Zobrazeno 1 - 10
of 33
pro vyhledávání: '"J.-M. Seiler"'
Autor:
M. Samaille, E. Guyez, M. Bottin, J.-M. Seiler, J.-C. Bonnard, G. Ratel, M. Amižic, J.-F. Haquet
Publikováno v:
Annals of Nuclear Energy. 93:35-42
During a severe accident in a Pressurized Water Reactor, corium may fall in the reactor pit and interact with concrete. The CLARA facility, financed by EDF, IRSN, GDF-Suez and CEA, has been designed to understand the heat transfer phenomena involved
Publikováno v:
Nucl.Eng.Des.
Nucl.Eng.Des., 2018, 335, pp.279-290. ⟨10.1016/j.nucengdes.2018.05.023⟩
Nuclear Engineering and Design
Nuclear Engineering and Design, 2018, 335, pp.279-290. ⟨10.1016/j.nucengdes.2018.05.023⟩
Nucl.Eng.Des., 2018, 335, pp.279-290. ⟨10.1016/j.nucengdes.2018.05.023⟩
Nuclear Engineering and Design
Nuclear Engineering and Design, 2018, 335, pp.279-290. ⟨10.1016/j.nucengdes.2018.05.023⟩
Within the framework of the Generation IV Sodium-cooled Fast Reactor (SFR) in which the CEA (French Commissariat a l’Energie Atomique et aux Energies Alternatives) is involved, the French innovative reactor design behavior under severe accidents co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9abfeed0151da9b103127c49a1ca3b37
https://hal.archives-ouvertes.fr/hal-01851226
https://hal.archives-ouvertes.fr/hal-01851226
Publikováno v:
Oil & Gas Science and Technology-Revue d'IFP Energies nouvelles
Oil & Gas Science and Technology-Revue d'IFP Energies nouvelles, Institut Français du Pétrole, 2013, 68 (4), pp.725-739. ⟨10.2516/ogst/2013115⟩
Oil & Gas Science and Technology-Revue d'IFP Energies nouvelles, 2013, 68 (4), pp.725-739. ⟨10.2516/ogst/2013115⟩
Oil & Gas Science and Technology-Revue d'IFP Energies nouvelles, Institut Français du Pétrole, 2013, 68 (4), pp.725-739. ⟨10.2516/ogst/2013115⟩
Oil & Gas Science and Technology-Revue d'IFP Energies nouvelles, 2013, 68 (4), pp.725-739. ⟨10.2516/ogst/2013115⟩
International audience; norganic species from biomass (wood or agricultural waste) exhibit large variations in compositions and amounts, depending on the origin of the biomass (nature, growing conditions and location). Different thermal conversion pr
Publikováno v:
Revue Générale Nucléaire. :63-72
L’article presente les enjeux et l’etat des connaissances concernant les possibilites de retention de materiaux issus d’un coeur de Reacteur a Eau Pressurisee en situation hypothetique d’accident grave. On discute les situations de retention
Autor:
K. Trambauer, S. Guentay, C. Tinkler, S. Dickinson, R. Zeyen, B. Turland, L. Fickert, B. Raj Sehgal, J. Bagues, L.E. Herranz Puebla, Alessandro Annunziato, M. El-Shanawany, M. Buerger, J. M. Seiler, D. Magallon, J. Jakab, K. Atkhen, A. Mailliat, Zoltán Hózer, H. Sjövall, L. Meyer, F. Martin-Fuentes
Publikováno v:
Nuclear Engineering and Design. 235:309-346
EURSAFE thematic network was a concerted action in the sixth framework programme of the European Commission. It established a large consensus among the main actors in nuclear safety on the severe accident issues where large uncertainties still subsis
Publikováno v:
Revue Générale Nucléaire. :90-94
L'EPR est le fruit d'environ 10 ans de collaboration entre Framatome et Siemens. Les deux industriels ont concu un reacteur qui reprend les meilleures technologies des reacteurs N4 francais et des KONVOI allemands. Une approche evolutionnaire a ete r
Autor:
G. Azarian, J.-L Grange, O Kymäläinen, A Zurita, B. R. Sehgal, A Latrobe, H. Alsmeyer, M. Bürger, J. M. Seiler, Manfred Fischer, B. Turland, C.J Cirauqui
Publikováno v:
Nuclear Engineering and Design. 221:119-136
The objective of the EUROCORE (European Group for Analysis of Corium Recovery Concepts) Concerted Action is to obtain a clear view of the state-of-the-art for melt stabilisation as considered in accident management schemes and to better identify Rese
Publikováno v:
Revue Générale Nucléaire. :33-37
Publikováno v:
Thermohydraulique des accidents graves dans les réacteurs à eau légère.
Publikováno v:
2011 2nd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications.
In support of the French ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) reactor program, which aims to demonstrate the industrial applicability of sodium fast reactors with an increased level of safety demonstration and a