on a series of internal components out of the reactor pressure vessel (RPV). Important targets are: minimization of operators' dose uptake and of primary and secondary waste generation and economics of the procedure. Specific radioactivity of such components is in the order of magnitude of 1E5 to 1E8 Bq/g (activation) and of 1E4 to 1E5 Bq/square cm (contamination). Due to its long-term operation, VAK dismantling can be considered to a large extent (dose rates, activation, contamination, material ageing) as representative for the future decommissioning of LWRs. In particular, the generation of specific data on costs, working hours and job doses as well as on the amount of created secondary waste is considered as an important objective of this project. Work will be implemented in close cooperation with the pilot dismantling projects BR-3/Mol and KRB-A. The results of the comparative assessment study made by KRB will be considered in the implementation of the contract. General Information: WORK PROGRAMME: 1. Conceptual studies and construction of a 1:1 scale facility for UW testing of cutting tool and devices for remote operation; 2. Preliminary tests on nonradioactive components, including devices for segmentation, remote operation techniques, definition of generated secondary waste and studies of dismantling scenarios; 3. Qualification of dismantling procedures for an application to radioactive components; 4.Dismantling of a series of RPV internals (upper grid plate, chimney above the core, control systems); 5. Generation of specific data on costs, radioactive job doses, working time and secondary waste arisings, derived from the execution of items 2, 3 and 4. Achievements: The aim of the present contract is the development, qualification and practical application of different underwater (UW) segmenting and remote handling techniques on a series of internal components out of the reactor pressure vessel (RPV). After evaluation of 7 decommissioning studies the principal choice of the cutting and handling technology was made. This resulted in a dismantling concept based on cutting technologies that produced a minimum of aerosols. As a result, plasma melt cutting (PMC) for dismantling of core internals was exchanged for mechanical cutting techniques like milling, grinding and electro discharge machining (EDM). Sawing and milling tests with a welding cladded RPV sample, both under water and in air were successfully performed.

Effectiveness and long-term behaviour of cleanable high efficiency aerosol filters

Das Projekt "Effectiveness and long-term behaviour of cleanable high efficiency aerosol filters" wird vom Umweltbundesamt gefördert und von Technischer Überwachungsverein Bayern Sachsen durchgeführt. Objective: Because of the high quantity of dust generated by various cutting/dismantling processes, frequent replacement of high-efficiency sub-micron particulate air filters is necessary. If such filters could be cleaned during service, costs for the replacement of the filters, radiation exposures and the amount of secondary waste could be reduced. The effectiveness in long-term operation (approx. one year) of high-efficiency sub micron particle air filters will be investigated in the framework of the dismantling of the Niederaichbach nuclear power station (KKN) in Germany. A high-efficiency sub micron particle air filter system will be exposed to heavy dust generation during the remote-controlled dismantling of KKN primary circuit pressure tubes, and therefore must be dedusted periodically. The dust is radioactively charged (essentially cobalt-60 and iron-55). The radioactivity could amount to approximately 1E5 Bq/g (pressure tubes and moderator tank) and the dose rate to 0.1 Sv/h. There is at present no experience on the effectiveness and the long-term behaviour of high-efficiency sub micron particle air filters that are dedustable during operation. General Information: WORK PROGRAMME: 1. Installation of the filters; 2. Determination of the main parameters of the clean filter station; 3. Continuous measurements (pressure pickups, air humidity and temperatures) during cutting of KKN primary cooling circuit (activated cooling channel tubes inside the reactor vessel); 4. Final evaluation including radiation exposure of workers, secondary waste arisings, specific costs, effectiveness and long-term behaviour of the filter system. Achievements: Because of the high quantity of dust generated by various cutting/dismantling processes, frequent replacement of high efficiency sub micron particulate air filters is necessary. If such filters could be cleaned during service, costs for the replacement of the filters, radiation exposures and the amount of secondary waste could be reduced. The effectiveness in long term operation of high efficiency sub micron particle air filters is investigated in the framework of the dismantling of the Niederaichbach nuclear power station (KKN) in Germany. ...

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