Heat transfer and fluid flow in a molten pool are influenced by internal volumetric heat generated from the radioactive decay of fission product species retained in the pool. The pool superheat is determined based on the overall energy balance that equates the heat production rate to the heat loss rate. Decay heat of fission products in the pool was estimated by product of the mass concentration and energy conversion factor of each fission product. For the calculation of heat generation rate in the pool, twenty-nine elements were chosen and classified by their chemical properties. The mass concentration of a fission product is obtained from released fraction and the tabular output of the ORIGEN 2 code. The initial core and pool inventories at each time can also be estimated using ORIGEN 2. The released fraction of each fission product is calculated based on the bubble dynamics and mass transport. Numerical analysis was performed for the TMI-2 accident. The pool is assumed to be a partially filled hemispherical geometry and the change of pool geometry during the numerical calculation was neglected. Results of the numerical calculation revealed that the peak temperature of the molten pool significantly decreased and most of the volatile fission products were released from the molten pool during the accident.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3597-9
PROCEEDINGS PAPER
Heat and Fission Product Transport in a Molten U-Zr-O Pool With Crust
K. Y. Suh,
K. Y. Suh
Seoul National University, Seoul, Korea
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C. S. Kang
C. S. Kang
Seoul National University, Seoul, Korea
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J. I. Yun
FNC Technology Company, Seoul, Korea
K. Y. Suh
Seoul National University, Seoul, Korea
C. S. Kang
Seoul National University, Seoul, Korea
Paper No:
ICONE10-22438, pp. 723-728; 6 pages
Published Online:
March 4, 2009
Citation
Yun, JI, Suh, KY, & Kang, CS. "Heat and Fission Product Transport in a Molten U-Zr-O Pool With Crust." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 14–18, 2002. pp. 723-728. ASME. https://doi.org/10.1115/ICONE10-22438
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