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Thermal-Hydraulic Simulations of Guard Containment in Depressurization Accidents of a Gas-Cooled Fast Reactor

[+] Author Affiliations
Zhanjie Xu, Thomas Jordan

Karlsruhe Institute of Technology, Karlsruhe, Germany

Paper No. ICONE21-15955, pp. V003T06A029; 9 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


A gas-cooled fast reactor is designed as an advanced nuclear reactor in next generation in the EU. In depressurization accident scenarios, pressurization caused by a release of helium from the primary system with a higher pressure into the guard containment would endanger the integrity of the containment. In the design stage, the released source term is analyzed theoretically, and is applied as a boundary condition in the 3D CFD code simulation to the transient pressurization process. The simulation results supply a reference value about the design pressure of the containment.

Copyright © 2013 by ASME



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