Core degradation experiment will be conducted in Fuel Rod Melt Progression apparatus (FROMA) to investigate the distribution of mass and energy in designed fuel rod during a core degradation process. Numerical research on the core degradation experiment is mainly to evaluate the designed parameters of FROMA. The pre-numerical study was conducted using the widely accepted severe accident analysis software MELCOR. The fuel rods used in the experiment consisted of real reactor fuel elements, and the designed fuel rods were electrically heated with internal center tungsten-rhenium rod to a very high temperature. Numerical analysis model is described, and the input parameters are in accord with experimental conditions. In the transient period of core degradation, the production hydrogen and the distribution of mass and temperature are obtained. All the predicted MELCOR results will be compared with the experimental measurements.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5153-1
PROCEEDINGS PAPER
Numerical Research on Fuel Rod Progression During Core Degradation Process Using MELCOR
Tangtao Feng,
Tangtao Feng
Xi'an Jiaotong University, Xi'an, China
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Wenxi Tian,
Wenxi Tian
Xi'an Jiaotong University, Xi'an, China
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Ping Song,
Ping Song
Xi'an Jiaotong University, Xi'an, China
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Jun Wang,
Jun Wang
University of Wisconsin-Madison, Madison, WI
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Mingjun Wang,
Mingjun Wang
Xi'an Jiaotong University, Xi'an, China
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G. H. Su,
G. H. Su
Xi'an Jiaotong University, Xi'an, China
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Suizheng Qiu
Suizheng Qiu
Xi'an Jiaotong University, Xi'an, China
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Tangtao Feng
Xi'an Jiaotong University, Xi'an, China
Wenxi Tian
Xi'an Jiaotong University, Xi'an, China
Ping Song
Xi'an Jiaotong University, Xi'an, China
Jun Wang
University of Wisconsin-Madison, Madison, WI
Mingjun Wang
Xi'an Jiaotong University, Xi'an, China
G. H. Su
Xi'an Jiaotong University, Xi'an, China
Suizheng Qiu
Xi'an Jiaotong University, Xi'an, China
Paper No:
ICONE26-81738, V009T16A049; 5 pages
Published Online:
October 24, 2018
Citation
Feng, T, Tian, W, Song, P, Wang, J, Wang, M, Su, GH, & Qiu, S. "Numerical Research on Fuel Rod Progression During Core Degradation Process Using MELCOR." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 9: Student Paper Competition. London, England. July 22–26, 2018. V009T16A049. ASME. https://doi.org/10.1115/ICONE26-81738
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