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Ho, H. Q.; Honda, Yuki; Goto, Minoru; Takada, Shoji
no journal, ,
Yoshikawa, Ryuji; Imai, Yasutomo*; Tanaka, Masaaki; Ohshima, Hiroyuki
no journal, ,
Accurate evaluation of three-dimensional temperature distribution is essentially required for the structural integrity analysis of large-sized straight tube steam generator (SG) of an advanced Sodium-cooled Fast Reactor (SFR). Numerical simulation system to analyze three-dimensional thermal-hydraulics in the straight tube SG has been developed. The three-dimensional simulation on sodium side by the CFD code FLUENT with porous body model was coupled with the multi-channel simulation on water/steam side. Synthetic numerical simulation model of the SG including inlet and outlet plenums were constructed. Through the numerical simulation at the condition with plugged tubes, the characteristic three-dimensional distributions of velocity in the plenum and temperature distribution in the tube bundle were successfully analyzed.
Kanda, Hironori; Onojima, Takamitsu; Suzuki, Masashi; Imamura, Hiroaki; Tanaka, Masaaki; Murakami, Satoshi*
no journal, ,
The flow rate of the primary coolant system in natural circulation decay heat removal operation is reduced much lower than that in rated operation in Next generation sodium-cooled fast reactor. The electromagnetic flow meters have uncertainty on the indicated value at low flow rates conditions. Ensuring the measurement accuracy of electromagnetic flow meter is presumed to contribute the promotion of understanding of thermal hydraulics phenomena such as natural circulation in the fast reactor. In this paper, low flow rate evaluation method has been examined preliminarily by transport time-delay analysis of temperature fluctuation in sodium circulation loop. Measured data and evaluation results from temperature fluctuations which have been acquired in sodium-loop in AtheNa, indicate that this evaluation method can be applied to estimate flow rate in natural circulation decay heat removal operation.