The 10MW High Temperature Gas Cooled Test Reactor (HTR-10) has been built in Institute of Nuclear and New Energy Technology (INET) and has been operating successfully since the beginning of 2003. The core outlet temperature of HTR-10 is 700°C. To verify the technology of gas-turbine direct cycle, INET has planned to increase its core outlet temperature to 750°C and use a helium gas turbine instead of the steam generator (then the reactor is called HTR-10GT). Though HTR-10 has good intrinsic safety, the design basic accidents and beyond design basic accidents of HTR10-GT must be analyzed according to China’s nuclear regulations due to changed operation parameters. THERMIX code system is used to study the accident on one control rod withdrawal out of the core by a mistake. After a control rod in the side reflector was withdrawn out at a speed of 1 cm/s by a mistake, a positive reactivity was inserted and the reactor power increased and the temperature of the core increased. When the neutron flux of power measuring range exceeded 123% and the core outlet temperature was lager than 800°C, the reactor was scrammed. During the accident sequence the maximum fuel temperature was 1200.9°C. It was lower than the fuel temperature limitation of 1230°C. The paper compares the analysis result of HTR10-GT to those of HTR-10. The results shows that the HTR-10GT is still safe during the accident though its operating temperature is higher than HTR-10 when the fuel safety limits are the same.
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14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4246-0
PROCEEDINGS PAPER
The DBA Analysis of One Control Rod Withdrawal Out of the HTR-10GT Core
Mingang Lang,
Mingang Lang
Tsinghua University, Beijing, China
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Yujie Dong
Yujie Dong
Tsinghua University, Beijing, China
Search for other works by this author on:
Mingang Lang
Tsinghua University, Beijing, China
Yujie Dong
Tsinghua University, Beijing, China
Paper No:
ICONE14-89172, pp. 63-68; 6 pages
Published Online:
September 17, 2008
Citation
Lang, M, & Dong, Y. "The DBA Analysis of One Control Rod Withdrawal Out of the HTR-10GT Core." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 5: Safety and Security; Low Level Waste Management, Decontamination and Decommissioning; Nuclear Industry Forum. Miami, Florida, USA. July 17–20, 2006. pp. 63-68. ASME. https://doi.org/10.1115/ICONE14-89172
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