Zobrazeno 1 - 10
of 27
pro vyhledávání: '"M. Huggenberger"'
Publikováno v:
Nuclear Engineering and Design. 241:4551-4561
As part of the Euratom project TEMPEST (Testing and Enhanced Modelling of Passive Evolutionary Systems Technology for Containment Cooling), a series of five tests was performed in the PANDA facility to experimentally investigate the distribution of h
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c1d2fc14ae850c831a1a03c965c6fac4
https://doi.org/10.1016/j.nucengdes.2010.11.022
https://doi.org/10.1016/j.nucengdes.2010.11.022
Akademický článek
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Publikováno v:
Science and Technology of Nuclear Installations, Vol 2008 (2008)
Natural circulation characteristics at low pressure/low power have been studied by performing experimental investigations and numerical simulations. The PANDA large-scale facility was used to provide valuable, high quality data on natural circulation
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::48b8e80480e17607ec7456c04f1e291f
https://doi.org/10.1155/2008/874969
https://doi.org/10.1155/2008/874969
Autor:
M. Huggenberger, Annalisa Manera, K.C.J. Ketelaar, E. Royer, José Luis Muñoz-Cobo, Horst-Michael Prasser, T.H.J.J. van der Hagen, F. Castrillo, G. Dominicus, D. Caruge, V. Saldo, Ulrich Rohde, D. Hennig, George Yadigaroglu, A.J. Geutjes, C. Aguirre
Publikováno v:
Nuclear Engineering and Design (2005)235, 401-409
From the beginning of BWR technology it was realized that a BWR can become unstable under particular circumstances caused by a feedback between the thermal-hydraulics and the neutronics. This instability can result in oscillations of the power and th
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9b1d153f22f215e31d787a4b5a98f194
https://doi.org/10.1016/j.nucengdes.2004.08.048
https://doi.org/10.1016/j.nucengdes.2004.08.048
Autor:
W.J.M Slegers, F Reventos Puigjaner, J Hart, J Lopez Jimenez, J. L. Muñoz-Cobo González, S.L de Boer, M. Huggenberger
Publikováno v:
Nuclear Engineering and Design. 209:243-252
The objective of the technology enhancement for passive safety systems (TEPSS) project TEPSS Final Report, INNO-TEPSS(99)-D21 (1999)) was to make significant additions to the technology base of the European simplified boiling water reactor (ESBWR). T
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::35440c54bb2185b9a1fa27c77770b370
https://doi.org/10.1016/s0029-5493(01)00407-1
https://doi.org/10.1016/s0029-5493(01)00407-1
Publikováno v:
Nuclear Engineering and Design. 204:285-298
Recently, passive cooling systems have been designed for the long-term decay heat removal from the containment of Advanced Light Water Reactors. In particular, the long-term LOCA response of the Passive Containment Cooling System (PCCS) for the Gener
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7517750320c39fe2be943b8e8299c8ef
https://doi.org/10.1016/s0029-5493(00)00317-4
https://doi.org/10.1016/s0029-5493(00)00317-4
Akademický článek
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Autor:
C. Aubert, T. Bandurski, J. Healzer, S. Tomperski, G. Yadigaroglu, O. Fischer, J. Dreier, H.-J. Strassberger, M. Huggenberger, G. Varadi
Publikováno v:
Kerntechnik. 61:214-222
The PANDA test facility at the Paul Scherrer Institute is used to study the long-term performance of the Simplified Boiling Water Reactor's passive containment cooling system. The PANDA tests demonstrate performance on a larger scale than previous te
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::548f7f3d7dc96fe992c426683ef6efe9
https://doi.org/10.1515/kern-1996-615-607
https://doi.org/10.1515/kern-1996-615-607
Autor:
M. Hudina, M. Huggenberger
Publikováno v:
Nuclear Engineering and Design. 97:347-360
Extensive experimental and analytical investigations of fluid flow and heat transfer in gas-cooled rod bundles have been carried out. Different bundle geometries with partially or fully roughened rod surfaces were tested in a carbon dioxide loop. An
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c18604872946eef199c9a7b5d5622d4c
https://doi.org/10.1016/0029-5493(86)90170-6
https://doi.org/10.1016/0029-5493(86)90170-6
Autor:
K.R. Schultz, M. Huggenberger
Publikováno v:
Nuclear Technology - Fusion. 4:456-467
A preliminary design for a helium-cooled solid breeder blanket for a tokamak fusion reactor has been developed, and its performance looks quite good. The design is capable of bearing a 4 MW/m/sup 2/ neutron wall load, and the ideal pumping power requ
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::28c6ec5fffa1b9cdd444d977feafe0b1
https://doi.org/10.13182/fst83-a22795
https://doi.org/10.13182/fst83-a22795