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pro vyhledávání: '"Mauger, G."'
Akademický článek
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Publikováno v:
In Nuclear Engineering and Design November 2016 308:20-29
Autor:
Hall, J.M., Asztalos, S., Biltoft, P., Church, J., Descalle, M.-A., Luu, T., Manatt, D., Mauger, G., Norman, E., Petersen, D., Pruet, J., Prussin, S., Slaughter, D.
Publikováno v:
In Nuclear Inst. and Methods in Physics Research, B August 2007 261(1-2):337-340
Publikováno v:
In Marine Environmental Research 2003 56(3):349-365
Publikováno v:
IAHR 2018-29th Symposium on Hydraulic Machinery and Systems
IAHR 2018-29th Symposium on Hydraulic Machinery and Systems, Sep 2018, Kyoto, Japan
IAHR 2018-29th Symposium on Hydraulic Machinery and Systems, Sep 2018, Kyoto, Japan
International audience; For reactor design and safety purposes, the French Alternative Energies and AtomicEnergy Commission (CEA) is currently working on Sodium Fast Reactor (SFR) thermal-hydraulics. A SFR is a system composed of three circuits (prim
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::a90931194b808acd352bd5ac546ef312
https://hal-cea.archives-ouvertes.fr/cea-02338952
https://hal-cea.archives-ouvertes.fr/cea-02338952
Publikováno v:
Geoscientific Instrumentation, Methods & Data Systems Discussions (GID). 2013, Vol. 3 Issue 1, p193-219. 27p.
Akademický článek
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Publikováno v:
In Nuclear Inst. and Methods in Physics Research, A 1999 422(1):252-256
Publikováno v:
NURETH 2015-16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics
NURETH 2015-16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2015, Chicago, United States
NURETH 2015-16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Aug 2015, Chicago, United States
International audience; ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) is the 1500 MWthFrench sodium-cooled fast reactor (SFR) developed by the CEA and its partners. It is designed todemonstrate the workability at an indu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::cd3b1f5d4f943ea2aadb7e3bd3bdaa56
https://hal-cea.archives-ouvertes.fr/cea-02509157/file/201500001127.pdf
https://hal-cea.archives-ouvertes.fr/cea-02509157/file/201500001127.pdf
Autor:
Bertrand, Emanuel, Mauger, G.
Publikováno v:
NURETH-16-16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics3
NURETH-16-16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics3, Aug 2015, Chicago, United States
NURETH-16-16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics3, Aug 2015, Chicago, United States
International audience; The present paper is dedicated to preliminary transient studies carried out for the analysis of the overall system behavior of the ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) demonstrator develo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::66825945116b9a97013bfa5e74f8622a
https://hal-cea.archives-ouvertes.fr/cea-02489514
https://hal-cea.archives-ouvertes.fr/cea-02489514