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# Website0

open access for nuclear content

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## Beiträge

- [Publications](https://atw-scientific.com/publications-2/) - -
- [Continuously operated separation system for the processing of reusable abrasive for the water abrasive suspension cutting process](https://atw-scientific.com/continuously-operated-separation-system-for-the-processing-of-reusable-abrasive-for-the-water-abrasive-suspension-cutting-process/) - Alexander Heneka Karlsruher Institut für Technologie (KIT) Institut für Technologie und Management im Baubetrieb (TMB) Gotthard-Franz-Str. 3, Geb. 50.31, 76131 Karlsruhe E-Mail: alexander.heneka@kit.edu Junaid Chaudhry, Sascha Gentes, Carla-Olivia Krauß, Jonas Ruoff Karlsruher Institut für Technologie (KIT) Institut für Technologie und Management im Baubetrieb (TMB) Gotthard-Franz-Str. 3, Geb. 50.31, 76131 Karlsruhe E-Mail: muhammad.chaudhry@kit.edu carla-olivia.krauss@kit.edu
- [Entwicklung eines Robotersystems zur Automatisierung der Dekontamination kerntechnischer Anlagen](https://atw-scientific.com/entwicklung-eines-robotersystems-zur-automatisierung-der-dekontamination-kerntechnischer-anlagen/) - Siavash Kazemi Karlsruher Institut für Technologie (KIT) Institut für Technologie und Management im Baubetrieb (TMB) Geb. 50.33 Am Fasanengarten D-76131 Karlsruhe siavash.kazemi@kit.edu Sascha Gentes Karlsruher Institut für Technologie (KIT) Institut für Technologie und Management im Baubetrieb (TMB) Geb. 50.31 Am Fasanengarten sascha.gentes@kit.edu Zusammenfassung Um Kernkraftwerke nach der Stilllegung rückbauen zu können, müssen alle Oberflächen dekontaminiert
- [DEVELOPMENT AND TEST OF A SORTING SYSTEM FOR SOIL WITH CONVENTIONAL AND RADIOLOGICAL CONTAMINATION](https://atw-scientific.com/development-and-test-of-a-sorting-system-for-soil-with-conventional-and-radiological-contamination/) - Christoph Klein NUKEM Technologies Engineering Services GmbH Zeche Gustav 6, 63791 Karlstein a. M. christoph.klein@nukemtechnologies.de Felix Langer Marina Sokcic-Kostic NUKEM Technologies Engineering Services GmbH Zeche Gustav 6, 63791 Karlstein a. M. felix.langer@nukemtechnologies.de marina.sokcic-kostic@nukemtechnologies.de SUMMARY NUKEM’s system FREMES, which has been successfully applied worldwide, is able to characterize and sort both radiological and chemical
- [ESTIMATION OF RADIONUCLIDE INVENTORY OF IRRADIATED REACTOR GRAPHITE USING THE MC-BASED PROGRAM FLUKA](https://atw-scientific.com/estimation-of-radionuclide-inventory-of-irradiated-reactor-graphite-using-the-mc-based-program-fluka/) - Maurice Klink Hochschule Mannheim, Mannheim University of Applied Sciences Paul-Wittsack-Straße 10, 68163 Mannheim E-mail: n.heiss@hs-mannheim.de Niklas Heiß, Lotte Lens, Ulrich W. Scherer Hochschule Mannheim, Mannheim University of Applied Sciences Paul-Wittsack-Straße 10, 68163 Mannheim E-mail: n.heiss@hs-mannheim.de; l.lens@hs-mannheim.de; u.scherer@hs-mannheim.de SUMMARY German research reactors undergo shutdown and dismantling. The special focus is on the irradiated reactor
- [Rückbau 4.0 - Die Digitalisierung des kerntechnischen Rückbaus in Deutschland](https://atw-scientific.com/rueckbau-4-0-die-digitalisierung-des-kerntechnischen-rueckbaus-in-deutschland/) - Dominik Krupp Safetec GmbH Dischingerstraße 8, 69123 Heidelberg Dominik.Krupp@Safetec-HD.de Andreas Wieser, Johannes Radtke Safetec GmbH Dischingerstraße 8, 69123 Heidelberg Zusammenfassung Durch die Abschaltung der letzten Leistungsreaktoren in Deutschland befinden sich nun alle noch vorhandenen Kernkraftwerke im Rückbau. Die Gebäudedekontamination und Freigabe (GeDuF) stellt dabei die Entlassung der Anlage aus dem Geltungsbereich des Atomgesetzes dar.
- [CHARACTERIZATION AND DECONTAMINATIONOF IRRADIATED REACTOR GRAPHITE - AN OVERVIEW -](https://atw-scientific.com/characterization-and-decontaminationof-irradiated-reactor-graphite-an-overview/) - Lotte Lens Hochschule Mannheim, Mannheim Universtiy of Applied Sciences Paul-Wittsack-Straße 10, 68163 Mannheim l.lens@hs-mannheim.de Lorie Meunier, Niklas Heiß, Ulrich W. Scherer Hochschule Mannheim, Mannheim University of Applied Sciences Paul-Wittsack-Straße 10, 68163 Mannheim l.meunier@hs-mannheim.de; n.heiss@hs-mannheim.de; u.scherer@hs-mannheim.de SUMMARY Germany’s many research reactors have contributed significantly to scientific advancement. Now that most of them are shut down,
- [CHARACTERIZATION OF IRRADIATED GRAPHITE SAMPLES USING DESTRUCTIVE AND NON-DESTRUCTIVE METHODS](https://atw-scientific.com/characterization-of-irradiated-graphite-samples-using-destructive-and-non-destructive-methods/) - Lorie Meunier Hochschule Mannheim, Mannheim University of Applied Sciences Paul-Wittsack-Str. 10, 68163 Mannheim l.meunier@hs-mannheim.de Lotte Lens, Niklas Heiß, U. W. Scherer Hochschule Mannheim, Mannheim University of Applied Sciences Paul-Wittsack-Str. 10, 68163 Mannheim l.lens@hs-mannheim.de; n.heiss@hs-mannheim.de; u.scherer@hs-mannhem.de SUMMARY Characterisation of irradiated, thus activated graphite samples is mandatory before any decontamination steps can be developed.
