| Nuclear Engineering and Technology | |
| Burst pressure estimation of Alloy 690 axial cracked steam generator U-bend tubes using finite element damage analysis | |
| Myeong-Woo Lee1  Jun-Young Jeon2  Jong-Sung Kim3  Yun-Jae Kim4  Ji-Seok Kim4  | |
| [1] Corresponding author.;Korea Atomic Energy Research Institute, Innovative SMR System Development Division, 111, Daedeok-daero, 989 Beon-gil, Yuseong-gu, Daejeon, 34057, Republic of Korea;Korea Institute of Materials Science, Authorized Nuclear Inspection Department, 797, Changwon-daero Seongsan-gu, Changwon-si, Gyeongsangnam-do, 51508, Republic of Korea;Korea University, Department of Mechanical Engineering, Sungbuk-Ku, Seoul, 136-701, Republic of Korea; | |
| 关键词: Alloy 690 steam generator U-bend tube; Burst pressure; Finite element damage analysis; Strain hardening due to the U-bending process; | |
| DOI : | |
| 来源: DOAJ | |
【 摘 要 】
This paper presents numerical estimation of burst pressures of axial cracked U-bend tubes, considering the U-bending process analysis. The validity of the FE simulations is confirmed by comparing with published experimental data. From parametric analyses, it is shown that existing EPRI burst pressure estimation equations for straight tubes can be conservatively used to estimate burst pressures of the U-bend tubes. This is due to the increase in yield strength during the U-bending process. The degree of conservatism would decrease with increasing the bend radius and with increasing the crack depth.
【 授权许可】
Unknown