Design and Engineering Verification of HTR-PM Fuel Handling

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Abstract. HTR-PM is a twin-reactor structure pebble bed modular reactor. With the gather-scatter fuel handling system (FHS), handling and circulating function of twin reactors’ fuel elements are performed under a non-shutdown continuous condition. Relying on separate pipeline system of sphere fuel main circulation, FHS achieved automatic operation in the structural model by sphere fuel’s gravity flowing and pneumatic conveying in the twin reactors. The FHS adopted the international experience at design and operation of similar systems, especially based on that of HTR-10. However, some key components and technologies were improved so that fuel handling of HTR-PM becomes more reliable. All of the improved components and technologies will be tested in a full-scale hot testing facility, and some of them were verified and validated with the help of separated cold testing facilities. The functions and design of HTR-PM FHS is introduced in this paper. Design and engineering test of the FHS in HTR-PM demonstration power plant are reviewed.

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317-325

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December 2012

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© 2013 Trans Tech Publications Ltd. All Rights Reserved

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[1] J. G. Liu, H. L. Xiao, C. P. Li, Design and full scale test of the fuel handling system, Nuclear Engineering and Design. 218, ( 2002) 169-178.

DOI: 10.1016/s0029-5493(02)00188-7

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[2] J. G. Liu, H. L. Xiao, M. Xi, Hot testing facility of HTR-10 fuel circulation system, Joural of Tsinghua University (Sci & Tech) (in Chinese). Vol. 37, (1997) No. 5, pp.20-28.

Google Scholar

[3] J. G. Liu, X. H. Lian, P. Huang, Transportation of Fuel Element in HTR-10, Nuclear Power Engineering (in Chinese). Vol. 22, (2001)No. 6, pp.526-529.

Google Scholar

[4] Z. D. Han, T. F. Liu, Q. X. Ma, External detection system for ball fuel elements in high temperature gas cooled reactors, Joural of Tsinghua University (Sci & Tech) (in Chinese). Vol. 47, (2007) No. 8, pp.1259-1262.

Google Scholar