[3C01-04] 炉心熱流動

[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)

キーワード：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).