Two-Phase Flow Heat Transfer in Nuclear Reactor Systems | Zendy

Boštjan Končar | Zendy; Eckhard Krepper | Zendy; Dominique Bestion | Zendy; Chul-Hwa Song | Zendy; Yassin A. Hassan | Zendy

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Two-Phase Flow Heat Transfer in Nuclear Reactor Systems

Author(s) -

Boštjan Končar,

Eckhard Krepper,

Dominique Bestion,

Chul-Hwa Song,

Yassin A. Hassan

Publication year - 2013

Publication title -

science and technology of nuclear installations

Language(s) - English

Resource type - Journals

SCImago Journal Rank - 0.417

H-Index - 24

eISSN - 1687-6083

pISSN - 1687-6075

DOI - 10.1155/2013/587839

Subject(s) - nuclear engineering , research reactor , heat transfer , energy transfer , division (mathematics) , engineering , technical university , nuclear physics , environmental science , library science , engineering physics , physics , thermodynamics , computer science , mathematics , arithmetic , neutron

1 Reactor Engineering Division, Jožef Stefan Institute, Jamova 39, 1000 Ljubljana, Slovenia 2Helmholtz-Zentrum Dresden-Rossendorf, Institute of Fluid Dynamics, Bautzner Landstrase 400, 01328 Dresden, Germany 3 Commissariat a l’Energie Atomique (CEA), 17 rue des Martyrs, 38054 Grenoble, France 4Thermal-Hydraulic Safety Research Division, Korea Atomic Energy Research Institute (KAERI), Daedeok-daero 989-111, Yuseong-gu, Daejeon 305-353, Republic of Korea 5 Department of Nuclear Engineering, Texas A&M University, 3133 Tamu, College Station, TX 77843-3133, USA

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