Closed Brayton cycle (CBC) coupled with High Temperature Gas-cooled Reactor (HTGR) has potential application due to its compact configuration, high power generation efficiency and inherent safety. It is also one of the major power conversion methods for Generation IV advanced nuclear power systems. The typical CBC has several helium-water heat exchangers, including pre-cooler and inter-cooler. These helium-water heat exchangers have important influence on the performance of power conversion system, especially in loss-of-flow accidents (LOFAs). A system model including the reactor and the energy conversion system was established in this paper. The 10MW High Temperature Gas-cooled reactor-test Module helium Gas Turbine (HTR-10GT) was taken as the example to show the consequences of LOFAs. The results showed that LOFAs led to the rising of water temperature out of heat exchangers. With the reduction of water flow rate, the maximum water temperature would increase sharply, and the water temperature in pre-cooler was higher than that in inter-cooler. At low water flow rate, the water temperature would exceed the boiling point. LOFAs also made the rising of helium temperature. It had impacts on the performance of helium compressors. The elevated inlet temperature of helium compressors changed the corrected speed and corrected flow rate, therefore caused the deterioration of compressor’s performance. Furthermore, the LOFAs caused the reactor inlet temperature increasing. In low water flow rate, it would make the reactor inlet temperature beyond the temperature limitation of reactor pressure vessel and influence the safety of reactor. And the LOFAs also reduced the output work of cycle. This paper provides insights of features of CBC in LOFAs and will be helpful to the design and safety operation of closed Brayton cycle coupled with HTGR.
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ASME 2018 Nuclear Forum collocated with the ASME 2018 Power Conference and the ASME 2018 12th International Conference on Energy Sustainability
June 24–28, 2018
Lake Buena Vista, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5154-8
PROCEEDINGS PAPER
Analysis of Loss-of-Flow Accidents in Pre-Cooler and Inter-Cooler of HTR-10GT
Xiaoyong Yang,
Xiaoyong Yang
Tsinghua University, Beijing, China
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Xiao Li,
Xiao Li
China United Gas Turbine Technology Co., Ltd., Beijing, China
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Youjie Zhang
Youjie Zhang
Tsinghua University, Beijing, China
Search for other works by this author on:
Xiaoyong Yang
Tsinghua University, Beijing, China
Xiao Li
China United Gas Turbine Technology Co., Ltd., Beijing, China
Jie Wang
Tsinghua University, Beijing, China
Youjie Zhang
Tsinghua University, Beijing, China
Paper No:
NUCLRF2018-7381, V001T04A001; 6 pages
Published Online:
October 4, 2018
Citation
Yang, X, Li, X, Wang, J, & Zhang, Y. "Analysis of Loss-of-Flow Accidents in Pre-Cooler and Inter-Cooler of HTR-10GT." Proceedings of the ASME 2018 Nuclear Forum collocated with the ASME 2018 Power Conference and the ASME 2018 12th International Conference on Energy Sustainability. ASME 2018 Nuclear Forum. Lake Buena Vista, Florida, USA. June 24–28, 2018. V001T04A001. ASME. https://doi.org/10.1115/NUCLRF2018-7381
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