Simulation of Thermodynamic Characteristics of Supercritical Carbon Dioxide Brayton Cycle System Based on Modelica

Zhang Liqin; Huang Yanping; Zeng Xiaokang; Gong Houjun

doi:10.13832/j.jnpe.2024.03.0124

Volume 45 Issue 3

Jun. 2024

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2024 > 45(3): 124-131

Zhang Liqin, Huang Yanping, Zeng Xiaokang, Gong Houjun. Simulation of Thermodynamic Characteristics of Supercritical Carbon Dioxide Brayton Cycle System Based on Modelica[J]. Nuclear Power Engineering, 2024, 45(3): 124-131. doi: 10.13832/j.jnpe.2024.03.0124

Citation:

Zhang Liqin, Huang Yanping, Zeng Xiaokang, Gong Houjun. Simulation of Thermodynamic Characteristics of Supercritical Carbon Dioxide Brayton Cycle System Based on Modelica[J]. Nuclear Power Engineering, 2024, 45(3): 124-131. doi: 10.13832/j.jnpe.2024.03.0124

Citation:

Zhang Liqin, Huang Yanping, Zeng Xiaokang, Gong Houjun. Simulation of Thermodynamic Characteristics of Supercritical Carbon Dioxide Brayton Cycle System Based on Modelica[J]. Nuclear Power Engineering, 2024, 45(3): 124-131. doi: 10.13832/j.jnpe.2024.03.0124

PDF( 6286 KB)

Simulation of Thermodynamic Characteristics of Supercritical Carbon Dioxide Brayton Cycle System Based on Modelica

doi: 10.13832/j.jnpe.2024.03.0124

CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2023-08-20
Rev Recd Date: 2023-11-16
Publish Date: 2024-06-13

Abstract

Abstract

Modelica is an open-source object-oriented language for modeling large and complex systems, and developed by the Swedish non-profit organization Modelica Association. In this paper, Modelica language is used to simulate the thermodynamic characteristics of supercritical carbon dioxide Brayton cycle system. Based on the mechanism relationship of key equipment such as compressor, turbine, regenerator and cooler, a supercritical carbon dioxide model library based on Modelica language was developed. A simulation model of single-stage regenerative cycle system was built based on drag and drop modeling and visual interface. The steady-state solution was carried out based on the solver of Modelica platform Mworks. Compared with the calculation results of SCTRAN/CO2, the reliability of Modelica model and the feasibility of Modelica in the simulation of thermodynamic characteristics of supercritical carbon dioxide Brayton cycle system were verified, and the transient characteristics of single-stage regenerative cycle were analyzed.
- Modelica,
- Supercritical carbon dioxide,
- System simulation,
- Brayton cycle

FullText(HTML)

References(9)

References

[1]	FERRERO S, BATET L, LINARES J I, et al. A modelica dynamic model of a supercritical CO₂ energy conversion system for EU-DEMO[J]. Fusion Engineering and Design, 2021, 173: 112826. doi: 10.1016/j.fusengdes.2021.112826
[2]	DELGOSHAEI P, HEIDARINEJAD M, AUSTIN M A. Semantic inference-based control strategies for building HVAC systems using modelica-based physical models[J]. Procedia Engineering, 2017, 205: 1975-1982. doi: 10.1016/j.proeng.2017.10.060
[3]	刘伟,丁建完,赵建军,等. 基于Modelica的载人航天器环热控系统建模仿真[J]. 航天器环境工程,2017, 34(2): 143-149.
[4]	李冰洁,张晓斌,吴小华,等. 基于Dymola及Modelica语言的飞机三级发电机的建模与仿真[J]. 微电机,2016, 49(3): 40-44.
[5]	杨世铭,陶文铨. 传热学[M]. 第四版. 北京: 高等教育出版社,1982: 246.
[6]	陈卓如,金朝铭. 工程流体力学[M]. 第二版. 北京: 高等教育出版社,1992: 265.
[7]	GAO C T, WU P, SHAN J Q, et al. Preliminary study of system design and safety analysis methodology for supercritical carbon dioxide Brayton cycle direct-cooled reactor system[J]. Annals of Nuclear Energy, 2020, 147: 107734. doi: 10.1016/j.anucene.2020.107734
[8]	CARSTENS N A, HEJZLAR P, DRISCOLL M J. Control system strategies and dynamic response for supercritical CO₂ power conversion cycles: MIT-GFR-038[R]. Cambrige: MIT Nuclear Engineering Department, 2006.
[9]	CARSTENS N A. Control strategies for supercritical carbon dioxide power conversion systems[D]. Cambridge: Massachusetts Institute of Technology, 2007.