- [Digitalization of spatial data acquisition for the clearance of buildings](https://atw-scientific.com/digitalization-of-spatial-data-acquisition-for-the-clearance-of-buildings/) - Melanie Müßle Karlsruhe Institute of Technology, Institute of Technology and Management in Construction Gotthard-Franz-Str. 3, 76131 Karlsruhe Melanie.Muessle@kit.edu Sascha Gentes Karlsruhe Institute of Technology, Institute of Technology and Management in Construction Gotthard-Franz-Str. 3, 76131 Karlsruhe Sascha.Gentes@kit.edu SUMMARY The clearance of buildings is a central step in the decomissioning process of
- [IN-SITU MOISTURE MEASURING IN CONCRETE STRUCTURES OF NUCLEAR REACTOR BUILDINGS DURING DECOMMISSIONING](https://atw-scientific.com/in-situ-moisture-measuring-in-concrete-structures-of-nuclear-reactor-buildings-during-decommissioning/) - Tanzila Nurjahan Institut für Energietechnik, Technische Universität Dresden,Germany t.nurjahan@hzdr.de Felipe de Assis Dias Experimental Thermal Fluid Dynamics, Helmholtz-Zentrum Dresden Rossendorf, Dresden, Germany f.dias@hzdr.de Eckhard Schleicher Experimental Thermal Fluid Dynamics, Helmholtz-Zentrum Dresden Rossendorf, Dresden, Germany e.schleicher@hzdr.de Uwe Hampel Institut für Energietechnik,Technische Universität Dresden,Germany, Experimental Thermal Fluid Dynamics, Helmholtz-Zentrum Dresden Rossendorf, Dresden, Germany u.hampel@hzdr.de
- [Vorstellung des Forschungsprojekts zur Entwicklung eines Beprobungssystems inklusive qualitätsgesichertem Beprobungsverfahren für nicht zugängliche Kunststoffrohrleitungen (Bero)](https://atw-scientific.com/vorstellung-des-forschungsprojekts-zur-entwicklung-eines-beprobungssystems-inklusive-qualitaetsgesichertem-beprobungsverfahren-fuer-nicht-zugaengliche-kunststoffrohrleitungen-bero/) - Pfau, Michael Karlsruher Institut für Technologie Gotthard-Franz-Straße 10 Michael.pfau@kit.edu Bachmann, Madeleine / Gentes, Sascha Karlsruher Institut für Technologie Gotthard-Franz-Straße 10 Madeleine.bachmann@kit.edu / sascha.gentes@kit.edu Zusammenfassung Im Projekt Bero wird das Ziel verfolgt für Kunststoffrohrleitungen in Einbaulage ein Demonstratorsystem zu entwickeln, welches nach einem qualitätsgesichertem Beprobungsverfahren eine bedarfsgerechte Beprobung durchführen und das abgetragene Probematerial, soweit möglich, verlustfrei
- [DEVELOPMENT OF A DECONTAMINATION TOOL FOR INNER EDGES AND CORNERS (EKONT-2)](https://atw-scientific.com/development-of-a-decontamination-tool-for-inner-edges-and-corners-ekont-2/) - Eric Rentschler Karlsruher Institut für Technologie, TMB Karlsruhe, Gotthard-Franz-Str. 3 eric.rentschler@kit.edu Sascha Gentes Stefan Stemmle Johannes Greb Martin Villinger Kurt Heppler Karlsruher Institut für Technologie, TMB Karlsruhe, Gotthard- Franz-Str. 3 SAT Kerntechnik Gmbh Robur Group Worms, Am Guten Brunnen 10 Contec Maschinenbau GmbH Alsdorf, Hauptstraße 146 HTWG Konstanz Maschinenkonstruktion Konstanz, Alfred- Wachtel-Straße 8
- [Einfluss innovativer kerntechnischer Rückbaumethoden auf Schwebstoff-Filtersysteme](https://atw-scientific.com/einfluss-innovativer-kerntechnischer-rueckbaumethoden-auf-schwebstoff-filtersysteme/) - Marco Sauder Krantz GmbH Uersfeld 24, 52072 Aachen Marco.Sauder@krantz.de ZUSAMMENFASSUNG Während bei herkömmlichen Rückbaumethoden wie der mechanischen Oberflächenbearbeitung oder den mechanischen und thermischen Trennverfahren bereits bewährte abreinigbare Filtersysteme zum Einsatz kommen, ist es beim Einsatz neuer Rückbaumethoden wichtig, das Konzept ganzheitlich zu betrachten und zu prüfen, inwieweit diese neuen Methoden einen Einfluss auf bestehende oder
- [RADIOLOGICAL CHARACTERIZATION OF SOLID WASTE: FROM FREE RELEASE MEASUREMENTS UP TO THE MEASUREMENT OF HIGH RADIOACTIVE WASTE](https://atw-scientific.com/radiological-characterization-of-solid-waste-from-free-release-measurements-up-to-the-measurement-of-high-radioactive-waste/) - Dr. Marina Sokcic-Kostic NUKEM Technologies Engineering Services Zeche Gustav 6, 63791 Karlstein am Main marina.sokcic-kostic@nukemtechnologies.de Dr. Christoph Klein, Dr. Frank Scheuermann NUKEM Technologies Engineering Services Zeche Gustav 6, 63791 Karlstein am Main christoph.klein@nukemtechnologies.de, frank.scheuremann@nukemtechnologies.de SUMMARY Nuclear radioactive waste is produced in research institutes, nuclear power plants but also in nuclear
- [Fort Calhoun Station Decommissioning and Demolition Project Reactor Vessel Segmentation](https://atw-scientific.com/fort-calhoun-station-decommissioning-and-demolition-project-reactor-vessel-segmentation/) - Marcus Trempler Siempelkamp NIS Ingenieursgesellschaft mbh Industriestr. 13, 63755 Alzenau marcus.trempler@siempelkamp-nis.com Detlef Queißer Siempelkamp NIS Ingenieursgesellschaft mbh Industriestr. 13, 63755 Alzenau detlef.queisser@siempelkamp-nis.com SUMMARY The Fort Calhoun Nuclear Generating Station (FCS) commissioned in August 1973 was shut down in October 2016. The station was powered by a pressurized water reactor with a name plate
