High temperature gas-cooled reactor (HTGR), especially the pebble-bed core type reactor, will inevitably cause the wear the graphite components and generate graphite dust in the core. The graphite dust is taken away by helium coolant and deposited on the surface of the primary circuit, and the fission products may be absorbed on the dust. Since it is possible that the fission products are released with dust under the accident conditions such as depressurization events, they have a potential hazard of radiation exposure to the environment. The objective of this paper is to develop a code for calculating the behaviour of graphite dust in the primary circuit of HTGR. The paper is focused on development of models for predicting the deposition rates of the dust. The purpose of the work is to estimate the amount and distribution of deposited dust during plant life time, which was assumed to be 40 full-power years. The result will lay the foundation for further studies of fission products releasing and interaction with dust under accident conditions.
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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
Development of Modeling Transport of Graphite Dust in HTGR During Normal Operation Condition
Zhipeng Chen,
Zhipeng Chen
Tsinghua University, Beijing, China
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Yanhua Zheng,
Yanhua Zheng
Tsinghua University, Beijing, China
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Fu Li
Fu Li
Tsinghua University, Beijing, China
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Zhipeng Chen
Tsinghua University, Beijing, China
Fei Xie
Tsinghua University, Beijing, China
Yanhua Zheng
Tsinghua University, Beijing, China
Lei Shi
Tsinghua University, Beijing, China
Fu Li
Tsinghua University, Beijing, China
Paper No:
ICONE20-POWER2012-54390, pp. 291-297; 7 pages
Published Online:
October 30, 2013
Citation
Chen, Z, Xie, F, Zheng, Y, Shi, L, & Li, F. "Development of Modeling Transport of Graphite Dust in HTGR During Normal Operation Condition." 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. 291-297. ASME. https://doi.org/10.1115/ICONE20-POWER2012-54390
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