Influence factors of fracture mechanics analysis of reactor pressure vessel under pressurized thermal shock

被引:0
|
作者
Luo J. [1 ]
Luo J.C. [1 ]
机构
[1] Nuclear Power Institute of China, Shuangliu District, Chengdu
来源
Key Eng Mat | 2019年 / 333-339期
关键词
Fracture toughness; Pressurized thermal shock; Reactor pressure vessel; Stress intensity factor;
D O I
10.4028/www.scientific.net/KEM.795.333
中图分类号
学科分类号
摘要
When the reactor pressure vessel (RPV) is subjected to pressurized thermal shock (PTS), the cooling water injected by the emergency core cooling system (ECCS) will generate a large temperature difference in the wall thickness of the pressure vessel. On the other hand, the fracture toughness of the RPV material decreases a lot under long-term neutron irradiation. Under this condition, the PTS transient may cause a rapid growth of defects in the inner surface of the vessel, resulting in failure of the pressure vessel. In this paper, the fracture mechanics analysis method of RPV under pressurized thermal shock is studied. The thermal analysis and structural analysis of the pressure vessel are performed by finite element method. The stress intensity factor and fracture toughness are obtained through calculation. At the same time, the influence factors of fracture mechanics analysis of RPV under PTS condition are analyzed. The effects of different crack size, crack type, load transient, and neutron irradiation flux on the PTS fracture mechanics analysis results are evaluated. Results show that the larger the ratio of length to depth for axial inner surface cracks, the easier RPV crack grows. Under small break condition, the circumferential cracks are safer than axial cracks. The longer the operating time, the more severe the embrittlement of RPV materials, which will lead to the failure of RPV more easily. For the two typical PTS transients studied in this paper, the re-pressurization condition is safer than the small break condition. The results can provide basis for structural integrity assessment of RPV under PTS condition. © 2019 Trans Tech Publications Ltd, Switzerland.
引用
收藏
页码:333 / 339
页数:6
相关论文
共 50 条
  • [41] REACTOR VESSEL INTEGRITY ANALYSIS - APPLICATIONS TO PRESSURIZED THERMAL-SHOCK
    SENGUPTA, S
    MATHAVAN, SK
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1985, 49 (JUN): : 451 - 453
  • [42] Analysis of probabilistic fracture mechanics for PTS of reactor pressure vessel
    Liu, Zhi-Wei
    Qiao, Hong-Wei
    Zhang, Yong
    Hedongli Gongcheng/Nuclear Power Engineering, 2013, 34 (05): : 37 - 40
  • [43] Integrity Evaluation of Korean Nuclear Reactor Pressure Vessel under Pressurized Thermal Shock Conditions According to JEAC
    Kim, Se-Chang
    Choi, Jae-Boong
    Cho, Doo-Ho
    Lee, Sang-Min
    Kim, Yong-Beum
    Chung, Hae-Dong
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2013, VOL 1B: CODES AND STANDARDS, 2014,
  • [44] Sensitive Analyses of Probabilistic Fracture Mechanics for Reactor Pressure Vessel during Pressurized Thermal Shock and Comparison with the Results of International Round Robin Analyses in Asian Countries
    Kanto, Y.
    Yoshimura, S.
    FRACTURE AND STRENGTH OF SOLIDS VII, PTS 1 AND 2, 2011, 462-463 : 878 - +
  • [45] Computational Fluid Dynamics Study of Pressurized Thermal Shock Transients in the Reactor Pressure Vessel
    Jaros, Michal
    Lafferty, Nathan
    Qian, Guian
    Niceno, Bojan
    Niffenegger, Markus
    26TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2017), 2017,
  • [46] Computational fluid dynamics study of pressurized thermal shock phenomena in the reactor pressure vessel
    Sharabi, M.
    Gonzalez-Albuixech, V. F.
    Lafferty, N.
    Niceno, B.
    Niffenegger, M.
    NUCLEAR ENGINEERING AND DESIGN, 2016, 299 : 136 - 145
  • [47] Fracture Assessment for Pressurized Water Reactor Vessel Nozzles Subjected to Pressure and Thermal Loading
    Chu, Qibao
    Qing, Wang
    Fang, Yonggang
    Wei, Tan
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2022, 144 (05):
  • [48] Verification of Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessel
    Li, Yinsheng
    Katsumata, Genshichiro
    Masaki, Koichi
    Hayashi, Shotaro
    Itabashi, Yu
    Nagai, Masaki
    Suzuki, Masahide
    Kanto, Yasuhiro
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2021, 143 (04):
  • [49] Case Study on the Relationship between Safety Margin and Conditional Probability for the Integrity Analysis of Reactor Pressure Vessel under Pressurized Thermal Shock
    Li, Y. B.
    Gao, Z. L.
    Lei, Y. B.
    PRESSURE VESSEL TECHNOLOGY: PREPARING FOR THE FUTURE, 2015, 130 : 1554 - 1563
  • [50] PRESSURE-VESSEL INTEGRITY UNDER PRESSURIZED THERMAL-SHOCK CONDITIONS
    STAHLKOPF, KE
    NUCLEAR ENGINEERING AND DESIGN, 1984, 80 (02) : 171 - 180