- [Laser-based measurement system for the detection of subsurface anomalies](https://atw-scientific.com/laser-based-measurement-system-for-the-detection-of-subsurface-anomalies/) - Valentin Vierhub-Lorenz Fraunhofer Institute for Physical Measurement Techniques IPM Georges-Koehler-Allee 301, 79110 Freiburg valentin.vierhub-lorenz@ipm.fraunhofer.de Dr. Christoph Werner Fraunhofer Institute for Physical Measurement Techniques IPM Georges-Koehler-Allee 301, 79110 Freiburg christoph.werner@ipm.fraunhofer.de Prof. Alexander Reiterer Albert-Ludwigs-University Freiburg, INATECH Emmy-Noether-Str. 2 alexander.reiterer@ipm.fraunhofer.de SUMMARY We present a laser-based measurement system for the detection of subsurface anomalies such as delaminations and
- [Material clearance measurement under the influence of natural occurring radioactive material](https://atw-scientific.com/material-clearance-measurement-under-the-influence-of-natural-occurring-radioactive-material/) - Dr. Bastian Weinhorst Safetec GmbH Dischingerstr. 8, 69123 Heidelberg Bastian.weinhorst@safetec-hd.de Dr. Tim Thomas, Dr. Edgar Perez Lezama, Iheb Meddeb, Michele Pastena Safetec GmbH Dischingerstr. 8, 69123 Heidelberg SUMMARY (max. 125 words) The paper describes a study performed with the large clearance monitor (LCM) simulation software SIStec presenting a novel approach to take the
- [Schritte zur Freigabe des Sicherheitsbehälters im KKS](https://atw-scientific.com/schritte-zur-freigabe-des-sicherheitsbehaelters-im-kks/) - Hans-Georg Willschütz PreussenElektra GmbH, Kernkraftwerk Stade Bassenflether Chaussee, 21682 Stade hans-georg.willschuetz@preussenelektra.de Florian Lorenzen, Peter Kreft und Marco Albers PreussenElektra GmbH, Kernkraftwerk Stade Bassenflether Chaussee, 21682 Stade florian.lorenzen@preussenelektra.de Stephan Bergander Tiefenbach Oberflächentechnik GmbH Industriestraße 14, 21640 Horneburg s.bergander@tiefenbach-oberflaechentechnik.de KURZFASSUNG Das Kernkraftwerk Stade (KKS) befindet sich in den letzten Schritten auf dem Weg zur Entlassung aus dem
- [Application of Weight Parameters generated via Recursive Monte Carlo Method for Optimized Shielding Calculations](https://atw-scientific.com/application-of-weight-parameters-generated-via-recursive-monte-carlo-method-for-optimized-shielding-calculations/) - Pratibha Yadav Institut für Kernenergetik und Energiesysteme – Universität Stuttgart Pfaffenwaldring 31, 70569, Stuttgart, Germany pratibha.yadav@ike.uni-stuttgart.de Reuven Rachamin, Jörg Konheiser Helmholtz-Zentrum Dresden-Rossendorf Bautzner Landstraße 400 – 01328 Dresden r.rachamin@hzdr.de, j.konheiser@hzdr.de SUMMARY This paper discusses the challenges of using Monte Carlo calculations for radiation shielding analysis. Complex shielding scenarios often yield unreliable outcomes due to
- [AUSLEGUNG EINER TRANSPORTBEREITSTELLUNGSHALLE UND DESSEN BEHÄLTERSTAPEL GEGEN EINWIRKUNG VON AUßEN AUS ERDBEBEN UND EXPLOSIONSDRUCKWELLE](https://atw-scientific.com/auslegung-einer-transportbereitstellungshalle-und-dessen-behaelterstapel-gegen-einwirkung-von-aussen-aus-erdbeben-und-explosionsdruckwelle/) - Marcus Ries Wölfel Engineering GmbH + Co. KG Max-Planck-Straße 15, 97204 Höchberg, Deutschland ries@woelfel.de Ronald Müller-Petersen Laatzener Straße 1, 30539 Hannover, Deutschland Ronald.Mueller-Petersen@preussenelektra.de Marco Hildmann, Fritz-Otto Henkel Wölfel Engineering GmbH + Co. KG Max-Planck-Straße 15, 97204 Höchberg, Deutschland ZUSAMMENFASSUNG Es wird die Auslegung einer Transportbereitstellungshalle (TBH) hinsichtlich Standsicherheit, insbe- sondere der darin befindlichen Behälterstapel,
- [Aktueller Stand des Standortauswahlverfahrens aus der Sicht der Vorhabenträgerin](https://atw-scientific.com/aktueller-stand-des-standortauswahlverfahrens-aus-der-sicht-der-vorhabentraegerin/) - Lisa Seidel, Dr. Sönke Reiche Bundesgesellschaft für Endlagerung mbH, BGE Eschenstraße 55, 31224 Peine Lisa.Seidel@bge.de, Soenke.Reiche@bge.de ZUSAMMENFASSUNG Nach Veröffentlichung des Zwischenbericht Teilgebiete in 2020 ermittelt die Bundesgesellschaft für Endlagerung mbH (BGE) Standortregionen für die übertägige Erkundung. Ein wichtiger Teil der aktuellen Arbeiten der BGE besteht in der Ausarbeitung eines konkreten Arbeitsprozesses, der zu einer nachvollziehbaren,
- [KONZEPTE FÜR ENDLAGERBEHÄLTER IN KRISTALLINEM WIRTSGESTEIN IN DEUTSCHLAND](https://atw-scientific.com/konzepte-fuer-endlagerbehaelter-in-kristallinem-wirtsgestein-in-deutschland/) - Amin Bannani GNS Gesellschaft für Nuklear-Service mbH Frohnhauser Straße 67, 45127 Essen amin.bannani@gns.de Ansgar Wunderlich 1), Matthias Dittrich 2), Michael Ulbrich 2) BGE TECHNOLOGY GmbH 1) GNS Gesellschaft für Nuklear-Service mbH 2) Kurzfassung Im Projekt „ELBRock“ wurden die für die Endlagerbehälterkonzeptfindung notwendigen Grundlagen und Randbedingungen sowie der Stand von Wissenschaft und Technik hinsichtlich der Endlagerung
