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Sicherheit von Kernreaktoren Nuclear Safety

Grant period2021 - 2026
Funding bodyHelmholtz Gemeinschaft Deutscher Forschungszentren
CategoriesLeistungskategorie I ; Topic
IdentifierG:(DE-HGF)POF4-142

Nukleare Entsorgung, Sicherheit und Strahlenforschung (NUSAFE II)

   

Recent Publications

All known publications ...
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http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png 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 20252025-07-072025-07-11 - () BibTeX | EndNote: XML, Text | RIS

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png 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 20252025-07-072025-07-11 () [10.34734/FZJ-2025-03394] OpenAccess  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png 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 20252025-08-312025-09-05 14 pp. () BibTeX | EndNote: XML, Text | RIS

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png 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 20252025-08-312025-09-05 BibTeX | EndNote: XML, Text | RIS

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png 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 20252025-08-312025-09-05 [10.34734/FZJ-2025-03334] OpenAccess  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png 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 20252025-07-072025-07-11 BibTeX | EndNote: XML, Text | RIS

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png 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 20252025-07-072025-07-11 BibTeX | EndNote: XML, Text | RIS

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png 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 - () [10.1016/j.nucengdes.2024.113722] OpenAccess  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png Abstract  ;  ;
Hydrogen safety in cogeneration processes - overview of methodologies and challenges
IAEA, ViennaVienna, Austria, 12 Nov 2024 - 14 Nov 20242024-11-122024-11-14 [10.34734/FZJ-2025-01738] OpenAccess  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png Abstract  ;  ;  ;  ;  ;  ;  ;
A proposal of hydrogen safety technology for decommissioning of the Fukushima Daiichi Nuclear Power Plant
WHEC2024, CancunCancun, Mexico, 23 Jun 2024 - 27 Jun 20242024-06-232024-06-27 [10.34734/FZJ-2025-01737] OpenAccess  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

All known publications ...
Download: BibTeX | EndNote XML,  Text | RIS | 


 Datensatz erzeugt am 2021-01-15, letzte Änderung am 2021-01-16



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