Heat Transfer Study for Thermal-Hydraulic Design of the Soild-Target of Spallation Neutron Source

概要

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In relation to thermal-hydraulic design of the solid-target system of a spallation neutron source, heat transfer experiments were performed to obtain experimental data systematically on heat transfer coefficient and critical heat flux (CHF) for vertical upward and horizontal flows in thin rectangular channels simulating a coolant channel of the proposed spallation neutron source. Single phase heat transfer coefficients and CHF data for rectangular channels with 1.0 mm gap (Lh⁄De=50.2) with mass flux of 10–7,500 kg/m2·s, single phase and two phase heat transfer coefficients, onset of nucleate boiling (ONB) and CHF data for 1.5 mm gap (Lh⁄De=33.9) with mass flux of 10–5,000 kg/m2·s were obtained in the atmospheric pressure with inlet subcooling of 40–80 K. Finally, thermal-hydraulic correlations that could be used for design calculations were proposed based on the obtained data.
社団法人日本原子力学会の論文
2001-10-25