Research on Dynamic Modeling and Control Method of Heat Pipe Reactor

Yin Shaoxuan; Yu Ren; Sheng Dongjie; Mao Wei

doi:10.13832/j.jnpe.2024.04.0166

Volume 45 Issue 4

Aug. 2024

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Yin Shaoxuan, Yu Ren, Sheng Dongjie, Mao Wei. Research on Dynamic Modeling and Control Method of Heat Pipe Reactor[J]. Nuclear Power Engineering, 2024, 45(4): 166-172. doi: 10.13832/j.jnpe.2024.04.0166

Citation:

Yin Shaoxuan, Yu Ren, Sheng Dongjie, Mao Wei. Research on Dynamic Modeling and Control Method of Heat Pipe Reactor[J]. Nuclear Power Engineering, 2024, 45(4): 166-172. doi: 10.13832/j.jnpe.2024.04.0166

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Research on Dynamic Modeling and Control Method of Heat Pipe Reactor

doi: 10.13832/j.jnpe.2024.04.0166

College of Nuclear Science and Technology, Naval University of Engineering, Wuhan, 430033, China

Received Date: 2023-08-29
Rev Recd Date: 2023-10-10
Publish Date: 2024-08-12

Abstract

Abstract

In order to study the nuclear power control method of heat pipe reactor (HPR), the lightweight dynamic model of MegaPower HPR is constructed, and then the designed controller is verified by simulation. Based on lumped parameter method, a heat transfer model from core to heat pipe and then to heat exchanger is studied, and Simulink model is established. Aiming at the control method design of HPR, the control objectives of load tracking and keeping the heat exchanger outlet temperature constant are determined. Then, two controllers, the parallel proportional-integral-derivative (PID) and the cascade PID, are designed, and their control effects are compared and analyzed. The results show that the steady-state error of the model is less than 0.05%, and the parameter response trend of the model without control is consistent with the theoretical analysis, and the simulation speed is faster. In terms of control, the two controllers can achieve the control objectives, and the adjustment time of nuclear power and heat exchanger outlet temperature is less than 150 s with small fluctuation amplitude. Therefore, the dynamic model of HPR established in this paper can be used to verify the control method, and the two controllers based on PID design have great control effect, and the cascade PID controller has better control performance.
- Heat pipe reactor,
- Dynamic model,
- Load tracking,
- Temperature control,
- PID control

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References(12)

References

[1]	SUBKI M H. Advances in technology developments of small modular reactors–including microreactors[C]//21st INPRO Dialogue Forum on the Deployment of SMR Projects and Technologies to Support the Sustainable Development Goals. Sankt Petersburg, Russian: International Atomic Energy Agency, 2023.
[2]	余红星,马誉高,张卓华,等. 热管冷却反应堆的兴起和发展[J]. 核动力工程,2019, 40(4): 1-8. doi: 10.13832/j.jnpe.2019.04.0001.
[3]	钟睿诚,马誉高,邓坚,等. 热管堆多反馈效应下的启堆特性研究[J]. 核动力工程,2021, 42(S2): 104-108. doi: 10.13832/j.jnpe.2021.S2.0104.
[4]	邹正平,王一帆,姚李超,等. 超临界二氧化碳闭式布莱顿循环系统研究进展[J]. 北京航空航天大学学报,2022, 48(9): 1643-1677. doi: 10.13700/j.bh.1001-5965.2022.0196.
[5]	MARCHIONNI M, BIANCHI G, TASSOU S A. Transient analysis and control of a heat to power conversion unit based on a simple regenerative supercritical CO₂ Joule-Brayton cycle[J]. Applied Thermal Engineering, 2021, 183: 116214. doi: 10.1016/j.applthermaleng.2020.116214
[6]	柴晓明,马誉高,韩文斌,等. 热管堆固态堆芯三维核热力耦合方法与分析[J]. 原子能科学技术,2021, 55(S2): 189-195.
[7]	GUO Y C, LI Z G, WANG K, et al. A transient multiphysics coupling method based on OpenFOAM for heat pipe cooled reactors[J]. Science China Technological Sciences, 2022, 65(1): 102-114.
[8]	MCCLURE P R, POSTON D I, DASARI V R, et al. Design of megawatt power level heat pipe reactors: LA-UR-15-28840[R]. Los Alamos: Los Alamos National Laboratory, 2015.
[9]	马誉高,杨小燕,刘余,等. MW级热管冷却反应堆反馈特性及启堆过程研究[J]. 原子能科学技术,2021, 55(S2): 213-220.
[10]	GE L, LI H Q, TIAN X Y, et al. Improvement and validation of the system analysis model and code for heat-pipe-cooled microreactor[J]. Energies, 2022, 15(7): 2586. doi: 10.3390/en15072586
[11]	ZUO Z J, FAGHRI A. A network thermodynamic analysis of the heat pipe[J]. International Journal of Heat and Mass Transfer, 1998, 41(11): 1473-1484. doi: 10.1016/S0017-9310(97)00220-2
[12]	MA Y G, CHEN E H, YU H X, et al. Heat pipe failure accident analysis in megawatt heat pipe cooled reactor[J]. Annals of Nuclear Energy, 2020, 149: 107755. doi: 10.1016/j.anucene.2020.107755