2016 Annual Meeting

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Oral Presentation

III. Fission Energy Engineering » 304-1. Thermal Hydraulics, Energy Conversion, Energy Transfer, Energy Storage

[3C01-04] Core Thermal Hydraulics

Mon. Mar 28, 2016 9:30 AM - 10:35 AM Room C (Lecture Rooms B B103)

Chair: Hiroyuki Yoshida (JAEA)

9:30 AM - 9:45 AM

[3C01] Critical Heat Flux in Tight Lattice Three-Pin Bundle with and without Wire Spacer

Dan Le1, ＊Sho Tanabe1, Minoru Takahashi2, Masatoshi Kondo2 (1.Department of Nuclear Engineering, Tokyo Institute of Technology, 2.Research Laboratory for Nuclear Reactor, Tokyo Institute of Technology)

Keywords:Critical heat flux, Tight lattice, Two-phase, Wire spacer, Bundle pin

Critical heat flux (CHF) behavior in tight lattice core in boiling two-phase flow was clarified experimentally for three-pins tight rod bundle with wire spacer with the parameter of the ration of pitch to diameter ratio (p/d).