Often a forced convection heat transfer coefficient is used to calculate the peak fuel temperature for a rectangular lattice TRIGA core even though the core is cooled by natural convection. The arguments for applying a forced convection empirical relationship are examined and another relationship is suggested. The peak fuel temperature was calculated using two different correlations, Dittus-Boelter and natural convection, for pool temperatures of 30°C and 60°C. The Dittus-Boelter correlation predicted a fuel temperature rise of 1.85°C for this difference in pool temperature, contrary to the predicted rise of 25.64°C from natural convection relationships. Experimental data shows that the relationship of fuel temperature rise with increasing pool temperature is more accurately represented by the natural convection correlation than with Dittus-Boelter. Using a derived natural convection correlation, the calculated peak fuel temperatures then closely match measured data. A procedure was developed to access convective heat transfer coefficient changes in the cladding gap as a function of reactor power for the hot channel which are similar to those presented in literature.
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2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference
July 30–August 3, 2012
Anaheim, California, USA
Conference Sponsors:
- Nuclear Engineering Division
- Power Division
ISBN:
978-0-7918-4497-7
PROCEEDINGS PAPER
A New Approach to Calculating Fuel Temperature in TRIGA Mark I Research Reactors Available to Purchase
Jesse M. Johns,
Jesse M. Johns
Texas A&M University, College Station, TX
Search for other works by this author on:
W. D. Reece
W. D. Reece
Texas A&M University, College Station, TX
Search for other works by this author on:
Jesse M. Johns
Texas A&M University, College Station, TX
W. D. Reece
Texas A&M University, College Station, TX
Paper No:
ICONE20-POWER2012-54921, pp. 631-637; 7 pages
Published Online:
October 30, 2013
Citation
Johns, JM, & Reece, WD. "A New Approach to Calculating Fuel Temperature in TRIGA Mark I Research Reactors." Proceedings of the 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries. Anaheim, California, USA. July 30–August 3, 2012. pp. 631-637. ASME. https://doi.org/10.1115/ICONE20-POWER2012-54921
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