- [MUON IMAGING OF TRANSPORT AND STORAGE CASKS](https://atw-scientific.com/muon-imaging-of-transport-and-storage-casks/) - Suzanne Eisenhofer1,2 1 Technische Universität Dresden Institut für Energietechnik, Fakultät Maschinenwesen, 01062 Dresden 2 Helmholtz-Zentrum Dresden – Rossendorf e. V., Bautzner Landstraße 400, 01328 Dresden s.eisenhofer@hzdr.de Jakub Dykas1,2, Guanghao Jiao1,2, Michael Wagner1,2, Uwe Hampel1,2 j.dykas@hzdr.de, g.jiao@hzdr.de, michael.wagner@hzdr.de, u.hampel@hzdr.de SUMMARY Understanding the state of the inventory of transport and storage casks is a
- [AUSLEGUNG UND BERECHNUNG DER OBERIRDISCHEN GEBÄU- DETEILE EINES ENDLAGERS FÜR DEN LASTFALL ERDBEBEN AUF GRUNDLAGE DER KTA](https://atw-scientific.com/auslegung-und-berechnung-der-oberirdischen-gebaeu-deteile-eines-endlagers-fuer-den-lastfall-erdbeben-auf-grundlage-der-kta/) - Marco Hildmann Wölfel Engineering GmbH & Co. KG Max-Plank-Straße 15, D-97204 Höchberg hildmann@woelfel.de Anna Bauer, Fritz-Otto Henkel Wölfel Engineering GmbH & Co. KG Max-Plank-Straße 15, D-97204 Höchberg Anna.Bauer@woelfel.de, Henkel@woelfel.de ZUSAMMENFASSUNG Ein geologisches Tiefenlager für mittel- und schwachradioaktive Abfälle wurde Anfang der 90er Jahre in einem ehemaligen deutschen Bergwerk konzipiert. Es umfasst Stahlbetonkonstruktionen mit Stahlförderturm für
- [RADIOLOGISCHE BETRACHTUNGEN ZUR FESTLEGUNG VON MINDESTABSTÄNDEN FÜR STANDORTE VON ABFALL- UND/ODER BRENNELEMENTE-ZWISCHENLAGERN DER BGZ](https://atw-scientific.com/radiologische-betrachtungen-zur-festlegung-von-mindestabstaenden-fuer-standorte-von-abfall-und-oder-brennelemente-zwischenlagern-der-bgz/) - André Indenhuck, Vera Derya WTI Wissenschaftlich-Technische Ingenieurberatung GmbH Karl-Heinz-Beckurts-Straße 8, 52428 Jülich indenhuck@wti-juelich.de, derya@wti-juelich.de KURZZUSAMMENFASSUNG Für alle Standorte von Abfall- und/oder Brennelemente-Zwischenlagern der BGZ Gesellschaft für Zwischenlagerung mbH kann zukünftig Bedarf nach Änderungen der Grenzen der jeweiligen Betriebs- gelände oder der für die Umgebung gültigen Flächennutzungspläne entstehen. Unabhängig vom konkreten Bedarf sollen perspektivisch standortspezifische radiologische
- [THE MUTOMCA PROJECT – AN OVERVIEW](https://atw-scientific.com/the-mutomca-project-an-overview/) - Julia Niedermeier Chair of Nuclear Technology, Technical University Munich, Germany Boltzmannstraße 15, 85747 Garching Julia.Niedermeier@tum.de Andreetto¹, K. Aymanns², M. Balling³, Benettoni¹, N. Bez¹, G.Bonomi⁴, Castellani¹, P. Checchia¹, E. Conti¹, Dackner⁵, F. Gonella², A. Jussofie³, Lorenzon¹, F. Montecassiano¹, M. Mosconi⁵, Murtezi⁵, I. Niemeyer², J. Pekkarinen⁵, Scarpa¹, M. Stuke³, M. Turcato¹, Zumerle¹ ¹ INFN Padova
- [ESTABLISHING A NEW CASK FAMILY -](https://atw-scientific.com/establishing-a-new-cask-family/) - Jens Pauluhn GNS Gesellschaft für Nuklear-Service mbH Frohnhauser Straße 67 jens.pauluhn@gns.de Robert Schneider GNS Gesellschaft für Nuklear-Service mbH Frohnhauser Straße 67 robert.schneider@gns.de SUMMARY The dual-purpose CASTOR® casks – designed, licensed and manufactured by GNS Gesellschaft für Nuklear-Service mbH – is well-established with more than 40 years of continuous evolution and improvement. Due to
- [SUPERCRITICAL CO2 RECUPERATED CYCLE PART LOAD OPERATIONS EMPLOYING TURBINE THROTTLE VALVE](https://atw-scientific.com/supercritical-co2-recuperated-cycle-part-load-operations-employing-turbine-throttle-valve/) - Matthias Peiretti University of Stuttgart Pfaffenwaldring 31, 70569 Stuttgart, Germany matthias.peiretti@ike.uni-stuttgart.de Markus Hofer University of Stuttgart Michael Buck University of Stuttgart Jörg Starflinger University of Stuttgart SUMMARY This study focuses on the implementation of a turbine throttle valve for part-load operation in a 5 MWth recuperated supercritical carbon dioxide (sCO2) Brayton cycle, integrated with
- [DEVELOPMENT OF A HEAT PIPE MODEL FOR ATHLET](https://atw-scientific.com/development-of-a-heat-pipe-model-for-athlet/) - Daniel Eckert, Fabian Weyermann, Norman Dünne, Andreas Schaffrath Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) Boltzmannstr. 14, 85748 Garching, Germany daniel.eckert@grs.de, fabian.weyermann@grs.de, norman.duenne@grs.de, andreas.schaffrath@grs.de Jörg Starflinger Institut für Kernenergetik und Energiesysteme (IKE) Pfaffenwaldring 31, 70569 Stuttgart, Germany joerg.starflinger@ike.uni-stuttgart.de SUMMARY Heat pipe-cooled micro modular reactors (HP-MMRs) are very small and transportable nuclear reactors, which are being
