Zobrazeno 1 - 8
of 8
pro vyhledávání: '"Werner Scholtyssek"'
Publikováno v:
Nuclear Technology. 139:10-20
The research and development program at the Forschungszentrum Karlsruhe, performed within the Program Nuclear Safety Research, is centered around phenomena and processes that could possibly endanger the containment integrity of a large pressurized wa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f2c38786b336bf52b8e046392b4253e2
https://doi.org/10.13182/nt02-a3298
https://doi.org/10.13182/nt02-a3298
Publikováno v:
Nuclear Technology. 126:143-152
In the development of the European pressurized water reactor (EPR), a new, challenging safety goal is the requirement to restrict the consequences of even severe accidents to the immediate vicinity of the plant To deal with the consequences of a seve
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1b59861e577a1a5742398d4d4e5db0fa
https://doi.org/10.13182/nt99-a2963
https://doi.org/10.13182/nt99-a2963
Autor:
Werner Scholtyssek
Publikováno v:
Nuclear Technology. 111:319-330
The TPCONT computer code is used to study the thermal-hydraulic behavior of a pressurized water reactor containment after a core-melt accident. A commercial-sized reactor of 1,500-MW(electric) power output is especially designed to withstand transien
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::33b218d890875587a3ade2b169b155ef
https://doi.org/10.13182/nt95-a15862
https://doi.org/10.13182/nt95-a15862
Autor:
Werner Scholtyssek, Joachim Ehrhardt, Georg Henneges, Hans-Werner Wiese, Guenther Kessler, Bernhard J. Kuczera
Publikováno v:
Nuclear Technology. 111:305-318
Safety requirements on future nuclear power plants converge in the common objective that these plants should be so safe that even in case of a severe accident there will be no need of off-site emergency actions such as an evacuation or resettlement o
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5256761685dc80b92fc07c86400f70b1
https://doi.org/10.13182/nt95-a15861
https://doi.org/10.13182/nt95-a15861
Autor:
David Meneghetti, Dwight A. Kucera, Siegfried Jacobi, Wolfgang Kröger, Rudolf Schulten, Gregory J. Van Tuyle, Gregory C. Slovik, Robert J. Kennett, Bing C. Chan, Arnold L. Aronson, Peter Kroeger, Robert T. Lancet, Robert Z. Litwin, Ravnesh C. Amar, Robert D. Rogers, Alan V. von Arx, Charles J. Mueller, David C. Wade, James E. Cahalan, David J. Hill, John M. Kramer, John F. Marchaterre, Dean R. Pedersen, Roger W. Tilbrook, T. Y. C. Wei, Arthur E. Wright, Karl Verfondern, Werner Schenk, Heinz Nabielek, John Cleveland, Daniel E. Carroll, Kenneth D. Bergeron, Werner Scholtyssek, Greg D. Valdez, Richard Gido
Publikováno v:
Nuclear Technology. 91:133-138
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4e6a91f75264f6d7a86cf3940d1ffaf7
https://doi.org/10.13182/nt90-a34422
https://doi.org/10.13182/nt90-a34422
Publikováno v:
Nuclear Technology. 91:259-267
The CONTAIN code is the NRC's best-estimate code fo the evaluation of the conditions that may exist inside a reactor containment building during a severe accident. Included in the phenomena modeled are thermal-hydrulics, radiant and convective heat t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::141d2f836b695096fc45919ff1e33f2d
https://doi.org/10.13182/nt90-a34433
https://doi.org/10.13182/nt90-a34433
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Akademický článek
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