Relative Articles

[1]	Hao Chengming, Liu Lizhi, Han Yifu, Xia Junbao, Yu Qiao, Liu Chengmin, Wang Jie. Global Optimization Analysis of Nuclear Power Plant Parameters Based on Modelica[J]. Nuclear Power Engineering, 2024, 45(S2): 28-34. doi: 10.13832/j.jnpe.2024.S2.0028
[2]	Liu Jiusong, Liu Chengmin, Yi Jingwei, Li Yi, Li Siguang. Research on Operation Characteristics of Heat Pipe Reactor Coupled with Open-Air Brayton Cycle[J]. Nuclear Power Engineering, 2024, 45(1): 237-245. doi: 10.13832/j.jnpe.2024.01.0237
[3]	Qi Lin, Li Yangliu, Wang Xuesong, Yin Hao, Wang Shuguang. Modeling and Simulation of Heat Pipe Radiator Based on Modelica[J]. Nuclear Power Engineering, 2024, 45(S1): 45-51. doi: 10.13832/j.jnpe.2024.S1.0045
[4]	Zong Yi, Zhuang Kun, Lu Di, Qi Shengdong. Study on Reactivity Disturbance Characteristics of SCO₂ Reactor Assembly Caused by Burnable Poisons[J]. Nuclear Power Engineering, 2023, 44(S2): 153-159. doi: 10.13832/j.jnpe.2023.S2.0153
[5]	Huang Junlin, Li Chao, Zhu Xiaoliang, Tu Yiyou, Xu Qinglan. Novel Measurement Method for Shear Failure Strength of Oxide Scales on Inner Surface of Supercritical Carbon Dioxide PCHE[J]. Nuclear Power Engineering, 2023, 44(S2): 115-119. doi: 10.13832/j.jnpe.2023.S2.0115
[6]	Feng Mengjiao, Liu Minyun, Huang Shanfang, Huang YanPing. Design and Performance Investigation of Supercritical Carbon Dioxide Ejector[J]. Nuclear Power Engineering, 2023, 44(S1): 81-87. doi: 10.13832/j.jnpe.2023.S1.0081
[7]	Zhang Dongxu, Li Weiqing, Zhao Minfu, Liang Peng, Xu Yongwang, Li Qingyuan, Duan Minghui. Experimental Study on Critical Flow of Supercritical Carbon Dioxide at Transient State[J]. Nuclear Power Engineering, 2023, 44(5): 232-236. doi: 10.13832/j.jnpe.2023.05.0232
[8]	Liang Yangyang, Zhang Huimin, Wang Li, Li Yunlong, Yuan Yidan, Wang Jun, Du Shuhong. The Application of Modelica Simulation Technology in Micro Gas-Cooled Reactor[J]. Nuclear Power Engineering, 2022, 43(2): 152-159. doi: 10.13832/j.jnpe.2022.02.0152
[9]	Liu Xiuting, Huang Yanping, Wang Yangle, Liu Guangxu, Zhuo Wenbin, Li Xinyu. Analysis and Research of Coupled Brayton Cycle System for Small Fluorine Salt Cooled High Temperature Reactor[J]. Nuclear Power Engineering, 2022, 43(5): 20-26. doi: 10.13832/j.jnpe.2022.05.0020
[10]	Wang Junfeng, Wang Yangle, Zhou Yuan, Huang Yanping. Investigations on Supercritical CO2 Critical Flow through Mini Tubes[J]. Nuclear Power Engineering, 2021, 42(2): 35-38. doi: 10.13832/j.jnpe.2021.02.0035