- [Neutronic modelling of the Special Purpose Reactor MMR with Serpent as a part of the MISHA project](https://atw-scientific.com/neutronic-modelling-of-the-special-purpose-reactor-mmr-with-serpent-as-a-part-of-the-misha-project/) - Norman Dünne, Jeremy Bousquet, Daniel Eckert, Andreas Wielenberg, Andreas Schaffrath Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH Boltzmannstraße 14, 85748 Garching bei München Norman.Duenne@grs.de, Jeremy.Bousquet@grs.de, Daniel.Eckert@grs.de, Andreas.Wielenberg@grs.de, Andreas.Schaffrath@grs.de Jörg Starflinger Universität Stuttgart Institut für Kernenergetik und Energiesysteme Pfaffenwaldring 31, 70569 Stuttgart Joerg.Starflinger@ike.uni-stuttgart.de SUMMARY MISHA, a cooperative project between GRS and IKE, aims to
- [EXPERIMENTAL INVESTIGATION OF HEAT TRANSFER AT AND POST CRITICAL HEAT FLUX IN CO2 FLOW AT HIGH SUBCRITICAL PRESSURES](https://atw-scientific.com/experimental-investigation-of-heat-transfer-at-and-post-critical-heat-flux-in-co2-flow-at-high-subcritical-pressures/) - Jakub Dariusz Bronik, Michael Buck, Jörg Starflinger Institute of Nuclear Technology and Energy Systems (IKE), University of Stuttgart Pfaffenwaldring 31, 70569 Stuttgart, Germany jakub.bronik@ike.uni-stuttgart.de Summary Supercritical fluids, such as water or CO2, have promising properties for advanced nuclear reactor systems. For the safety assessment of thermohydraulic systems using these fluids, a deep understanding of heat
- [Advancing Micro Modular Reactor Safety: Experimental Analysis on Liquid Metal Heat Pipe Prototypes in the MISHA Project](https://atw-scientific.com/advancing-micro-modular-reactor-safety-experimental-analysis-on-liquid-metal-heat-pipe-prototypes-in-the-misha-project/) - Ruggero Meucci Institute of Nuclear Technology and Energy Systems (IKE) – University of Stuttgart Pfaffenwaldring 31, 70569, Stuttgart, Germany Ruggero.Meucci@ike.uni-stuttgart.de Rudi Kulenovic, Jörg Starflinger Pfaffenwaldring 31, 70569, Stuttgart, Germany Rudi.Kulenovic@ike.uni-stuttgart.de, Joerg.Starflinger@ike.uni-stuttgart.de SUMMARY Recent years have confirmed a growing interest in Small Modular Reactors (SMRs) and Micro Modular Reactors (MMRs) for their potential
- [Entwicklung und Validierung einer Rechenkette zur Simulation von Micro Modular Reactors](https://atw-scientific.com/entwicklung-und-validierung-einer-rechenkette-zur-simulation-von-micro-modular-reactors/) - Andreas Schaffrath, Jérémy Bousquet, Daniel Eckert, Norman Dünne, Andreas Wielenberg, Fabian Weyermann Gesellschaft für Anlagen und Reaktorsicherheit (GRS) gGmbH Boltzmannstrasse 14, 85748 Garching bei München Andreas.Schaffrath@grs.de Jörg Starflinger, Jakub Dariusz Bronik, Michael Buck, Viktoriia Gasanova, Markus Hofer, Rudi Kulenovic, Ruggero Meucci, Matthias Peiretti Institut für Kernenergetik und Energiesysteme (IKE), Pfaffenwaldring 31, 70569 Stuttgart Joerg.Starflinger@ike.uni-stuttgart.de Kurzfassung
- [CREATING OPERATION MANUALS FOR A WASTE MANAGEMENT ORGANIZATION](https://atw-scientific.com/creating-operation-manuals-for-a-waste-management-organization/) - Kaisa Pellinen Fortum Power and Heat, Nuclear Services Keilalahdentie 2-4, 02150 Espoo kaisa.pellinen@fortum.com SUMMARY In this paper, we present an approach to create and develop operating manual and instructions for a new nuclear waste management facility. The aim for the instructions is to be informative, easy to follow and fulfill the needs for a new
- [Schacht Konrad 1 – Austausch des Führungsgerüstes](https://atw-scientific.com/schacht-konrad-1-austausch-des-fuehrungsgeruestes/) - Marc Roßmöller Bundesgesellschaft für Endlagerung mbH Eschenstraße 55 31224 Peine Marc.rossmoeller@bge.de ZUSAMMENFASSUNG Die Bundesgesellschaft für Endlagerung (BGE) mit Sitz in Peine ist unter anderem mit der Umrüstung des ehemaligen Eisenerzbergwerkes Konrad zum Endlager für schwach- bis mittelradioaktive Abfälle beauftragt. Der vorliegende Bericht beschreibt den geplanten Führungsgerüstwechsel am Schacht Konrad 1 und die Inbetriebnahme der neuen
- [PRACTICAL CYBERSECURITY HARDENING FOR INTERIM STORAGE AND FINAL DISPOSAL FACILITIES](https://atw-scientific.com/practical-cybersecurity-hardening-for-interim-storage-and-final-disposal-facilities/) - Josef Schindler Framatome GmbH Paul-Gossen-Str. 100, 91052 Erlangen josef.schindler@framatome.com Claudia Lemos Sebastiao Christine Bürger Karl Waedt Framatome GmbH Framatome GmbH Framatome GmbH claudia.lemos- sebastiao@framatome.com christine.buerger@framatome.com karl.waedt@framatome.com INTRODUCTION Due to the upcoming Cyber Resilience Act (CRA) and the EU NIS2 directive (directive on measures for a high common level of cybersecurity across the European
- [NUMERISCHE MODELLIERUNG ZUR BEWERTUNG DER EXPOSITION ÜBER DEN GRUNDWASSERPFAD BEI DER DEPONIERUNG FREIGEGEBENER RADIOAKTIVER ABFÄLLE](https://atw-scientific.com/numerische-modellierung-zur-bewertung-der-exposition-ueber-den-grundwasserpfad-bei-der-deponierung-freigegebener-radioaktiver-abfaelle/) - Alexander Schwardt TÜV NORD EnSys GmbH & Co. KG Am TÜV 1, 30519 Hannover aschwardt@tuev-nord.de Wolfgang Botsch, Helge Wolter TÜV NORD EnSys GmbH & Co. KG Am TÜV 1, 30519 Hannover Zusammenfassung Im Zusammenhang mit dem Rückbau von Kernkraftwerken fallen erhebliche Mengen an radioaktiven Abfällen an, von denen ein Großteil für eine Freigabe zur Entsorgung
