Source: Proceedings of the 11th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-11), Gyeongju, Korea, Oct. 9-13 2016 ; NUTHOS-11: The 11th International Topical

تفاصيل العنوان

اقرأ أكثر حفظ في قائمتي

Conference

Fast Transients and Critical heat flux for experimental reactors applications

Authors : Dorville, N.;

Subjects: flux critique; borax; transitoire exponentiel de puissanceParis; France

Source: Workshop on Numerical and Physical Modelling in Multiphase Flows ; https://cea.hal.science/cea-02339283 ; Workshop on Numerical and Physical Modelling in Multiphase Flows, Feb 2018, Paris, France

تفاصيل العنوان

اقرأ أكثر حفظ في قائمتي

Conference

A critical heat flux model for flow boiling in the ivr conditions

Authors : Hae Min, P.; Carnevali, S.; Gaudier, F. ...

Subjects: CHF; IVR; Uranie codeKyoto; JapanKyoto, Japan

Source: ICAPP 2017 ; https://hal.science/hal-02419627 ; ICAPP 2017, Apr 2017, Kyoto, Japan

تفاصيل العنوان

اقرأ أكثر حفظ في قائمتي

Conference

Towards modeling the impact of the aspect ratio in an energy model describing the transient flow boiling at high subcooling

Authors : Roumet, Elie; Nop, Raksmy; Dorville, Nicolas ...

Subjects: Flow boiling; Critical heat flux; Exponential power escalationKobe; Japan

Source: ICMF 2023 - 11th International Conference on Multiphase Flow ; https://cea.hal.science/cea-04440542 ; ICMF 2023 - 11th International Conference on Multiphase Flow, Apr 2023, Kobe, Japan

تفاصيل العنوان

اقرأ أكثر حفظ في قائمتي

Academic Journal

An energy model for the transient flow boiling crisis under highly subcooled conditions at atmospheric pressure

Authors : Nop, R.; Duluc, Marie-Christine; Dorville, N. ...

Subjects: Subcooled flow boiling crisis; Critical heat flux; Exponential power escalation

Source: ISSN: 1290-0729 ; International Journal of Thermal Sciences ; https://cnam.hal.science/hal-03605923 ; International Journal of Thermal Sciences, 2021, 168, pp.107042.

تفاصيل العنوان

اقرأ أكثر حفظ في قائمتي

Dissertation/ Thesis

Study of a boiling dielectric fluid in a vertical mini-channel : application to the thermal management of battery packs ; Etude de l’ébullition d’un fluide diélectrique en mini-canal vertical : application au contrôle thermique des packs batteries

Authors : Lioger--Arago, Robin;

Subjects: Boiling; Mini-Channel; Inverse method

Source: https://theses.hal.science/tel-04127164 ; Génie mécanique [physics.class-ph]. Université Grenoble Alpes [2020-.], 2023. Français. ⟨NNT : 2023GRALI022⟩.

تفاصيل العنوان

اقرأ أكثر حفظ في قائمتي

Dissertation/ Thesis

Experimental investigation and modeling of the transient flow boiling crisis of water at moderate pressure and high subcooling ; Étude expérimentale et modélisation de la crise d'ébullition en transitoire rapide de l'eau à fort sous-refroidissement et à pression modérée

Authors : Nop, Raksmy;

Subjects: Critical heat flux; Transient Flow Boiling Crisis; Exponential power escalation

Source: https://theses.hal.science/tel-03081992 ; Fluid mechanics [physics.class-ph]. Université Paris-Saclay, 2020. English. ⟨NNT : 2020UPAST046⟩.

تفاصيل العنوان

اقرأ أكثر حفظ في قائمتي

Academic Journal

Boiling phenomena in near-critical SF6 observed in weightlessness

Authors : Lecoutre-Chabot, Carole; Garrabos, Yves; Beysens, Daniel, Null ...

Subjects: Microgravity experiment; Sulphur hexafluoride; Liquid-gas critical point

Source: ISSN: 0094-5765.

تفاصيل العنوان

اقرأ أكثر حفظ في قائمتي

Conference

Prediction of annular flows in vertical pipes with new correlations for the CATHARE-3 three-field model

Authors : Spirzewski, M.; Fillion, P.; Valette, M. ...

Subjects: CATHARE; three-field model; annular flowXi'An; China

Source: 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17)https://cea.hal.science/cea-0243403717th International Topical Meeting on Nuclear Reactor Thermal

تفاصيل العنوان

اقرأ أكثر حفظ في قائمتي

Conference

Application of SAPIUM guidelines to Input Uncertainty Quantification: the ATRIUM project

Authors : Ghione, Alberto; Sargentini, Lucia; Damblin, Guillaume ...

Subjects: Inverse Uncertainty Quantification; BEPU; Thermal-hydraulic codeWashington DC; United StatesWashington DC, United States

Source: 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 20)https://cea.hal.science/cea-0419107920th International Topical Meeting on Nuclear Reactor Thermal

تفاصيل العنوان

اقرأ أكثر حفظ في قائمتي

نتائج البحث

فلترة النتائج

Assessment of Critical Heat Flux correlations in narrow rectangular channels

Fast Transients and Critical heat flux for experimental reactors applications

A critical heat flux model for flow boiling in the ivr conditions

Towards modeling the impact of the aspect ratio in an energy model describing the transient flow boiling at high subcooling

An energy model for the transient flow boiling crisis under highly subcooled conditions at atmospheric pressure

Study of a boiling dielectric fluid in a vertical mini-channel : application to the thermal management of battery packs ; Etude de l’ébullition d’un fluide diélectrique en mini-canal vertical : application au contrôle thermique des packs batteries

Experimental investigation and modeling of the transient flow boiling crisis of water at moderate pressure and high subcooling ; Étude expérimentale et modélisation de la crise d'ébullition en transitoire rapide de l'eau à fort sous-refroidissement et à pression modérée

Boiling phenomena in near-critical SF6 observed in weightlessness

Prediction of annular flows in vertical pipes with new correlations for the CATHARE-3 three-field model

Application of SAPIUM guidelines to Input Uncertainty Quantification: the ATRIUM project

اتصل بنا

اتبع