Creep Analysis of Reactor Pressure Vessel Lower Head under Core Meltdown Severe Accident

Luo Juan; Luo Jiacheng; Li Pengzhou; Sun Lei; Tang Peng

doi:10.13832/j.jnpe.2019.02.0037

Volume 40 Issue 2

Apr. 2019

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2019 > 40(2): 37-41

Luo Juan, Luo Jiacheng, Li Pengzhou, Sun Lei, Tang Peng. Creep Analysis of Reactor Pressure Vessel Lower Head under Core Meltdown Severe Accident[J]. Nuclear Power Engineering, 2019, 40(2): 37-41. doi: 10.13832/j.jnpe.2019.02.0037

Citation:

Luo Juan, Luo Jiacheng, Li Pengzhou, Sun Lei, Tang Peng. Creep Analysis of Reactor Pressure Vessel Lower Head under Core Meltdown Severe Accident[J]. Nuclear Power Engineering, 2019, 40(2): 37-41. doi: 10.13832/j.jnpe.2019.02.0037

Citation:

PDF( 0 KB)

Creep Analysis of Reactor Pressure Vessel Lower Head under Core Meltdown Severe Accident

doi: 10.13832/j.jnpe.2019.02.0037

Publish Date: 2019-04-15

Abstract

Abstract

During the core meltdown severe accident in the nuclear power plants, the strategy of In-Vessel Retention (IVR) to contain the melt in the Reactor Pressure Vessel (RPV) is a key mitigation measure. During the implementation of IVR strategy, the RPV lower head is likely to fail due to excessive creep deformation under the combined action of extremely high temperature loads and mechanical loads. Therefore, it is necessary to perform the analysis of the creep deformation of the RPV lower head, to ensure the structural integrity of the RPV under the condition of melt retention. In this paper, under the assumption of IVR, the finite element method is used to perform the thermal-structural coupling analysis of the RPV lower head. The temperature and stress fields of the vessel wall, and the plasticity and creep deformation of the lower head are calculated. Combining the plasticity and creep rupture criteria, the failure was analyzed. Results show that the deformation of the structure will be greatly increased when creep is considered. During the IVR strategy under severe accident, the main failure mode of the RPV lower head is creep failure instead of plastic failure. Further analysis implies that the internal pressure has a significant influence on the creep deformation and failure time. This paper provides the method for the creep and failure analysis of the RPV lower head under severe accident.
- Severe accident,
- In-vessel retention(IVR),
- Lower head,
- Plastic deformation,
- Creep deformation

FullText(HTML)

References(0)