- [NUMERICAL AND EMPIRICAL APPROACHES TO QUANTIFY THE PROTECTIVE EFFECT OF SOIL](https://atw-scientific.com/numerical-and-empirical-approaches-to-quantify-the-protective-effect-of-soil/) - Lars Heibges RPTU University of Kaiserslautern-Landau Institute of Structural Analysis and Dynamics Paul-Ehrlich-Straße 14, 67663 Kaiserslautern, Germany lars.heibges@bauing.rptu.de Hamid Sadegh-Azar RPTU University of Kaiserslautern-Landau Institute of Structural Analysis and Dynamics Paul-Ehrlich-Straße 14, 67663 Kaiserslautern, Germany hamid.sadegh-azar@bauing.rptu.de SUMMARY In this paper, existing empirical approaches referenced in guidelines and standards are analysed and evaluated based
- [Shielding Fuel Assembly Design Optimization](https://atw-scientific.com/shielding-fuel-assembly-design-optimization/) - Shielding Fuel Assembly Design Optimization SUMMARY The aging nuclear fleet is facing demand of lifetime extension to ensure reliable and carbon-free energy production. A major limiting parameter for lifetime extension is the neutron fluence of the reactor presure vessel. Furthermore, new requirments on flanges may require extensive material investigations.Framatome’s shielding fuel assemblies reduce the neutron
- [A hybrid experimental and numerical investigation on the Cr2AlC-coated zirconium for accident-tolerant fuel systems](https://atw-scientific.com/a-hybrid-experimental-and-numerical-investigation-on-the-cr2alc-coated-zirconium-for-accident-tolerant-fuel-systems/) - A hybrid experimental and numerical investigation on the Cr2AlC-coated zirconium for accident-tolerant fuel systems SUMMARY This study utilized a hybrid experimental and numerical approach to investigate the failure behavior of zirconium substrates coated with Cr2AlC. The failure mechanism was determined through a series of interrupted in-situ three-point bending tests in the scanning electron microscope (SEM),
- [Effect of Bulk Condensation on Containment Atmosphere Mixing](https://atw-scientific.com/effect-of-bulk-condensation-on-containment-atmosphere-mixing/) - Effect of Bulk Condensation on Containment Athmosphere Mixing SUMMARY The impact of bulk condensation on the mixing dynamics of gases and flammability of the containment atmosphere is investigated in detail using OpenFOAM-based ‘containmentFOAM’ CFD package developed at Forschungszentrum Julich. The bulk condensation is efficiently modeled by bringing the local gas mixture to saturation temperature at
- [Ground Control and the Principle of Minimizing Radiological Exposure as Key Drivers for the Recovery of Radioactive Waste Out of the Asse II Mine](https://atw-scientific.com/elementor-532/) - Ground Control and the Principle of Minimizing Radiological Exposure as Key Drivers for the Recovery of Radioactive Waste Out of the Asse II Mine Thomas Lautsch, Beate Kallenbach-Herbert and Sebastian Voigt Geology The Asse salt structure is located in the Southwest of the Hercynian Mountains in Northern Germany. In geological times, compressive tectonic movements ruptured
- [Assessment of Loss of Shutdown Cooling System Accident during Mid-Loop Operation in LSTF Experiment using SPACE Code](https://atw-scientific.com/elementor-538/) - Author Co-Authors Category Institution Contact Author Minhee Kim Co-Authors Junkyu Song, Kyungho Nam Category International Trends & Developments in Nuclear Institution Central Research Institute, Korea Hydro & Nuclear Power Co., Daejeon, Korea Contact minhee.kim@khnp.co.kr Content Keywords Published on DOI Other Content Article Keywords – Published on – DOI – Other – Assessment of Loss of
- [IAEA Approach to Review the Applicability of the Safety Standards to Small Modular Reactors](https://atw-scientific.com/elementor-544/) - Author Co-Authors Category Institution Contact Author Paula Calle Vives Senior Nuclear Safety Officer Co-Authors Kristine Madden Associate Nuclear Safety Officer International Atomic Energy Agency Vesselina Rangelova Safety Assessment Section Head International Atomic Energy Agency Category Nuclear Competence & Nuclear Safety Institution International Atomic Energy Agency Contact P.Calle-Vives@iaea.org Content Keywords Keywords DOI Other Content Article Keywords
- [A zero-power facility as multi-fold opportunity to support quick progress in innovative reactor development](https://atw-scientific.com/elementor-550/) - Author Co-Authors Category Category Institution Contact Author Prof. Bruno Merk Co-Authors Dzianis Litskevich Anna Detkina Seddon Atknison School of Engineering, University of Liverpool, United Kingdom Greg Cartland-Glover Scientific Computing Department, Science and Technology Facilities Council, Daresbury Laboratory, SciTech Daresbury, United Kingdom Mark Bankhead National Nuclear Laboratory, United Kingdom Category Tab-Inhalt Category International Trends & Developments
