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원자로공동냉각계통 실험을 위한 표면 처리에 따른 SS400 표면 열방사율 측정
김찬수(C. S. Kim),김종환(J. H. Kim),김응선(E. S. Kim),배윤영(Y. Y. Bae),김민환(M. H. Kim) 대한기계학회 2013 대한기계학회 춘추학술대회 Vol.2013 No.12
After the Fukushima accident, future nuclear systems are especially focused on a passive safety without additional external electricity. A Very High Temperature gas-cooled Reactor (VHTR) has shown great chance for its inherent safety. Its safety feature is the Reactor Cavity Cooling System (RCCS), which can remove the nuclear residual heat by natural convection and radiation without additional electricity and coolant injection. KAERI is constructing the RCCS thermo-hydraulic experimental facility. In this study, the emissivity with various surface modificiation conditions were measured to simulate the radiation heat transfer between the reactor vessel and RCCS.