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Modeling Temperature Distributions in a Nuclear Fuel Rod With the Integral Technique

[+] Author Affiliations
Chris J. Kobus

Oakland University, Rochester, MI

Paper No. HT2013-17095, pp. V004T19A005; 6 pages
doi:10.1115/HT2013-17095
From:
  • ASME 2013 Heat Transfer Summer Conference collocated with the ASME 2013 7th International Conference on Energy Sustainability and the ASME 2013 11th International Conference on Fuel Cell Science, Engineering and Technology
  • Volume 4: Heat and Mass Transfer Under Extreme Conditions; Environmental Heat Transfer; Computational Heat Transfer; Visualization of Heat Transfer; Heat Transfer Education and Future Directions in Heat Transfer; Nuclear Energy
  • Minneapolis, Minnesota, USA, July 14–19, 2013
  • Conference Sponsors: Heat Transfer Division
  • ISBN: 978-0-7918-5550-8
  • Copyright © 2013 by ASME

abstract

There is a large amount of research in the modeling of nuclear reactor fuel rods for various parameters amongst which the temperature is high on the list, reason being the critical temperature limit above which control of geometry will be lost as a meltdown or a partial meltdown may occur. Much of this research involves complex numerical models that are of little help especially to students learning the basics of nuclear engineering and heat transfer. This paper will explore the possibility of utilizing the integral technique for such modeling. The advantage of the technique is its simplicity which comes at the cost of some accuracy. An example is given here for a simplified cross-sectional geometry to illustrate how this modeling is done, and why it may be a superior technique to at least introduce students to the concept, but which may have applications to research in the field as well.

Copyright © 2013 by ASME

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