A control and operation method of a High Temperature Gas Cooled Reactor (HTGR) power plant with Steam Cycle has been investigated, and an adequacy of the method has been examined by plant dynamics analyses. In this plant, the steam cycle system with regenerative and reheat cycle is employed, where the heat generated in the reactor is transferred to the secondary coolant (water and steam) through the steam generator (SG), which has the steam turbine and generator, is installed in the secondary system. The reactor and steam cycle system control methods were evaluated. Analytical results through system modeling concluded that the reactor power changes could be effectively achieved by utilizing primary system helium flow rate control, and overall plant system responsiveness and control could be achieved by employing feed water flow control system and turbine governor control system. The plant dynamics analysis code ASURA, which was developed by MHI, can simulate the major components and systems of this plant. It was used for this examination. In order to adequate of the control and operation method, some cases of plant dynamics analysis by ASURA was conducted in this study.
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Fourth International Topical Meeting on High Temperature Reactor Technology
September 28–October 1, 2008
Washington, DC, USA
Conference Sponsors:
- ASME
ISBN:
978-0-7918-4854-8
PROCEEDINGS PAPER
Development of Plant Dynamics Analysis Code for HTGR-Steam Cycle Available to Purchase
Yorikata Mizokami,
Yorikata Mizokami
Mitsubishi Heavy Industries, Ltd., Kobe, Japan
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Tetsuo Saguchi,
Tetsuo Saguchi
Mitsubishi Heavy Industries, Ltd., Kobe, Japan
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Isao Minatsuki,
Isao Minatsuki
Mitsubishi Heavy Industries, Ltd., Toyko, Japan
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Dominique Petit
Dominique Petit
AREVA NP, Lyon, France
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Yorikata Mizokami
Mitsubishi Heavy Industries, Ltd., Kobe, Japan
Tetsuo Saguchi
Mitsubishi Heavy Industries, Ltd., Kobe, Japan
Isao Minatsuki
Mitsubishi Heavy Industries, Ltd., Toyko, Japan
Dominique Petit
AREVA NP, Lyon, France
Paper No:
HTR2008-58100, pp. 641-647; 7 pages
Published Online:
July 1, 2009
Citation
Mizokami, Y, Saguchi, T, Minatsuki, I, & Petit, D. "Development of Plant Dynamics Analysis Code for HTGR-Steam Cycle." Proceedings of the Fourth International Topical Meeting on High Temperature Reactor Technology. Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 1. Washington, DC, USA. September 28–October 1, 2008. pp. 641-647. ASME. https://doi.org/10.1115/HTR2008-58100
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