Zobrazeno 1 - 10
of 11
pro vyhledávání: '"Thierry Cadiou"'
Publikováno v:
Nuclear Engineering and Design
Nuclear Engineering and Design, 2021, 374, pp.111048. ⟨10.1016/j.nucengdes.2020.111048⟩
Nucl.Eng.Des.
Nucl.Eng.Des., 2021, 374, pp.111048. ⟨10.1016/j.nucengdes.2020.111048⟩
Nuclear Engineering and Design, 2021, 374, pp.111048. ⟨10.1016/j.nucengdes.2020.111048⟩
Nucl.Eng.Des.
Nucl.Eng.Des., 2021, 374, pp.111048. ⟨10.1016/j.nucengdes.2020.111048⟩
International audience; We employ a novel methodology to simulate the irradiation of Sodium cooled Fast Reactors (SFR) subassemblies. The proposed approach allows considering the coupling between key thermal–hydraulic and thermomechanical phenomena
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::0205378ea230ddc27974ef7b2d401f44
https://hal.science/hal-03191164
https://hal.science/hal-03191164
Publikováno v:
Nuclear Engineering and Design. 387:111600
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7d3e9491c928fec196f5bee238e09f38
https://doi.org/10.1016/j.nucengdes.2021.111600
https://doi.org/10.1016/j.nucengdes.2021.111600
Publikováno v:
Nuclear Engineering and Design
Nuclear Engineering and Design, In press, pp.110500. ⟨10.1016/j.nucengdes.2019.110500⟩
Nuclear Engineering and Design, Elsevier, In press, pp.110500. ⟨10.1016/j.nucengdes.2019.110500⟩
Nuclear Engineering and Design, In press, pp.110500. ⟨10.1016/j.nucengdes.2019.110500⟩
Nuclear Engineering and Design, Elsevier, In press, pp.110500. ⟨10.1016/j.nucengdes.2019.110500⟩
International audience; To improve the safety of the integrated Sodium-cooled Fast Reactor, we present an original safety complementary device to prevent or mitigate the consequences of a hypothetical severe accident consecutive to a loss of reactor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::ffd98f06b22245f3b1a1c78781fe1b2c
https://cea.hal.science/cea-02340027/document
https://cea.hal.science/cea-02340027/document
Autor:
Thierry Cadiou, Aakanksha Saxena
Publikováno v:
Nuclear Engineering and Design. 295:162-172
As the CEA is involved in the pre-conceptual design phase of a Sodium-cooled Fast Reactor (SFR), the thermal–hydraulics modeling of sodium flow in the reactor core is a key scientific subject, not only due to the innovations proposed for the core d
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::705510f268d5902e3cf836313d06549f
https://doi.org/10.1016/j.nucengdes.2015.10.001
https://doi.org/10.1016/j.nucengdes.2015.10.001
Publikováno v:
Nuclear Engineering and Design
Nuclear Engineering and Design, 2018, 330, pp.72-86. ⟨10.1016/j.nucengdes.2018.01.009⟩
Nuclear Engineering and Design, Elsevier, 2018, 330, pp.72-86. ⟨10.1016/j.nucengdes.2018.01.009⟩
Nuclear Engineering and Design, 2018, 330, pp.72-86. ⟨10.1016/j.nucengdes.2018.01.009⟩
Nuclear Engineering and Design, Elsevier, 2018, 330, pp.72-86. ⟨10.1016/j.nucengdes.2018.01.009⟩
International audience; The MEXIICO project carried out by the CEA and supported by EDF and AREVA has the objective to characterize the behaviour of irradiated fuel pellet issued from nuclear water reactor during power transients. The MEXIICO experim
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::562a8d5bc13498d758dc41d382612b31
https://hal-cea.archives-ouvertes.fr/cea-02063619
https://hal-cea.archives-ouvertes.fr/cea-02063619
Publikováno v:
EPJ Web of Conferences, Vol 170, p 04005 (2018)
ANIMMA2017 International conference on advancements in nuclear instrumentation measurement methods and their applications
ANIMMA2017 International conference on advancements in nuclear instrumentation measurement methods and their applications, Jun 2017, Liege, Belgium
ANIMMA2017 International conference on advancements in nuclear instrumentation measurement methods and their applications
ANIMMA2017 International conference on advancements in nuclear instrumentation measurement methods and their applications, Jun 2017, Liege, Belgium
International audience; CABRI is an experimental pulse reactor, funded bythe French Nuclear Safety and Radioprotection Institute (IRSN)and operated by CEA at the Cadarache research center. It isdesigned to study fuel behavior under RIA conditions. In
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::cfdad9fabf7158d59603a4ac6eb3810e
https://doaj.org/article/2b8ca86ad9b24dcba81e742369926a19
https://doaj.org/article/2b8ca86ad9b24dcba81e742369926a19
Autor:
Thierry Cadiou, Manuel Saez, Johann Quenaut, Mark Tothill, Hong-Son Pham, Olivier Gastaldi, Jean-Henry Ferrasse, Nicolas Alpy, Olivier Boutin
Publikováno v:
International Journal of Heat and Fluid Flow
International Journal of Heat and Fluid Flow, Elsevier, 2016, 61 (Part B), pp.379-394. ⟨10.1016/j.ijheatfluidflow.2016.05.017⟩
International Journal of Heat and Fluid Flow, 2016, 61 (Part B), pp.379-394. ⟨10.1016/j.ijheatfluidflow.2016.05.017⟩
International Journal of Heat and Fluid Flow, Elsevier, 2016, 61 (Part B), pp.379-394. ⟨10.1016/j.ijheatfluidflow.2016.05.017⟩
International Journal of Heat and Fluid Flow, 2016, 61 (Part B), pp.379-394. ⟨10.1016/j.ijheatfluidflow.2016.05.017⟩
International audience; One of the challenges in the performance prediction of the supercritical CO2 (sc-CO2) compressor is the real gas behavior of the working fluid near the critical point. This study deals with the establishment of an approach tha
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a0cfd6a2391928bfe51dd8ddbb30509e
https://hal.archives-ouvertes.fr/hal-01461787
https://hal.archives-ouvertes.fr/hal-01461787
Autor:
Thierry Cadiou, Marc Berthoux
Publikováno v:
Nuclear Engineering and Design. 240:3372-3386
The ALLEGRO project, led by the CEA in the European framework, is devoted to the conception and the building of the first Gas cooled Fast Reactor (GFR) demonstrator. In order to fulfil this ambitious challenge, the ESTHAIR program has the objective t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4b5312dcf909cbd63f34f4d225205430
https://doi.org/10.1016/j.nucengdes.2010.07.009
https://doi.org/10.1016/j.nucengdes.2010.07.009
Autor:
Thierry Cadiou, Jacky Louvet
Publikováno v:
Nuclear Technology. 153:256-263
Upon request of the French Safety Authorities, the transient phase, initiated by a total instantaneous blockage (TIB) in a Phenix reactor fuel assembly, has been investigated. Based on an experimental program performed with the SCARABEE reactor, the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::db141b0c3f20da7a9469cb0a1740d790
https://doi.org/10.13182/nt06-a3705
https://doi.org/10.13182/nt06-a3705
Publikováno v:
2013 3rd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and their Applications (ANIMMA).
The objective of the study is to understand the thermal hydraulics in a core sub-assembly with liquid sodium as coolant by performing detailed numerical simulations. The passage for the coolant flow between the fuel rods is maintained by thin wires w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::23811f3c6715439a20be4fd69e2f5e11
https://doi.org/10.1109/animma.2013.6728099
https://doi.org/10.1109/animma.2013.6728099