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Science and Technology of Nuclear Installations
Volume 2012, Article ID 247482, 9 pages
Research Article

Validation and Application of the Thermal Hydraulic System Code TRACE for Analysis of BWR Transients

1Institute for Neutron Physics and Reactor Technology (INR), Karlsruhe Institute of Technology (KIT), 76344 Eggenstein-Leopoldshafen, Germany
2TÜV SÜD Industrie Service GmbH, Westendstraße 199, 80686 Munich, Germany
3Westinghouse Electric Germany GmbH, 68140 Mannheim, Germany

Received 13 April 2012; Accepted 7 August 2012

Academic Editor: Boštjan Končar

Copyright © 2012 V. H. Sánchez et al. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Linked References

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  3. K. Nikitin, J. Judd, G. M. Grandi, A. Manera, and H. Ferroukhi, “Peach bottom 2 turbine trip 2 simulation by TRACE/S3K coupled code,” in Proceedings of the Advances in Reactor Physics to Power the Nuclear Renaissance Pittsburgh Conference (PHYSOR '10), pp. 2283–2293, CD-ROM, American Nuclear Society, Pittsburgh, Pa, USA, May 2010. View at Scopus
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