Optimal Control of Stretch-out Operation for CPR1000 Nuclear Power Unit

Yang Zhang; Song Yinlei; Tian Wei

doi:10.13832/j.jnpe.2022.03.0144

Volume 43 Issue 3

Jun. 2022

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Yang Zhang, Song Yinlei, Tian Wei. Optimal Control of Stretch-out Operation for CPR1000 Nuclear Power Unit[J]. Nuclear Power Engineering, 2022, 43(3): 144-150. doi: 10.13832/j.jnpe.2022.03.0144

Citation:

Yang Zhang, Song Yinlei, Tian Wei. Optimal Control of Stretch-out Operation for CPR1000 Nuclear Power Unit[J]. Nuclear Power Engineering, 2022, 43(3): 144-150. doi: 10.13832/j.jnpe.2022.03.0144

Yang Zhang, Song Yinlei, Tian Wei. Optimal Control of Stretch-out Operation for CPR1000 Nuclear Power Unit[J]. Nuclear Power Engineering, 2022, 43(3): 144-150. doi: 10.13832/j.jnpe.2022.03.0144

Citation:

Yang Zhang, Song Yinlei, Tian Wei. Optimal Control of Stretch-out Operation for CPR1000 Nuclear Power Unit[J]. Nuclear Power Engineering, 2022, 43(3): 144-150. doi: 10.13832/j.jnpe.2022.03.0144

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Optimal Control of Stretch-out Operation for CPR1000 Nuclear Power Unit

doi: 10.13832/j.jnpe.2022.03.0144

Ningde Nuclear Power Company, Ningde, Fujian, 355200, China

Received Date: 2021-03-24
Rev Recd Date: 2021-10-10
Publish Date: 2022-06-07

Abstract

Abstract

Stretch-out operation (SO) is an important means of flexible operation for PWR nuclear power unit. It is of great significance to study how to improve the safety and economy of the unit under SO mode. For the case of fluctuation of important parameters such as primary loop average temperature, core thermal power, core axial power deviation and temperature regulating rod (R rod) position of a Chinese improved three loop pressurized water reactor (CPR1000) nuclear power unit under SO mode, relevant research shows that the main reason is that the high-pressure regulating valve of the steam turbine of the CPR1000 nuclear power unit operates in the steep region of the flow characteristic curve, which causes the valve opening to fluctuate under the influence of external disturbances, and induces fluctuations of important parameters such as main steam flow, average temperature of primary loop, etc. Combined with the operation characteristics of the nuclear power unit, strategies such as optimizing the flow characteristic curve of the high-pressure regulating valve and optimizing the main steam flow limit are proposed to improve the safety and economy of the unit during SO. The effectiveness of the strategy is verified by several engineering cases of stretch-out operation of several CPR1000 nuclear power units.
- CPR1000,
- Stretch-out Operation (SO),
- Control optimization,
- Economy

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References(14)

References

[1]	谢运利,李满仓,娄磊,等. 华龙一号堆芯延伸运行能力分析[J]. 科技创新导报,2020, 17(2): 28-31,33.
[2]	尹浪,吴迪,申中祥,等. M310型压水堆核电厂延伸运行专项研究[J]. 科技创新导报,2020, 17(8): 47-48,50.
[3]	廖业宏,肖岷,李现锋,等. 大亚湾核电站延伸运行及降功率期间反应堆轴向功率偏差的控制及其计算机模拟分析[J]. 核动力工程,2004, 25(4): 297-300. doi: 10.3969/j.issn.0258-0926.2004.04.003
[4]	肖岷,朱闽宏,李现锋,等. 大亚湾核电站延伸运行技术的研究与实施[J]. 核动力工程,2006, 27(1): 1-4,50. doi: 10.3969/j.issn.0258-0926.2006.01.001
[5]	朱闽宏,傅先刚,王斐,等. 大亚湾核电站延伸运行与长期低功率运行[J]. 核动力工程,2002, 23(5): 22-25,36. doi: 10.3969/j.issn.0258-0926.2002.05.006
[6]	周红,毛海耘,柴国旱,等. 对广东大亚湾核电厂延伸运行的监督实践[J]. 核安全,2004, 6(2): 26-29.
[7]	厉井钢,张洪,梁薇,等. 岭澳核电站延伸运行工况下的功率能力分析[J]. 核动力工程,2005, 26(S6): 62-64.
[8]	国际在线. 我国首座自主品牌CPR1000核反应堆启动[J]. 电网与清洁能源,2010, 26(6): 91 .
[9]	柴伟东,赵清森. CPR1000机组蒸汽发生器裕度问题分析[J]. 热力发电,2019, 48(3): 126-131.
[10]	舒相挺,蒋彦龙,杨璋. 某型核电汽轮机高压主汽调节阀组稳定性研究[J]. 汽轮机技术,2020, 62(3): 209-212,216. doi: 10.3969/j.issn.1001-5884.2020.03.014
[11]	杨璋,蒋彦龙. 某型核电汽轮发电机组一次调频功能试验[J]. 热力发电,2020, 49(1): 109-81.
[12]	徐辛酉,宋凯,陈璞洁,等. 某核电汽轮机主调门流量特性曲线对DEH控制系统的影响分析[J]. 机械工程师,2015(6): 176-177. doi: 10.3969/j.issn.1002-2333.2015.06.075
[13]	董威,黄美华,曾彬. 核电厂汽机主调节阀阀位波动问题研究[J]. 自动化仪表,2015, 36(11): 50-52,56.
[14]	王青青,李国栋,关建军. 汽轮机高压调阀动力油软管漏油原因分析[J]. 设备管理与维修,2016, 397(S1): 79-81.