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Analysis of Isolation Condenser Behavior by TRACG Code

[+] Author Affiliations
Yoshihiko Ishii, Naoyuki Nakadozono

Hitachi, Ltd., Hitachi, Ibaraki, Japan

Hitoshi Ochi

Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan

Paper No. ICONE21-16671, pp. V003T06A046; 5 pages
  • 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
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5580-5
  • Copyright © 2013 by ASME


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.

Copyright © 2013 by ASME



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