Zobrazeno 1 - 5
of 5
pro vyhledávání: '"Tobias Sühnel"'
Publikováno v:
Nuclear Engineering and Design 238(2008)7, 1788-1801
It is known that under-borated coolant can accumulate in the loops and that it can be transported towards the reactor core during a loss of coolant accident. Therefore, the mixing of weakly borated water inside the reactor pressure vessel was investi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a1ab34e588c2d1792f41e1c831d8d956
https://doi.org/10.1016/j.nucengdes.2007.10.016
https://doi.org/10.1016/j.nucengdes.2007.10.016
Publikováno v:
Multiphase Science and Technology. 20:265-290
Some of the accident scenarios discussed for the Russian type pressurized water reactors VVER-440 assume an overfeed of the secondary side of the steam generators by water coming either from the primary side or from the feedwater system. This may hap
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::280b1506ef29d0dc8ebef194bf512cdb
https://doi.org/10.1615/multscientechn.v20.i3-4.30
https://doi.org/10.1615/multscientechn.v20.i3-4.30
Publikováno v:
ResearcherID
Kerntechnik 71(2006)3, 95-103
Kerntechnik 71(2006)3, 95-103
For the investigation of air/water slug flow, a horizontal channel with rectangular cross-section was built at Forschungszentrum Rossendorf. The channel allows the investigation of air/water co- and counter-current flows at atmospheric pressure, espe
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b15d036229f41b15da41d8a8bc19f25f
https://doi.org/10.3139/124.100281
https://doi.org/10.3139/124.100281
Publikováno v:
CFD4NRS-Benchmarking of CFD Codes for Application to Nuclear Reactor Safety, 05.-07.09.2006, Garching, München, Germany
Nuclear Engineering and Design 238(2008), 637-646
CFD4NRS-Benchmarking of CFD Codes for Application to Nuclear Reactor Safety, 05.-07.09.2006, Garching, München, GermanyPaper A6-31
Nuclear Engineering and Design 238(2008), 637-646
CFD4NRS-Benchmarking of CFD Codes for Application to Nuclear Reactor Safety, 05.-07.09.2006, Garching, München, GermanyPaper A6-31
For the investigation of stratified two-phase flow, two horizontal channels with rectangular cross-section were built at Forschungszentrum Dresden-Rossendorf (FZD). The channels allow the investigation of air/water co-current flows, especially the sl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4947ad1b901178cb6c56b438edbbcc3d
https://www.hzdr.de/publications/Publ-8080-2
https://www.hzdr.de/publications/Publ-8080-2
Autor:
Thomas Höhne, Horst-Michael Prasser, Ulrich Rohde, Frank-Peter Weiss, Tobias Sühnel, Sören Kliem
Publikováno v:
OECD/NEA & IAEA Workshop: "Benchmarking of CFD Codes for Application to Nuclear Reactor Safety", 05.-07.09.2006, Garching, GermanyProceedings CD-ROM paper A4-17, Issy-les-Moulineaux, France: OECD NEA
OECD/NEA & IAEA Workshop: "Benchmarking of CFD Codes for Application to Nuclear Reactor Safety", 05.-07.09.2006, Garching, Germany
Nuclear Engineering and Design 238(2008), 566-576
OECD/NEA & IAEA Workshop: "Benchmarking of CFD Codes for Application to Nuclear Reactor Safety", 05.-07.09.2006, Garching, Germany
Nuclear Engineering and Design 238(2008), 566-576
For the validation of computational fluid dynamics (CFD) codes, experimental data on fluid flow parameters with high resolution in time and space are needed. Rossendorf Coolant Mixing Model (ROCOM) is a test facility for the investigation of coolant
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::40113a00b3d4d30034cd4959a8974714
https://www.hzdr.de/publications/Publ-8315-1
https://www.hzdr.de/publications/Publ-8315-1