Zobrazeno 1 - 10
of 13
pro vyhledávání: '"André Seeliger"'
Autor:
Ulrich Harm, Wolfgang Kästner, Stefan Renger, Ulrike Gocht, André Seeliger, Sören Alt, Holger Kryk
Publikováno v:
Nuclear Technology 205(2019)1-2, 248-261
17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), 03.-08.09.2017, Xi'an, China17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17)
17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), 03.-08.09.2017, Xi'an, China
17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), 03.-08.09.2017, Xi'an, China17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17)
17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), 03.-08.09.2017, Xi'an, China
In a joint research project of the Zittau/Goerlitz University of Applied Sciences (HSZG), the Technische Universitaet Dresden (TUD) and the Helmholtz-Zentrum Dresden-Rossendorf (HZDR), the main emphasis is the time-related assignment of simultaneous
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::aae60b12d29a03ecb8f38373faab9823
https://www.hzdr.de/publications/Publ-26214-3
https://www.hzdr.de/publications/Publ-26214-3
Publikováno v:
Nuclear Engineering and Design 305(2016), 489-502
Within the framework of the German reactor safety research, generic experimental investigations were carried out aiming at thermal-hydraulic consequences of physicochemical mechanisms, caused by dissolution of zinc in boric acid during corrosion proc
Publikováno v:
Volume 3: Thermal-Hydraulics.
Investigations about the release, transportation and deposit of fibrous insulation material (FIM), corrosion products as well as resulting compounds and debris mixtures become more important to reactor safety research, when considering long-term beha
Autor:
G.M. Cartland Glover, F. Zacharias, Holger Kryk, Stefan Renger, Sören Alt, Eckhard Krepper, Alexander Kratzsch, Frank-Peter Weiss, André Seeliger, Wolfgang Kästner
Publikováno v:
Proceedings of the 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14)
14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, 25.-29.09.2011, Toronto, CanadaProceedings of the 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14), CD-ROM
14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, 25.-29.09.2011, Toronto, Canada
The Journal of Computational Multiphase Flows, Vol 4, Iss 3, Pp 255-270 (2012)
The Journal of Computational Multiphase Flows 4(2012)3, 255-270
14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, 25.-29.09.2011, Toronto, CanadaProceedings of the 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics (NURETH-14), CD-ROM
14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, 25.-29.09.2011, Toronto, Canada
The Journal of Computational Multiphase Flows, Vol 4, Iss 3, Pp 255-270 (2012)
The Journal of Computational Multiphase Flows 4(2012)3, 255-270
Damage to insulation materials located near to a primary circuit coolant leak may compromise the operation of the emergency core cooling system (ECCS). Insulation material in the form of mineral wool fiber agglomerates (MWFA) maybe transported to the
Autor:
André Seeliger, F. Zacharias, Holger Kryk, Sören Alt, Alexander Grahn, Stefan Renger, Eckhard Krepper, Wolfgang Kästner, G. Cartland-Glover, Alexander Kratzsch, Wolfgang Hoffmann, Rainer Hampel
Publikováno v:
Kerntechnik 76(2011)1, 20-29
The investigation of insulation debris transport, sedimentation, penetration into the reactor core and head loss build up becomes important to reactor safety research for PWR and BWR, when considering the long-term behaviour of emergency core cooling
Autor:
Eckhard Krepper, Alexander Grahn, Alexander Kratzsch, André Seeliger, Rainer Hampel, Wolfgang Kästner, Gregory Cartland Glover, Sören Alt, Frank-Peter Weiss
Publikováno v:
Annals of Nuclear Energy 35(2008), 1564-1579
The investigation of insulation debris generation, transport and sedimentation becomes more important with regard to reactor safety research for pressurized and boiling water reactors, when considering the long-term behaviour of emergency core coolan
Publikováno v:
Volume 4: Thermal Hydraulics.
Background of the experimental and methodical work is a loss of coolant accident (LOCA) in a Pressurized Water Reactor (PWR). During LOCA, both the leakage water jet as well as the water in the containment can lead to corrosion of galvanized installa
Publikováno v:
Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries.
Background of experimental and methodical work is the loss of coolant accident (LOCA) with release of fibrous pipe insulation material. Latest investigations were focused on material deposition and distribution (cross mixing) in the reactor core. The
Autor:
Sören Alt, André Seeliger, Rainer Hampel, Gregory Cartland-Glover, Wolfgang Kästner, Frank-Peter Weiss, Alexander Grahn, Eckhard Krepper
Publikováno v:
Nuclear Engineering and Design 240(2009), 2357-2364
The investigation of insulation debris generation, transport and sedimentation becomes important with regard to reactor safety research for PWR and BWR, when considering the long-term behavior of emergency core cooling systems during all types of los
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::56a9caffe6c516d0ca7cff3fcd5d02fd
https://www.hzdr.de/publications/Publ-12962-1
https://www.hzdr.de/publications/Publ-12962-1
Autor:
Sören Alt, André Seeliger, Wolfgang Kästner, Rainer Hampel, Eckhard Krepper, Frank-Peter Weiss, Alexander Grahn, Gregory Cartland-Glover
Publikováno v:
Nuclear Technology 167(2009)1, 46-59
XCFD4RS Experiments and CFD Codes Application to Nuclear Reactor Safety, 10.-12.09.2008, Grenoble, France
Computational Fluid Dynamics (CFD) in Nuclear Reactor Safety (NRS)
XCFD4RS Experiments and CFD Codes Application to Nuclear Reactor Safety, 10.-12.09.2008, Grenoble, France
Computational Fluid Dynamics (CFD) in Nuclear Reactor Safety (NRS)
The investigation of insulation debris generation, transport, and sedimentation becomes more important with regard to reactor safety research for pressurized water reactors and boiling water reactors when considering the long-term behavior of emergen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b7308a29dcc03500043ffebb01a8b63a
https://www.hzdr.de/publications/Publ-10924-1
https://www.hzdr.de/publications/Publ-10924-1