Study on Control Strategy of Natural Circulation Lead-cooled Fast Reactor Coupled with S-CO<sub>2</sub> Brayton Cycle

Liu Guixiu; Yi Jingwei; Li Gen; Liang Tiebo; Fang Huawei; Chen Weixiong

doi:10.13832/j.jnpe.2023.04.0138

Volume 44 Issue 4

Aug. 2023

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2023 > 44(4): 138-147

Liu Guixiu, Yi Jingwei, Li Gen, Liang Tiebo, Fang Huawei, Chen Weixiong. Study on Control Strategy of Natural Circulation Lead-cooled Fast Reactor Coupled with S-CO2 Brayton Cycle[J]. Nuclear Power Engineering, 2023, 44(4): 138-147. doi: 10.13832/j.jnpe.2023.04.0138

Citation:

Liu Guixiu, Yi Jingwei, Li Gen, Liang Tiebo, Fang Huawei, Chen Weixiong. Study on Control Strategy of Natural Circulation Lead-cooled Fast Reactor Coupled with S-CO₂ Brayton Cycle[J]. Nuclear Power Engineering, 2023, 44(4): 138-147. doi: 10.13832/j.jnpe.2023.04.0138

Citation:

PDF( 6287 KB)

Study on Control Strategy of Natural Circulation Lead-cooled Fast Reactor Coupled with S-CO₂ Brayton Cycle

doi: 10.13832/j.jnpe.2023.04.0138

1.
State Key Laboratory of Multiphase Flow in Power Engineering, Xi’an Jiaotong University, Xi’an, 710049, China
2.
Nuclear Power Institude of China, Chengdu, 610213, China
3.
School of Electric Power, South China University of Technology, Guangzhou, 510641, China

Received Date: 2022-09-29
Rev Recd Date: 2023-03-28
Publish Date: 2023-08-15

Abstract

Abstract

The coupled power generation system of natural circulation lead cooled fast reactor with supercritical carbon dioxide (S-CO₂) Brayton cycle is the development trend of advanced nuclear energy systems in the future. Based on the software Apros, a dynamic model of the coupled power generation system was built, and two reactor control schemes were designed, one of which was the conventional control scheme of the reference core power control system of pressurized water reactor, and the other was the compensation control scheme with rod position limit of control rods. The research results showed that under a small variable load rate of 3% FP/min (FP is short for full power), the dynamic deviation of load following under both control schemes was between −2% and 1%, however, for the stability of core outlet coolant temperature, the compensation control scheme was superior to the conventional control scheme; at a large variable load rate of 6%FP/min-18%FP/min, the variation range of core outlet temperature under conventional control was −40℃-0℃, while the variation range of the core outlet temperature under compensation control was −5℃-2℃. Therefore, the compensation control scheme can be used as an effective means for the control of natural circulation lead cooled fast reactor.
- Lead cooled fast reactor,
- Natural circulation,
- S-CO₂ Brayton cycle,
- Reactor control

FullText(HTML)

References(11)

References

[1]	MOISSEYTSEV A, SIENICKI J J. Transient accident analysis of a supercritical carbon dioxide Brayton cycle energy converter coupled to an autonomous lead-cooled fast reactor[J]. Nuclear Engineering and Design, 2008, 238(8): 2094-2105. doi: 10.1016/j.nucengdes.2007.11.012
[2]	赵鹏程. 小型自然循环铅冷快堆SNCLFR-100一回路主冷却系统热工安全分析[D]. 合肥: 中国科学技术大学, 2017.
[3]	WU P, MA Y D, GAO C T, et al. A review of research and development of supercritical carbon dioxide Brayton cycle technology in nuclear engineering applications[J]. Nuclear Engineering and Design, 2020, 368: 110767. doi: 10.1016/j.nucengdes.2020.110767
[4]	PONCIROLI R, CAMMI A, DELLA BONA A, et al. Development of the ALFRED reactor full power mode control system[J]. Progress in Nuclear Energy, 2015, 85: 428-440. doi: 10.1016/j.pnucene.2015.06.024
[5]	MOISSEYTSEV A, SIENICKI J J. Development of a plant dynamics computer code for analysis of a supercritical carbon dioxide Brayton cycle energy converter coupled to a natural circulation lead-cooled fast reactor: ANL-06/27 TRN: US0704255[R]. U.S.: Argonne National Lab, 2007.
[6]	YANG M H, SONG Y, WANG J Y, et al. Temperature control characteristics analysis of lead-cooled fast reactor with natural circulation[J]. Annals of Nuclear Energy, 2016, 90: 54-61. doi: 10.1016/j.anucene.2015.11.029
[7]	WAN J S, XIE J Y, WANG P F, et al. Control system design for the once-through steam generator of lead–bismuth cooled reactor based on classical control theory[J]. Annals of Nuclear Energy, 2022, 175: 109214. doi: 10.1016/j.anucene.2022.109214
[8]	张建民. 核反应堆控制[M]. 西安: 西安交通大学出版社, 2002: 172.
[9]	MA, Y G, MOROSUK T, LUO J, et al. Superstructure design and optimization on supercritical carbon dioxide cycle for application in concentrated solar power plant[J]. Energy Conversion and Management, 2020, 206: 112290.
[10]	AL-MALIKI W A K, ALOBAID F, KEZ V, et al. Modelling and dynamic simulation of a parabolic trough power plant[J]. Journal of Process Control, 2016, 39: 123-138. doi: 10.1016/j.jprocont.2016.01.002
[11]	DYREBY J J. Modeling the supercritical carbon dioxide Brayton cycle with recompression[D]. Madison: University of Wisconsin-Madison, 2014.