For countermeasure of the station black out, an isolation condenser (IC) with enhancing direct-current power supply system is one of effective devices. But not so much transient heat transfer data were obtained for full scale ICs. The IC performance at the accident of the Fukushima daiichi nuclear power plant unit 1 was evaluated by TRACG code. The pressure of reactor pressure vessel was well simulated to measurements.
- Nuclear Engineering Division
Analysis of Isolation Condenser Behavior by TRACG Code
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Ishii, Y, Nakadozono, N, & Ochi, H. "Analysis of Isolation Condenser Behavior by TRACG Code." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes. Chengdu, China. July 29–August 2, 2013. V003T06A046. ASME. https://doi.org/10.1115/ICONE21-16671
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