Abstract
Following the German government’s decision to phase out the use of nuclear energy after the reactor accident in Fukushima in March 2011, 27 prototype and power reactors are currently undergoing a dismantling process in Germany. No nuclear power plants have been in operation in Germany since April 2023 (BMUV – Bundesministerium für Umwelt 2023). The dismantling of pipelines, which are difficult to access from the outside due to limited space or because they are installed in concrete structures, is associated with many challenges and additional work for the personnel on site. Among other things, there is no universal pipe cutting system that can be used to separate pipes made of different materials, diameters and wall thicknesses from the inside of the pipe. Additional functions such as remote operation or the ability to decontaminate the machines, are of great importance for use in a nuclear environment. Most of the devices available on the market focus on pipe decontamination and are limited to certain diameters and materials. In addition, the developments are based on conventional applications and must be further adapted to the particular conditions in a nuclear facility (Bachmann 2024). Based on this, the “RoTre” project and the resulting dissertation examined the internal pipe cutting process with disk cutters, circular saw blades and cut-off wheels. The investigations presented are part of the research project “Development of a novel universally internal pipe separator for the dismantling of (contaminated) pipelines (RoTre)”, funded by the Federal Ministry of Education and Research (BMBF).
Acknowledgments
Federal Ministry of Education and Research, Siempelkamp NIS Ingenieurgesellschaft mbH (NIS).
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Research ethics: Not applicable.
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Informed consent: Not applicable.
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Author contributions: The content of the article is based on the research project “RoTre” and the dissertation by Madeleine Bachmann.
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Use of Large Language Models, AI and Machine Learning Tools: None declared.
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Conflict of interest: No conflict of interest.
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Research funding: Federal Ministry of Education and Research.
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Data availability: Not applicable.
References
Bachmann, M. and Pfau, M. (2023). Development of a sampling system including quality assured sampling procedure for nonaccessible area (Bero), Available at: https://www.tmb.kit.edu/english/ResearchProjects_7907.php (Accessed 20 03 2025).Search in Google Scholar
Bachmann, M. (2024). Untersuchungen zur Betriebsparameterwahl für ein neuartiges Rohrinnentrennsystem. KIT open, Karlsruhe.Search in Google Scholar
Baldauf, V. (2016). Dismantling nuclear power stations. kit o, Available at: https://www.tuev-nord.de/explore/en/reveals/dismantling-nuclear-power-stations/(Accessed 03 02 2025).Search in Google Scholar
Bayerisches Staatsministerium für Umwelt und Verbraucherschutz (n.d.). FAQS zum Rückbau von Kernkraftwerken, Available at: https://www.stmuv.bayern.de/themen/reaktorsicherheit/stilllegung_abbau/faq.htm (Accessed 09 01 2025).Search in Google Scholar
BMUV - Bundesministerium für Umwelt (2023). Naturschutz, nukleare Sicherheit und Verbraucherschutz. Atomkraftwerke in Deutschland, Available at: https://www.bmuv.de/themen/nukleare-sicherheit/aufsicht-ueber-atomkraftwerke/atomkraftwerke-in-deutschland (Accessed 08 01 2025).Search in Google Scholar
Gentes, S., Bachmann, M., Pfau, M., Krau, C., Wadewitz, C., and Manneck, B. (2023). Teil I + II: Kurzbericht und Eingehende Darstellung zum Verbundvorhaben “Entwicklung eines neuartigen Rohrinnentrenners für die Demontage (kontaminierter) Rohrleitungen (RoTre), Available at: https://www.tib.eu/de/suchen?tx_tibsearch_search%5Baction%5D=download&tx_tibsearch_search%5Bcontroller%5D=Download&tx_tibsearch_search%5Bdocid%5D=TIBKAT%3A1883424372&cHash=e13fef1fc343a862b955f4977f06432f#download-mark (Accessed 09 01 2025).Search in Google Scholar
Hackel, W. (2012). Infoveranstaltung zum Abbau der Anlage Mülheim-Kärlich, Available at: https://www.rwe.com/-/media/RWE/documents/01-der-konzern/betriebsstandorte/muellheizkraftwerk-muelheim-kaerlich/infoveranstaltung-zum-abbau-der-anlage-muelheim-kaerlich.pdf (Accessed 09 01 2025).Search in Google Scholar
ME-Meßsysteme GmbH (n. d). K6D: 6-Achsen Kraft-Momenten sensor, Available at: https://www.me-systeme.de/de/k6d80-500n-20nm (Accessed 09 01 2025).Search in Google Scholar
Vattenfall GmbH (n. d). Kernenergie: Rückbau eines Kernkraftwerk - was bedeutet das? Available at: https://group.vattenfall.com/de/was-wir-tun/unsere-energiequellen/kernenergie/rueckbau-eines-kernkraftwerk (Accessed 09 01 2025).Search in Google Scholar
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Articles in the same Issue
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- Investigations into the development of a new type of internal pipe cutting device for difficult to access pipelines
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- Effect of glass cooling method on thermal shock behavior of nuclear waste container
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- Calendar of events
Articles in the same Issue
- Frontmatter
- Investigations into the development of a new type of internal pipe cutting device for difficult to access pipelines
- Study on flow field characteristics of regulator in uranium enrichment centrifugal cascade
- Innovative materials for enhancing safety, efficiency, and sustainability in nuclear waste management
- Double solitary waves reactor
- Advancing the safety design of heat pipe cooled reactors: a case study of lead liquid bath and monolith stainless steel core
- Evaluation of various calculational models of FA containing burnable absorber rod in the VVER-1000
- Accurate departure from nucleate boiling ratio (DNBR) prediction using SIMCA’s partial least squares regression and clustering
- Effect of glass cooling method on thermal shock behavior of nuclear waste container
- Study on the impact of containment mesh refinement and PAR installation on hydrogen distribution during severe accidents
- Preliminary analysis of typical accidents of CFETR helium-cooled solid breeder blanket system based on COSINE
- Calendar of events