[11]	Huang Yanping, Zeng Xiaokang, Ding Ji. Simulation Model Architecture and Concept Validation for Thermal Hydraulic Characteristics of Two-Phase Fluid Based on Modelica[J]. Nuclear Power Engineering, 2021, 42(1): 1-7. doi: 10.13832/j.jnpe.2021.01.0001
[12]	Liu Shenghui, Huang Yanping, Liu Guangxu, Wang Junfeng, Wang Jinyu. Influence of Gas State Equations on Acceleration Parameter for Heat Transfer to Supercritical Carbon Dioxide Flowing in Heated Tubes[J]. Nuclear Power Engineering, 2019, 40(1): 18-22. doi: 10.13832/j.jnpe.2019.01.0018
[13]	Liu Shenghui, Huang Yanping, Liu Guangxu, Wang Junfeng, Zan Yuanfeng, Lang Xuemei, Huang Jun. Investigation of Correlation for Forced Convective Heat Transfer to Supercritical Carbon Dioxide Flowing in a Vertical Tube[J]. Nuclear Power Engineering, 2017, 38(1): 1-5. doi: 10.13832/j.jnpe.2017.01.0001
[14]	Ruan Jian, Zou Yang, Li Minghai, Zhou Bo, Zhu Guifeng, Xu Hongjie. Transient Study on Characteristics of Power Generation by FHR Coupling with Air Brayton Turbine Cycle[J]. Nuclear Power Engineering, 2017, 38(4): 22-26. doi: 10.13832/j.jnpe.2017.04.0022
[15]	Liu Shenghui, Huang Yanping, Liu Guangxu, Wang Junfeng, Zan Yuanfeng, Lang Xuemei. Numerical Investigation of Buoyancy Effect in Forced Convective Heat Transfer to Supercritical Carbon Dioxide Flowing in a Tube[J]. Nuclear Power Engineering, 2016, 37(6): 18-22. doi: 10.13832/j.jnpe.2016.06.0018
[16]	Liu Shenghui, Huang Yanping, Liu Guangxu, Wang Junfeng, Zhao Dawei, Zang Jinguang, Zan Yuanfeng, Lang Xuemei, Xu Jianjun. Numerical Investigation of Heat Transfer Characteristics of Supercritical Carbon Dioxide in Double D-Shape Channel[J]. Nuclear Power Engineering, 2016, 37(2): 56-59. doi: 10.13832/j.jnpe.2016.02.0056
[17]	Huang Xiaoli, Wang Junfeng, Zang Jinguang. Thermodynamic Analysis of Coupling Supercritical Carbon Dioxide Brayton Cycles[J]. Nuclear Power Engineering, 2016, 37(3): 34-38. doi: 10.13832/j.jnpe.2016.03.0034
[18]	Liu Guangxu, Huang Yanping, Wang Junfeng, Zan Yuanfeng, Lang Xuemei. Experimental Investigation of Supercritical Carbon Dioxide Natural Circulation in Rectangular Loop[J]. Nuclear Power Engineering, 2015, 36(3): 31-35. doi: 10.13832/j.jnpe.2015.03.0031
[19]	Huang Yanping, Liu Guangxu, Wang Junfeng, LÜ； Fa. Evaluation of Heat Transfer Correlations for Supercritical Carbon Dioxide in Circular Tubes under Heating Conditions[J]. Nuclear Power Engineering, 2014, 35(3): 1-5. doi: 10.13832/j.jnpe.2014.03.0001
[20]	HUANG Yanping, WANG Junfeng. Applications of Supercritical Carbon Dioxide in Nuclear Reactor System[J]. Nuclear Power Engineering, 2012, 33(3): 21-27.