- [Studies on performance and degradation stability of chemically degraded nuclear graded ion exchange materials by application of radio analytical technique](https://atw-scientific.com/elementor-556/) - Author Co-Authors Category Institution Contact Author Prof. Pravin Singare Co-Authors – Category International Trends & Developments in Nuclear Institution Department of Chemistry N.M. Institute of Science, Bhavan’s College, Mumbai, India Contact pravin.singare@bhavans.ac.in Content Keywords Published on DOI Other Content Article Keywords – Published on – DOI Tab-Inhalt Other – Studies on performance and degradation stability
- [Development of Safety-related Residual Heat Removal Chains from German Technology Pressure Water Reactors (Light and Heavy Water)](https://atw-scientific.com/elementor-562/) - Author Co-Authors Category Institution Contact Author Franz Stuhlmüller Co-Authors Prof. Rafael Macián-Juan, PhD Head of the Chair of Nuclear Technology at the Technical University of Munich Category Nuclear Competence & Nuclear Safety Institution External Scientific Associate at the Chair for Nuclear Technology at the Technical University of Munich Contact f-stuhlmueller@t-online.de Content Keywords Published on DOI
- [TRIPLE C Waste Container for Increased Long-term Safety of  HHGW Disposal in Salt, Clay and Crystalline](https://atw-scientific.com/elementor-568/) - TRIPLE C Waste Container for Increased Long-term Safety of HHGW Disposal in Salt, Clay and Crystalline 1 Introduction Nuclear facilities for the utilization and handling of nuclear materials have to fulfill general safety goals. With varying importance and priorities the same five main safety goals apply for safety considerations of all nuclear facilities. – ISOLATION
- [Error Reduction in Radioactivity Calculation for Retired Nuclear Power Plant Considering Detailed Plant-specific Operation History](https://atw-scientific.com/elementor-574/) - Author Co-Authors Category Institution Contact Author Young Jae Maeng Co-Authors Chan Hyeong Kim Professor Hanyang University, Seoul, Korea Category Decommissioning and Waste Management Institution Korea Reactor Integrity Surveillance Technology, Daejeon, Korea Contact – Content Keywords Published on DOI Other Content Article Keywords – Published on – DOI – Other – Error Reduction in Radioactivity Calculation
- [Operating Experience from Ageing Events Occurred at Nuclear Power Plants](https://atw-scientific.com/elementor-580/) - Author Co-Authors Category Institution Contact Author Antonio Ballesteros Avila Scientific Officer Co-Authors – Category Operation and New Build Institution Joint Research Centre of European Commission, Petten, The Netherlands Contact Antonio.Ballesteros-Avila@ec.europa.eu Content Keywords Published on DOI Other Content Article Keywords – Published on – DOI – Other – Operating Experience from Ageing Events Occurred at Nuclear
- [SSiC Nuclear Waste Canisters: Stability Considerations During Static and Dynamic Impact](https://atw-scientific.com/elementor-586/) - SSiC Nuclear Waste Canisters: Stability Considerations During Static and Dynamic Impact Introduction High-level radioactive waste (HLW) is mainly a by-product of technical nuclear reactions. It has the highest radioactivity and longest decay time (millions of years with significant radiation). Most HLW (more than 90%) comes from spent nuclear fuel. The deep geological disposal concept is
- [Non-destructive Radioactive tracer technique in evaluation of photo-degraded polystyrene based nuclear grade ion exchange material | Pravin U. Singare](https://atw-scientific.com/elementor-592/) - Non-destructive Radioactive tracer technique in evaluation of photo-degraded polystyrene based nuclear grade ion exchange material Introduction Poly styrene-divinyl benzene type ion exchange materials having sulfonic acid and quaternary ammonium functional groups are widely used in various nuclear industries related applications where prolonged service in adverse environmental condition is required. In nuclear industrial applications organic resin
- [Improving Henry-Fauske Critical Flow Model in SPACE Code and Analysis of LOFT L9-3](https://atw-scientific.com/elementor-598/) - Author Co-Authors Category Institution Contact Author BumSoo Youn Senior Researcher Nuclear Safety Analysis Group Co-Authors – Category International Trends & Developments in Nuclear Institution Central Research Institute, Korea Hydro and Nuclear Power Co., LTD., Republic of Korea Contact bsyoun81@khnp.co.kr Content Keywords Published on DOI Other Content Article Keywords – Published on – DOI – Other
- [Investigations of the Tailskin Seal During the Retrieval Concept ‘Shield Tunnelling with Partial Face Excavation’ in the Asse II Mine](https://atw-scientific.com/elementor-604/) - Author Co-Authors Category Institution Contact Author Birte Froebus Co-Authors – Category Decommissioning and Waste Management Institution Research Assistant at Karlsruhe Institute of Technology, Karlsruhe, Germany Contact birte.froebus@kit.edu Content Keywords Published on DOI Other Content Article Keywords – Published on – DOI – Other – Investigations of the Tailskin Seal During the Retrieval Concept ‘Shield Tunnelling
