[3K10-15] Two-Phase Flow and Phase Change 3

[3K13] Fundamental study on critical heat flux in tight lattice core of Reduced-moderation Boiling Water Reactor

*Sho Tanabe¹, Masatoshi Kondo², Minoru Takahashi² (1. Department of Nuclear Engineering, Tokyo Institute of Technology, 2. Laboratory for Advanced Nuclear Energy, Tokyo Institute of Technology)

Keywords:Reduced-moderation Boiling Water Reactor, Critical heat flux, tight lattice core, boiling two-phase flow, spacer

The effect of spacer on critical heat flux (CHF) in tight lattice core was investigated experimentally using a simulated fuel assembly. The effects of a long wire spacer and the multi-steps of short wire spacers on CHF were clarified. The effect of the pitch of the long wire on CHF was small.As the number of the short spacers was increased, the CHF value was increased.