1422
Beyond Design Basis Accidents and Emergency Management
Grant period | 2021 - 2026 |
Funding body | Helmholtz Gemeinschaft Deutscher Forschungszentren |
Categories | Leistungskategorie I ; Subtopic |
Identifier | G:(DE-HGF)POF4-1422 |
⇧ Sicherheit von Kernreaktoren ⇧
All known publications ...
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Contribution to a conference proceedings
R&D WORKS ON HTR SPENT FUEL TREATMENT IN GERMANY
IAEA TM on the Management of Spent Fuel (Pebbles and Compacts) from High Temperature Reactors, ViennaVienna, Austria, 7 Jul 2025 - 11 Jul 2025
- (2025)
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Contribution to a conference proceedings
SPENT FUEL MANAGEMENT IN THE DECOMMISSIONING PROCESS FOR THE GERMAN HIGH TEMPERATURE REACTORS AVR AND THTR-300
IAEA TM on the Management of Spent Fuel (Pebbles and Compacts) from High Temperature Reactors, ViennaVienna, Austria, 7 Jul 2025 - 11 Jul 2025
(2025) [10.34734/FZJ-2025-03394]
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Contribution to a conference proceedings
Simulation and Analysis of Containment Behavior during selected Severe Accident Transients in a Generic Konvoi-type PWR using COCOSYS
21st International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-21), BusanBusan, South Korea, 31 Aug 2025 - 5 Sep 2025
14 pp. (2025)
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Conference Presentation (Other)
Simulation and Analysis of Containment Behavior during Selected Severe Accident Transients in a Generic Konvoi-type PWR using COCOSYS
21st International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-21), BusanBusan, South Korea, 31 Aug 2025 - 5 Sep 2025
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Abstract
Simulation and Analysis of Containment Behavior during Selected Severe Accident Transients in a Generic Konvoi-type PWR using COCOSYS
21st International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-21), BusanBusan, South Korea, 31 Aug 2025 - 5 Sep 2025
[10.34734/FZJ-2025-03334]
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Conference Presentation (Other)
R&D Works on HTR Spent Fuel Treatment in Germany
IAEA TM on the Management of Spent Fuel (Pebbles and Compacts) from High Temperature Reactors, WienWien, Austria, 7 Jul 2025 - 11 Jul 2025
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Conference Presentation (Other)
Spent Fuel Management in the Decommissioning Process for the German High Temperature Reactors AVR and THTR-300
IAEA TM on the Mangement of Spent Fuel (Pebbles and compacts) from High Temperature Reactors, WienWien, Austria, 7 Jul 2025 - 11 Jul 2025
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Journal Article
Validation process against late phase conditions of the passive autocatalytic recombiner simulation code PARUPM as a standalone tool using experimental data from REKO-3 and THAI facilities
Nuclear engineering and design 431, 113722 - (2025) [10.1016/j.nucengdes.2024.113722]
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Abstract
Hydrogen safety in cogeneration processes - overview of methodologies and challenges
IAEA, ViennaVienna, Austria, 12 Nov 2024 - 14 Nov 2024
[10.34734/FZJ-2025-01738]
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Abstract
A proposal of hydrogen safety technology for decommissioning of the Fukushima Daiichi Nuclear Power Plant
WHEC2024, CancunCancun, Mexico, 23 Jun 2024 - 27 Jun 2024
[10.34734/FZJ-2025-01737]
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All known publications ...
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