References

Relative Articles

[1]	Dai Wei, Jiang Pingting, Chen Peng, He Dongyu. Development and Verification of Ph Calculation Model of in-Containment Refueling Water Storage Tank under Severe Accidents[J]. Nuclear Power Engineering, 2023, 44(4): 259-266. doi: 10.13832/j.jnpe.2023.04.0259
[2]	Hu Zhen, Chen Linlin, Ji Songtao, Wei Yansong, Shi Xiaolei, Zheng Guangzong. Experimental Research on Mechanism of Aerosol Re-entrainment Behavior in Containment under Severe Accident Condition[J]. Nuclear Power Engineering, 2023, 44(4): 253-258. doi: 10.13832/j.jnpe.2023.04.0253
[3]	Yang Zhiyi, Shi Xueyao, Zhang Jiajia, Ding Chao, Chong Yimin. Study on Influence of Containment Venting on Hydrogen Risk of Spent Fuel Building under Severe Accident[J]. Nuclear Power Engineering, 2022, 43(5): 163-167. doi: 10.13832/j.jnpe.2022.05.0163
[4]	Wang Xiaoji, Wu Lingjun, Zhu Dahuan, Deng Jian, Liu Lili, Xu Youyou. Risk Analysis of Late Reinjection Pressure in the Primary Circuit under IVR Strategy[J]. Nuclear Power Engineering, 2022, 43(1): 183-186. doi: 10.13832/j.jnpe.2022.01.0183
[5]	Yang Licai, Qiu Tian, Yang Zhihai, Yin Qiwei. Study on High-temperature Creep for Lower Head of HPR1000 Reactor Pressure Vessel[J]. Nuclear Power Engineering, 2022, 43(S2): 202-207. doi: 10.13832/j.jnpe.2022.S2.0202
[6]	Yu Chengxin, Hao Bin, Deng Lingling. Analysis of Impact of Medium Pressure Safety Injection on Severe Accident Process under RRA Connected Mode[J]. Nuclear Power Engineering, 2021, 42(6): 128-134. doi: 10.13832/j.jnpe.2021.06.0128
[7]	Lu Junjing, Mao Yawei, Zhang Tianqi, Zhu Bolin, Yang Xiaoming, Ma Rubing. Study on Gravity Sedimentation of Multicomponent Hygroscopic Aerosols in Reactor Severe Accident[J]. Nuclear Power Engineering, 2021, 42(4): 80-85. doi: 10.13832/j.jnpe.2021.04.0080
[8]	Hu Wenchao, Pan Xinyi, Zhang Pan, Zhao Chuanqi, Sun Haixu, Yi Yan. Analysis of Sentitivity of Fission Product Iodine in Containment to Various Factors under Severe Accidents[J]. Nuclear Power Engineering, 2021, 42(5): 182-188. doi: 10.13832/j.jnpe.2021.05.0182
[9]	Lu Junjing, Zhang Tianqi, Yang Xiaoming, Ma Rubing, Yuan Yidan. Study on Natural Removal of Hygroscopic Aerosols in Reactor Severe Accident[J]. Nuclear Power Engineering, 2020, 41(1): 145-149. doi: 10.13832/j.jnpe.2020.01.0145
[10]	Wang Hongqing, Tang Min, Tang Yueming, Ma Weigang, Zheng Hua, Chu Li, Jiang E. Development of Hydrogen Concentration On-line Monitoring Devices under Severe Accidents in NPPs[J]. Nuclear Power Engineering, 2019, 40(4): 149-152.
[11]	Wang Xuedong, Cao Xuewu, Zhao Xiaoling. Simulation of Radiation Condition in HWR NPPs under a Postulated Severe Accident[J]. Nuclear Power Engineering, 2019, 40(5): 130-134.
[12]	Feng Jian, Liu Aihua, Shen Haibo, Qiu Liqing, Zhao Guozheng, Yuan Zhimin, Qing Mingbing. Research on Radioactive Consequences of Severe Accident of China Engineering Test Reactor[J]. Nuclear Power Engineering, 2018, 39(S2): 103-106. doi: 10.13832/j.jnpe.2018.S2.0103
[13]	He Yilin, Zhang Fan, Zhang Yangwei. Analysis of In-Vessel Retention Capacity for Marine Reactor Severe Accident[J]. Nuclear Power Engineering, 2018, 39(5): 111-116. doi: 10.13832/j.jnpe.2018.05.0111
[14]	Zhang Zhen, Xiong Wanyu, Wang Xiong, Zhuo Wenbin, Li Pengzhou, Zang Jinguang, Song Mingliang. Experimental Research of Critical Heat Flux on Pressure Vessel Lower Head External Surface under Severe Accident[J]. Nuclear Power Engineering, 2016, 37(5): 4-9. doi: 10.13832/j.jnpe.2016.05.0004
[15]	Chen Hang, Zhang Fan, Yan Feng, Wang Kun. Analysis of Blackout Accident and Mitigation Measure for Small Reactors[J]. Nuclear Power Engineering, 2015, 36(2): 62-65. doi: 10.13832/j.jnpe.2015.02.0062
[16]	Zhang Zhuohua, Peng Shinian, Yu Junchong. Model Development of UO₂-Zr Dispersion Plate-Type Fuel Behavior at Early Phase of Severe Accident and Molten Fuel Meat Relocation[J]. Nuclear Power Engineering, 2014, 35(5): 143-147. doi: 10.13832/j.jnpe.2014.04.0143
[17]	ZOU Jie, TONG Lili, CAO Xuewu, GU Jian, XUE Junfeng, JIANG Yu, HAO Lulu, CHOU Suchen, LIU Li. Analysis of Hydrogen Source Term and Effectiveness of Hydrogen Control in Thousand Megawatt PWR Severe Accident[J]. Nuclear Power Engineering, 2013, 34(S1): 47-50.
[18]	YU Hong-xing, LU Qing, HE Xiao-qiang, SU Guang-hui. Model Development on Cooling of Debris Formed of Molten Material in Lower Head[J]. Nuclear Power Engineering, 2013, 34(2): 16-19,39.
[19]	YU Jian, XU Jin-liang, CHEN Wu-xing, TANG Yao-yang. Influence on Injection Occasion to PWR Severe Accident Progression[J]. Nuclear Power Engineering, 2012, 33(4): 9-12.
[20]	YU Hongxing, SU Guanghui, GUAN Zhonghua, HUANG Daishun. Study on Application of CHF Models on Reactor Pressure Vessel Lower Head for Severe Accident Condition[J]. Nuclear Power Engineering, 2012, 33(6): 46-50.

Supplements(0)

Cited By

Cited by

Periodical cited type(10)

1.	杨皓，高鹏程，李济深，翟润泽，张斌. 基于热力学分析的核反应堆压力容器下封头完整性研究. 机械工程学报. 2025(02): 141-150 .
2.	赵阳，兰东宏. 冲击式水轮机配水环管试验封头受力分析. 电站系统工程. 2023(02): 79-81 .
3.	袁显宝，郭盼，张永红. 严重事故下封头失效机理分析. 核科学与工程. 2023(02): 412-420 .
4.	翟润泽，张斌，杨皓，高鹏程，唐绍伟，单建强. 压力容器下封头大变形模型的开发及在FOREVER实验中的应用分析. 核技术. 2023(11): 147-156 .
5.	苏东川，张瀛，杜娟，孙英学，傅孝龙，李辉，邵雪娇，郭素娟. 国产反应堆压力容器用16MND5钢的蠕变损伤本构模型研究. 核动力工程. 2022(01): 232-237 . 本站查看
6.	王小吉，武铃珺，朱大欢，邓坚，刘丽莉，许幼幼. IVR策略下一回路晚期再注水压力风险分析. 核动力工程. 2022(01): 183-186 . 本站查看
7.	王小吉，杨韵佳. 模块式小型堆严重事故下堆芯应急注水策略研究. 科技视界. 2021(12): 85-89 .
8.	杨立才，罗英，邱天，郑浩，曾鹏. 华龙一号反应堆压力容器材料高温性能试验研究. 科技视界. 2020(13): 124-127 .
9.	刘宇生，薛艳芳，王昆鹏，温爽，张钲新，李聪新. 压力容器-保温层流道变形条件下临界热流密度试验研究. 核动力工程. 2020(06): 52-57 . 本站查看
10.	张越，贠相羽，陆雨洲，张会勇，单建强，孙吉良. 基于耦合CFD-FEM方法的严重事故下RPV蠕变失效风险评估. 原子能科学技术. 2020(12): 2431-2438 .