上海交通大学学报 ›› 2024, Vol. 58 ›› Issue (8): 1290-1296.doi: 10.16183/j.cnki.jsjtu.2023.024
• 机械与动力工程 • 上一篇
杨泰波1,2, 刘佳鑫2, 彭志科3(), 罗能2, 刘才学2
收稿日期:
2023-01-19
修回日期:
2023-04-23
接受日期:
2023-04-24
出版日期:
2024-08-28
发布日期:
2024-08-27
通讯作者:
彭志科,教授;E-mail:作者简介:
杨泰波(1986-),副研究员,从事反应堆故障诊断与健康管理技术研究.
YANG Taibo1,2, LIU Jiaxin2, PENG Zhike3(), LUO Neng2, LIU Caixue2
Received:
2023-01-19
Revised:
2023-04-23
Accepted:
2023-04-24
Online:
2024-08-28
Published:
2024-08-27
摘要:
核反应堆中堆芯吊篮的稳定性是反应堆正常运行的保障和前提.压紧弹簧作为堆芯吊篮的约束与支撑直接影响堆芯吊篮的振动特性.在高温、辐射等恶劣工况下,压紧弹簧力学性能会发生如应力松弛的退化,影响堆芯吊篮振动以及反应堆运行安全,因此需要对堆芯吊篮压紧弹簧松弛特性展开研究.首先,建立堆芯吊篮及压紧弹簧在内的装配体有限元模型,利用湿模态法分析并获得压紧弹簧松弛情况下的堆芯吊篮梁式模态振动频率的变化.然后,开展堆芯吊篮压紧弹簧松弛试验,试验结果验证了模型的有效性.进一步利用仿真模型生成更多压紧弹簧松弛影响下的堆芯吊篮梁式模态频率数据,结合试验数据建立堆芯吊篮压紧弹簧松弛程度识别的数学模型,为反应堆堆芯吊篮压紧弹簧松弛劣化监测奠定了技术基础.
中图分类号:
杨泰波, 刘佳鑫, 彭志科, 罗能, 刘才学. 核反应堆堆芯吊篮压紧弹簧松弛特性[J]. 上海交通大学学报, 2024, 58(8): 1290-1296.
YANG Taibo, LIU Jiaxin, PENG Zhike, LUO Neng, LIU Caixue. Relaxation Characteristics of Hold-Down Spring of Core Support Barrel in Nuclear Reactor[J]. Journal of Shanghai Jiao Tong University, 2024, 58(8): 1290-1296.
[1] | MALAPLATE J, GAVOILLE P, PAGEOT J, et al. Assessment of potential swelling of pressurized water reactor internals the Gondole experiment in Osiris reactor[C]// Fontevraud 9-Contribution of Materials Investigations and Operating Experience to Light Water NPPs’ Safety, Performance and Reliability. Avignon, France: CEA, 2018: cea-02338721. |
[2] | CARTER R D, DAMCOTT D L, ATZMON M, et al. Effects of proton irradiation on the microstructure and microchemistry of type 304L stainless steel[J]. Journal of Nuclear Materials, 1993, 205: 361-373. |
[3] | BRUEMMER S M, SIMONEN E P, SCOTT P M, et al. Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals[J]. Journal of Nuclear Materials, 1999, 274(3): 299-314. |
[4] | 黄超, 许锋, 李世伟. 秦山核电厂堆内构件围板螺栓老化评估[J]. 核动力工程. 2022, 43(Sup.1): 16-21. |
HUANG Chao, XU Feng, LI Shiwei. Aging evaluation of baffle bolts for reactor internals of Qinshan nuclear power plant[J]. Nuclear Power Engineering, 2022, 43(Sup.1): 16-21. | |
[5] | KENIK E A, BUSBY J T. Radiation-induced degradation of stainless steel light water reactor internals[J]. Materials Science & Engineering: R: Reports, 2012, 73(7/8): 67-83. |
[6] | XU C L, ZHANG L, QIAN W J, et al. The studies of irradiation hardening of stainless steel reactor internals under proton and xenon irradiation[J]. Nuclear Engineering & Technology, 2016, 48(3): 758-764. |
[7] | FOX A. Effect of temperature on stress relaxation of several metallic materials[M]//Residual stress and stress relaxation. Boston, USA: Springer, 1982: 181-203. |
[8] | KANG H G, SEONG P H. A real-time monitoring system of core support barrel vibration using FEM data and self-organizing neural networks[J]. Nuclear Engineering & Design, 1995, 158(1): 19-29. |
[9] | 赖姜, 何超, 席志德, 等. 反应堆吊篮在正常和劣化支撑条件下的振动模态特性[J]. 核动力工程. 2016, 37(Sup.2): 20-23. |
LAI Jiang, HE Chao, XI Zhide, et al. Vibration characteristics of a core barrel with conventional and unconventional core support barrel[J]. Nuclear Power Engineering, 2016, 37(Sup.2): 20-23. | |
[10] | International Atomic Energy Agency. Assessment and management of ageing of major nuclear power plant components important to safety: PWR vessel internals[R]. Vienna, Italy: IAEA, 2007: IAEA-TECDOC-1557. |
[11] | WANG M, WANG L, JING J, et al. Study on the reactor core barrel instantaneous characteristics in case of Loss of Coolant Accident (LOCA) scenarios for loop-type PWR[J]. Nuclear Engineering & Design, 2017, 324: 93-102. |
[12] | JIRSA P. Monitoring of the VVER nuclear reactor internals[J]. Nuclear Engineering & Design, 1997, 168(1/2/3): 1-9. |
[13] | KANG H G, SEONG P H. A real-time monitoring system of core support barrel vibration using FEM data and self-organizing neural networks[J]. Nuclear Engineering & Design, 1995, 158(1): 19-29. |
[14] |
张波涛, 朱晔晨, 梅勇, 等. 平直条带流致振动特性实验及其数值模拟研究[J]. 上海交通大学学报, 2020, 54(1): 100-105.
doi: 10.16183/j.cnki.jsjtu.2020.01.013 |
ZHANG Botao, ZHU Yechen, MEI Yong, et al. Experimental and numerical simulation study on flow-induced vibration characteristics of flat strip[J]. Journal of Shanghai Jiao Tong University, 2020, 54(1): 100-105. | |
[15] | 陈宇峰, 陈务军, 何艳丽, 等. 柔性飞艇主气囊干湿模态分析与影响因素[J]. 上海交通大学学报, 2014, 48(2): 234-238. |
CHEN Yufeng, CHEN Wujun, HE Yanli, et al. Dry and wet modal analysis and evaluation of influencing factors for flexible airship envelop[J]. Journal of Shanghai Jiao Tong University, 2014, 48(2): 234-238. | |
[16] | 黄磊, 丁宗华. CAP1400堆内构件压紧弹性环的优化设计[J]. 机械工程师, 2015(6): 123-125. |
HUANG Lei, DING Zonghua. Optimal design of CAP1400 RVI hold-down spring[J]. Mechanical Engineer, 2015(6): 123-125. |
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