Acknowledgement
The work is supported in part by the National Natural Science Foundation of China Youth fund (12005096), and the Provincial Innovation and Entrepreneurship Training Program for Undergraduates (S202210555135), and the science and technology innovation Program of Hunan Province (2020RC4053).
References
- Pengfei Wang, Zhi Chen, Longtao Liao, Jiashuang Wan, Shifa Wu, A multiple-model based internal model control method for power control of small pressurized water reactors, Energy 210 (2020), 118527.
- Minjun Peng, Ze Du, Study on static characteristics of dual constant operation scheme of marine PWR nuclear power plant, Nucl. Sci. Eng. 21 (2001) 304-310 (in Chinese).
- Wei Zhang, Zonghua Ding, Guoqing Xia, Xinqian Bian, Applied study of coordinate control of nuclear-power system, Nucl. Sci. Eng. 26 (2006) 337-342 (in Chinese).
- Pengfei Wang, Qingfeng Jiang, Jiashuang Wan, Shifa Wu, Robust controller design for small pressurized water reactors using non-smooth optimization, Ann. Nucl. Energy 165 (2022), 108775.
- Jiashuang Wan, Pengfei Wang, Shifa Wu, Fuyu Zhao, Conventional controller design for the reactor power control system of the advanced small pressurized water reactor, Nucl. Technol. 198 (2017) 26-42. https://doi.org/10.1080/00295450.2017.1292822
- Ping Hu, Fuyu Zhao, Tai Yun, Coordination control and simulation for small nuclear power plant, Prog. Nucl. Energy 58 (2012) 21-26. https://doi.org/10.1016/j.pnucene.2012.02.001
- Debayan Bose, Abhik Hazra, Siddhartha Mukhopadhyay, Amitava Gupta, A coordinated control methodology for rapid load-following operation of a pressurized water reactor based small modular reactor, Nucl. Eng. Des. 367 (2020), 110748.
- Dalin Zhang, Rongshuan Xu, Youchun Chen, Bo Wang, Chenglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su, Preliminary study of parameter uncertainty influence on thermal design and analysis for sodium heated once-through steam generator, Nucl. Eng. Des. 369 (2020), 110858.
- Jianmin Zhu, Yousen Hu, Wei Zhang, Hong xiao, Study on uncertainty analysis of steam generator water level, Nucl. Sci. Eng. 40 (3) (2020) 353-358 (in Chinese).
- Tiejun Zu, Chenghui Wan, Liangzhi Cao, Hongchun Wu, Wei Shen, Total uncertainty analysis for PWR assembly based on the statistical sampling method, Nucl. Sci. Eng. 183 (2016) 371-386. Seh. https://doi.org/10.13182/NSE15-96
- Hao Chen, Ji Ma, Ning Xu, Qiang Zhao, Jiayu Du, Kaijie Zhu, Uncertainty propagation analysis for control rod worth of PWR based on the statistical sampling method, Ann. Nucl. Energy 137 (2020), 107054.
- XuYan, Pengfei Wang, Junyan Qing, Shifa Wu, Fuyu Zhao, Robust power control design for a small pressurized water reactor using an H infinity mixed sensitivity method, Nucl. Eng. Technol. 52 (2020) 1443-1451. https://doi.org/10.1016/j.net.2019.12.031
- Pengfei Wang, Qingfeng Jiang, Jiaxuan Zhang, Jiashuang Wan, Shifa Wu, A fuzzy fault accommodation method for nuclear power plants under actuator stuck faults, Ann. Nucl. Energy 165 (2022), 108674.
- Quan Ma, Xinyu Wei, Junyan Qing, Jiao Wen, Risheng Xu, Load following of SMR based on a flexible load, Energy 183 (2019) 733-746. https://doi.org/10.1016/j.energy.2019.06.172
- Pengfei Wang, Jiashuang Wan, Shifa Wu, Fuyu Zhao, A fuzzy-logic-based pressure setpoint modification method for pressurized water reactor pressurizers, Ann. Nucl. Energy 135 (2020), 106954.
- Pengfei Wang, Zhi Chen, Rui Zhang, Jian Sun, Zhengxi He, Fuyu Zhao, Xinyu Wei, Control simulation and study of load rejection transient for AP1000, Prog. Nucl. Energy 85 (2015) 28-43. https://doi.org/10.1016/j.pnucene.2015.05.008
- L.L. Briggs, Uncertainty quantification approaches for advanced reactor analyses, Argonne Natl. Lab. (2008). ANL-GenIV-110.
- S.S. Wilks, Determination of sample sizes for setting tolerance limits, Ann. Math. Stat. 12 (1) (1941) 91-96. https://doi.org/10.1214/aoms/1177731788
- M. Williams, D. Wiarda, H. Smith, M.A. Jessee, B.T. Rearden, W. Zwermann, M. Klein, A. Pautz, B. Krzykacz-Hausmann, L. Gallner, Development of a Statistical Sampling Method for Uncertainty Analysis with SCALE, PHYSOR, USA, 2012 Tennessee.
- Li Xiaoyu, Li Chuhao, Hu Yang, Yu Yongqi, Zeng Wenjie, Wu Haibiao, Uncertainty quantification of the power control system of a small PWR with coolant temperature perturbation, Nucl. Eng. Technol. 54 (2022) 2048-2054. https://doi.org/10.1016/j.net.2022.01.005
- Yang Zhao, Zhangpeng Guo, Fenglei Niu, Yu Yu, Shengfei Wang, Global sensitivity analysis of passive safety systems of FHR by using meta-modeling and sampling methods, Prog. Nucl. Energy 115 (2019) 30-41. https://doi.org/10.1016/j.pnucene.2019.03.002
- Yinuo Liu, Qingfeng Jiang, Chao Yang, Wenjie Zeng, Manbo Cai, Uncertainty analysis of reactivity feedback coefficient for LFR core power control system during reactivity insertion accident, Ann. Nucl. Energy 160 (2021), 108401.
- Ebiwonjumi Bamidele, Mai Nhan Nguyen Trong, Lee Hyun Chul, Lee Deokjung, Propagation of radiation source uncertainties in spent fuel cask shielding calculations, Nucl. Eng. Technol. 54 (2022) 2048-2054. https://doi.org/10.1016/j.net.2022.01.005
- Wan Chenghui, Cao Liangzhi, Wu Hongchun, Shen Wei, Nuclear-data uncertainty propagations in burnup calculation for the PWR assembly, Ann. Nucl. Energy 100 (2017) 20-31. https://doi.org/10.1016/j.anucene.2016.09.037
- Dinesh Kumar, Syed Bahauddin Alam, Tuhfatur Ridwan, S. Cameron, Goodwin, Quantitative risk assessment of a high power density small modular reactor (SMR) core using uncertainty and sensitivity analyses, Energy 227 (2021), 120400.
- Gangping Shang, Uncertainty Analysis of Input Parameters for Thermal Hydraulic Calculation of CEFR Steam Generator, Harbin Engineering University, Harbin (China), 2017 (in Chinese).
- Feng Han, CFD Uncertainty Analysis of Once-Through Steam Generator, Shandong University, Shandong (China), 2021 (in Chinese).