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of 37
pro vyhledávání: '"L. Saas"'
Akademický článek
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Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2021, 150, pp.107848-. ⟨10.1016/j.anucene.2020.107848⟩
Annals of Nuclear Energy, 2021, 150, pp.107848-. ⟨10.1016/j.anucene.2020.107848⟩
Annals of Nuclear Energy, Elsevier Masson, 2021, 150, pp.107848-. ⟨10.1016/j.anucene.2020.107848⟩
Annals of Nuclear Energy, 2021, 150, pp.107848-. ⟨10.1016/j.anucene.2020.107848⟩
International audience; Within the context of nuclear power safety, the In-Vessel Retention (IVR) strategy consists in sustaining the integrity of the reactor pressure vessel by External Reactor Vessel Cooling (ERVC). However, due to the ablation of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::0edccf792cf7d5beb2604d0f5029ea0b
https://hal.archives-ouvertes.fr/hal-03491217
https://hal.archives-ouvertes.fr/hal-03491217
Publikováno v:
Applied Thermal Engineering
Applied Thermal Engineering, 2017, 120, pp.314-326. ⟨10.1016/j.applthermaleng.2017.03.108⟩
Applied Thermal Engineering, 2017, 120, pp.314-326. ⟨10.1016/j.applthermaleng.2017.03.108⟩
International audience; Within the framework of lumped parameter models for integral codes, this paper focuses on the modeling of a two-phase Stefan fusion problem with natural convection in the liquid phase. In particular, this specific Stefan probl
Autor:
H. Esmaili, Florian Fichot, I. Melnikov, S. Weber, R.J. Park, L. Humphries, L. Carénini, R. Le Tellier, A. Filippov, N. Bakouta, P. Pandazis, V. Strizhov, L. Saas, T. Laato
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2020, 146, pp.107617-. ⟨10.1016/j.anucene.2020.107617⟩
Annals of Nuclear Energy, 2020, 146, pp.107617. ⟨10.1016/j.anucene.2020.107617⟩
Annals of Nuclear Energy, Elsevier Masson, 2020, 146, pp.107617-. ⟨10.1016/j.anucene.2020.107617⟩
Annals of Nuclear Energy, 2020, 146, pp.107617. ⟨10.1016/j.anucene.2020.107617⟩
International audience; The strategy for In-Vessel Retention (IVR) of corium is currently considered for several new reactor designs in various countries. One of the issues for the demonstration of the success of this strategy is that there are signi
Autor:
Eleonora Skrzypek, C. Le Guennic, L. Carénini, L. Vyskocil, L. Saas, R. Le Tellier, Maciej Skrzypek, K. Zwijsen, Afaque Shams, B. Bigot, Florian Fichot, D. Dovizio, Mathieu Peybernes
Publikováno v:
Annals of Nuclear Energy. 135:107004
During a severe accident in a nuclear reactor, core damage occurs and may lead to the formation of corium, followed by relocation to the vessel lower head. The decay heat released by the corium can threaten the integrity of the vessel, if no effectiv
Publikováno v:
International Journal for Multiscale Computational Engineering
International Journal for Multiscale Computational Engineering, Begell House, 2018, 16, pp.6. ⟨10.1615/IntJMultCompEng.2018025643⟩
International Journal for Multiscale Computational Engineering, 2018, 16, pp.6. ⟨10.1615/IntJMultCompEng.2018025643⟩
International Journal for Multiscale Computational Engineering, Begell House, 2018, 16, pp.6. ⟨10.1615/IntJMultCompEng.2018025643⟩
International Journal for Multiscale Computational Engineering, 2018, 16, pp.6. ⟨10.1615/IntJMultCompEng.2018025643⟩
International audience; This paper focuses on solving coupled problems of lumped parameter models. Such problems are of interest for the simulation of severe accidents in nuclear reactors: these coarse-grained models allow for fast calculations for s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::618d7226c9b21ac043ee5c555c762bda
Publikováno v:
Nuclear Engineering and Design. 287:68-77
In the context of light water reactor severe accidents analysis, this paper is focused on one key parameter of in-vessel corium phenomenology: the immiscible phases stratification and its impact on the heat flux distribution at the corium pool latera
A simplified geometrical model for transient corium propagation in core for LWR with heavy reflector
Publikováno v:
EPJ N-Nuclear Sciences & Technologies
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2017, 3, pp.20. ⟨10.1051/epjn/2016007⟩
EPJ N-Nuclear Sciences & Technologies, 2017, 3, pp.20. ⟨10.1051/epjn/2016007⟩
EPJ Nuclear Sciences & Technologies, Vol 3, p 20 (2017)
EPJ N-Nuclear Sciences & Technologies, EDP Sciences, 2017, 3, pp.20. ⟨10.1051/epjn/2016007⟩
EPJ N-Nuclear Sciences & Technologies, 2017, 3, pp.20. ⟨10.1051/epjn/2016007⟩
EPJ Nuclear Sciences & Technologies, Vol 3, p 20 (2017)
International audience; In the context of the simulation of the Severe Accidents (SA) in Light Water Reactors (LWR), we are interested on the in-core corium pool propagation transient in order to evaluate the corium relocation in the vessel lower hea
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d4631119f53d150a7501858d8fffe8cb
https://hal-cea.archives-ouvertes.fr/cea-02305032/document
https://hal-cea.archives-ouvertes.fr/cea-02305032/document
Akademický článek
Tento výsledek nelze pro nepřihlášené uživatele zobrazit.
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Publikováno v:
Annals of Clinical Biochemistry: International Journal of Laboratory Medicine. 40:411-416
Background: The demand for screening for coeliac disease has grown rapidly over the last few years. Laboratories depending on immunofluorescence assays are faced with an increasing workload using a labour-intensive test, and an alternative to this te