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1422

Beyond Design Basis Accidents and Emergency Management

Grant period2021 - 2026
Funding bodyHelmholtz Gemeinschaft Deutscher Forschungszentren
CategoriesLeistungskategorie I ; Subtopic
IdentifierG:(DE-HGF)POF4-1422

⇧ Sicherheit von Kernreaktoren ⇧

   

Recent Publications

All known publications ...
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http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png Poster (Other)  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;
Influence of Severe Accident Management on the In-Containment Combustion Risk in European Pressurized Water Reactors
International Conference Nuclear Energy for New Europe, BledBled, Slovenia, 8 Sep 2025 - 11 Sep 20252025-09-082025-09-11 BibTeX | EndNote: XML, Text | RIS

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png Proceedings  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;
Influence of Severe Accident Management on the In-Containment Combustion Risk in European Pressurized Water Reactors
International Conference Nuclear Energy for new Europe, BledBled, Slovenia, 8 Sep 2025 - 11 Sep 20252025-09-082025-09-11 BibTeX | EndNote: XML, Text | RIS

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png Abstract  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;  ;
Influence of Severe Accident Management on the In-Containment Combustion Risk in European Pressurized Water Reactors
International Conference Nuclear Energy for New Europe, BledBled, Slovenia, 8 Sep 2025 - 11 Sep 20252025-09-082025-09-11 BibTeX | EndNote: XML, Text | RIS

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png Journal Article  ;  ;
Numerical Simulation of Dispersion and Ventilation of Hydrogen Clouds in Case of Leakage Inside a Large-Scale Industrial Building
Hydrogen 6(2), 40 - () [10.3390/hydrogen6020040] OpenAccess  Download fulltext Files BibTeX | EndNote: XML, Text | RIS

http://join2-wiki.gsi.de/foswiki/pub/Main/Artwork/join2_logo100x88.png Conference Presentation (Other)  ;  ;  ;
Measurement of the near-wall velocity gradient under mixed convection by using an LDV profile sensor
32. Fachtagung "Experimentelle Strömungstechnik" (GALA), DarmstadtDarmstadt, Germany, 9 Sep 2025 - 11 Sep 20252025-09-092025-09-11 BibTeX | EndNote: XML, Text | RIS

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 Journal Article  ;
AMHYCO engineering correlation to describe the conversion of flammable gases in Framatome passive autocatalytic recombiners
Nuclear engineering and design 442, 114206 - () [10.1016/j.nucengdes.2025.114206] 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

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

 Record created 2021-01-15, last modified 2021-02-17
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