Analysis of Load-following Operation Capability of Large Sodium-cooled Fast Reactor

Dai Raoqi; Duan Tianying; Liu Yong; Zhang Houming; Zhang Weiying; Xu Weidong

doi:10.13832/j.jnpe.2023.06.0199

Volume 44 Issue 6

Dec. 2023

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Article Navigation > Nuclear Power Engineering > 2023 > 44(6): 199-205

Dai Raoqi, Duan Tianying, Liu Yong, Zhang Houming, Zhang Weiying, Xu Weidong. Analysis of Load-following Operation Capability of Large Sodium-cooled Fast Reactor[J]. Nuclear Power Engineering, 2023, 44(6): 199-205. doi: 10.13832/j.jnpe.2023.06.0199

Citation:

Dai Raoqi, Duan Tianying, Liu Yong, Zhang Houming, Zhang Weiying, Xu Weidong. Analysis of Load-following Operation Capability of Large Sodium-cooled Fast Reactor[J]. Nuclear Power Engineering, 2023, 44(6): 199-205. doi: 10.13832/j.jnpe.2023.06.0199

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Analysis of Load-following Operation Capability of Large Sodium-cooled Fast Reactor

doi: 10.13832/j.jnpe.2023.06.0199

1.
China Institute of Atomic Energy, Beijing, 102413, China
2.
North Regional Office of Nuclear and Radiation Safety Inspection, National Nuclear Safety Administration, Beijing, 100191, China

Received Date: 2022-12-28
Rev Recd Date: 2023-05-21
Publish Date: 2023-12-15

Abstract

Abstract

In order to study the load-following capability of a large sodium-cooled fast reactor in China, a simulation model of the whole system of this sodium-cooled fast reactor is established based on MATLAB/Simulink platform, and the load-following capability of the primary, second and third loops of the fast reactor system is tested in different levels under the extreme condition of load step and no control system intervention. The simulation results show that the primary and second loops of the fast reactor system can withstand ±10% of the load step, while the load-following capability of the third loop cannot meet this requirement. Under the current process design and key parameter limit conditions, this large sodium-cooled fast reactor has a poor load-following operation capability, and it cannot withstand a 10% load step. When operating at 90%P_n power level, it can withstand a 2.9% load step increase at most, and its once-through steam generator(OTSG) is the main limiting factor.
- Sodium-cooled fast reactor,
- Load-following,
- Once-through steam generator(OTSG),
- Simulation,
- Simulink

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References

[1]	张小冬,刘琳. AP1000反应堆控制系统特点分析[J]. 核动力工程,2011,32(4):62-65.
[2]	张玮瑛,段天英,刘勇,等. 中国实验快堆负荷跟踪能力分析[J]. 原子能科学技术,2017,51(11):2028-2035. doi: 10.7538/yzk.2017.51.11.2028
[3]	王平,傅龙舟,朱继洲. 钠冷快堆主回路系统的建模及动态仿真[J]. 核科学与工程,1992,12(2):116-126.
[4]	BRUENS N W S, BRUKX J F L M, LATZKO D G H, et al. Modeling of nuclear steam generator dynamics[C]. USA: Proceedings of the 2nd Power Plant Dynamics, Control and Testing Symposium. Knoxville, Tennessee, 1975.
[5]	WALSH J M, KESAVAN K. Hybrid computer model of the prototype large breeder reactor plant and control system[C]. USA: Proceedings of the 3rd Power Plant Dynamics, Control, and Testing Symposium. Knoxville, 1977.
[6]	杨世铭,陶文铨. 传热学[M]. 第三版. 北京:高等教育出版社,1998:159-164.
[7]	徐济鋆. 沸腾传热和气液两相流[M]. 北京:中国原子能出版社,2001:100-105,278-320.
[8]	于平安. 核反应堆热工分析[M]. 北京:中国原子能出版社,1981:83-92.
[9]	IEEE Committee Report. Dynamic models for steam and hydro turbines in power system studies[J]. IEEE Transactions on Power Apparatus and Systems, 1973, PAS-92(6): 1904-1915. doi: 10.1109/TPAS.1973.293570

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