- [Preliminary CFD analysis of innovative decay heat removal system for the European Sodium Fast Reactor Concept](https://atw-scientific.com/elementor-611/) - Preliminary CFD analysis of innovative decay heat removal system for the European Sodium Fast Reactor Concept 1 Introduction Sodium-cooled Fast Reactors (SFRs) are among the most advanced concept of the Generation-IV reactor systems [1] with extensive design, construction, operation and decommissioning experience. Several experimental, prototype and power reactors have been built in Europe and elsewhere
- [CFD Simulations of Single Phase Pressurized Thermal Shock in the RPV of a 330MWe PWR](https://atw-scientific.com/elementor-617/) - Authors Co-Authors Category Institution Contact Authors Numan Iqbal1 Rab Nawaz2 Kamran Rasheed Qureshi1 Ammar Ahmed1 R. Khan2,3 Co-Authors – Category International Trends & Developments in Nuclear Institution 1 Department of Mechanical Engineering, Pakistan Institute of Engineering and Applied Sciences (PIEAS). 2 Department of Nuclear Engineering, Pakistan Institute of Engineering and Applied Sciences (PIEAS). Contact rustam_pieas@yahoo.com
- [Experimental Study of Convective Heat Transfer Through Fuel Pins of a Nuclear Power Plant](https://atw-scientific.com/elementor-623/) - Experimental Study of Convective Heat Transfer Through Fuel Pins of a Nuclear Power Plant Cylindrical heat sources are used to model the fuel pins in the reactor core of a nuclear power plant and also in the spent fuel storage. This research was aimed at studying convection through slender cylinders arranged in a square array,
- [Equipment Selection Methodology of Seismic Probability Safety Assessment for Nuclear Power Plant](https://atw-scientific.com/elementor-635/) - Equipment Selection Methodology of Seismic Probability Safety Assessment for Nuclear Power Plant 1. Introduction A typical seismic probability safety assessment (SPSA) requires geological, structural, and systems analysts. In the case of probabilistic seismic hazard analysis (PSHA), geological experts can independently perform the analysis, but structural experts performing seismic fragility analysis (SFA). Probability safety assessment (PSA)
- [Ground Control and the Principle of Minimizing Radiological Exposure as Key Drivers for the Recovery of Radioactive Waste Out of the Asse II Mine](https://atw-scientific.com/ground-control-and-the-principle-of-minimizing-radiological-exposure-as-key-drivers-for-the-recovery-of-radioactive-waste-out-of-the-asse-ii-mine/) - Ground Control and the Principle of Minimizing Radiological Exposure as Key Drivers for the Recovery of Radioactive Waste Out of the Asse II Mine Geology The Asse salt structure is located in the Southwest of the Hercynian Mountains in Northern Germany. In geological times, compressive tectonic movements ruptured the overlying rock strata covering the salt
- [Study on verification of SPACE code based on an MSGTR experiment at the ATLAS-PAFS facility](https://atw-scientific.com/elementor-629/) - Author Co-Authors Category Institution Contact Author Kyungho Nam Co-Authors – Category – Institution Korea Hydro & Nuclear Power Co., LTD. Central Research Institute Safety Analysis Group Deajeon, Republic of Korea Contact – Content Keywords Published on DOI Other Content Article Keywords – Published on – DOI Tab-Inhalt Other – Study on verification of SPACE code
- [Minimization of local dose rates by rearrangement of drums in a strongly regulated MAW/LAW storage facility](https://atw-scientific.com/elementor-520/) - Author Co-Authors Category Institution Contact Author Dr. Philip J. Harding Co-Authors Johannes Iloff Dr. Stefan Thierfeldt Brenk Systemplanung GmbH, Aachen/Hamburg, Germany Dr. Thorsten Steinhardt Dr. Dennis Niedrée Jülicher Entsorgungsbetriebe für Nuklear-Anlagen, Jülich, Germany Category Decommissioning and Waste Management Institution Brenk Systemplanung GmbH, Hamburg, Germany Contact p.harding@brenk.com Content Keywords Published on DOI Other Content – Keywords
- [A new technical approach for the minimization of secondary waste produced by water abrasive suspension cutting during disassembling of nuclear facilities](https://atw-scientific.com/elementor-526/) - Author Co-Authors Category Institution Contact Author Alexander Heneka Co-Authors Carla-Olivia Krauss Prof. Dr. Sascha Gentes Karlsruhe Institute of Technology (KIT), Karlsruhe, Germany Dr. Frank Becker Prof. Dr. Horst Geckeis Dr. Johannes Lützenkirchen Dr. Markus Plaschke Dr. Dieter Schild Winfried Tobie Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen, Germany Institute for Nuclear Waste Disposal (INE) Category Decommissioning

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