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Thermal-hydraulic calculations for a fuel assembly in a European Pressurized Reactor using the RELAP5 code Cover

Thermal-hydraulic calculations for a fuel assembly in a European Pressurized Reactor using the RELAP5 code

By: Maciej Skrzypek and  R. Laskowski  
Open Access
|Sep 2015

References

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  2. 2. Pairot, F. (2011). Nuclear design. The pre-construction safety report (PCSR) (Chapter 4.3).
  3. 3. Scientech, Inc. (1998). RELAP5/MOD3 code manual. Volume I: code structure, system models and solution methods. Rockville, Maryland, Idaho Falls, Idaho.
  4. 4. Framatome ANP, Inc. (2005). EPR design description. Lynchburg.
  5. 5. U.S. NRC. (2013). EPR fi nal safety report (Chapter 4.3 Nuclear design).
  6. 6. Anglart, H. (2010). Thermal-hydraulics in nuclear systems. Stockholm: Kungliga Tekniska Högskolan.
  7. 7. Cathcart, J. V. (1977). Reaction rate studies, IV, Zirconium metal-water oxidation kinetics. Oak Ridge National Laboratory. (ORNL/NUREG-17).10.2172/7317596
DOI: https://doi.org/10.1515/nuka-2015-0110 | Journal eISSN: 1508-5791 | Journal ISSN: 0029-5922
Language: English
Page range: 537 - 544
Submitted on: Sep 24, 2014
Accepted on: May 20, 2015
Published on: Sep 25, 2015
Published by: Institute of Nuclear Chemistry and Technology
In partnership with: Paradigm Publishing Services
Publication frequency: 4 issues per year

© 2015 Maciej Skrzypek, R. Laskowski, published by Institute of Nuclear Chemistry and Technology
This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.