Small Pressurized Water Reactors (SPWR) are different from those of the commercial large Pressurized Water Reactors (PWRs). There are no hot legs and cold legs between the reactor core and the steam generators like in the PWR. The coolant inventory is in a large amount. The inertia of the coolant is large and it takes a long time for the primary system to respond to disturbances. Once-through steam generator is adopted and its water inventory is small. It is very sensitive to disturbances. These unique characteristics challenge the control system design of an SPWR. Relap5 is used to model an SPWR. In the reactor power control system, both the reactor power and the coolant average temperature are regulated by the control rod reactivity. In the feedwater flow control system, the coordination between the reactor and the turbine is considered and coolant average temperature is adopted as one measurable disturbance to balance them. The coolant pressure is adjusted based on the heaters and spray in the pressurizer. The water level in the pressurizer is controlled by the charging flow. Transient simulations are carried out to evaluate the control system performance. When the reactor is perturbed, the reactor can be stabilized under the control system.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5143-2
PROCEEDINGS PAPER
Coordinated Control of a Small Pressurized Water Reactor
Peiwei Sun,
Peiwei Sun
Xi'an Jiaotong University, Xi'an, China
Search for other works by this author on:
Chong Wang
Chong Wang
China Institute of Atomic Energy, Beijing, China
Search for other works by this author on:
Peiwei Sun
Xi'an Jiaotong University, Xi'an, China
Chong Wang
China Institute of Atomic Energy, Beijing, China
Paper No:
ICONE26-81156, V001T04A003; 6 pages
Published Online:
October 24, 2018
Citation
Sun, P, & Wang, C. "Coordinated Control of a Small Pressurized Water Reactor." Proceedings of the 2018 26th International Conference on Nuclear Engineering. London, England. July 22–26, 2018. V001T04A003. ASME. https://doi.org/10.1115/ICONE26-81156
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