Nuclear Engineering and Technology | |
Assessment of thermal fatigue induced by dryout front oscillation in printed circuit steam generator | |
Sang Ji Kim1  Sung Gil Shin2  Jeong Ik Lee2  Doh Hyeon Kim2  Jin Su Kwon2  | |
[1] Corresponding author.;Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology, 373-1 Guseong-dong, Yuseong-gu, Daejeon, 305-701, Republic of Korea; | |
关键词: PCSG; Thermal fatigue; Dryout oscillation; FEM; | |
DOI : | |
来源: DOAJ |
【 摘 要 】
A printed circuit steam generator (PCSG) is being considered as the component for pressurized water reactor (PWR) type small modular reactor (SMR) that can further reduce the physical size of the system. Since a steam generator in many PWR-type SMR generates superheated steam, it is expected that dryout front oscillation can potentially cause thermal fatigue failure due to cyclic thermal stresses induced by the transition in boiling regimes between convective evaporation and film boiling. To investigate the fatigue issue of a PCSG, a reference PCSG is designed in this study first using an in-house PCSG design tool. For the stress analysis, a finite element method analysis model is developed to obtain the temperature and stress fields of the designed PCSG. Fatigue estimation is performed based on ASME Boiler and pressure vessel code to identify the major parameters influencing the fatigue life time originating from the dryout front oscillation. As a result of this study, the limit on the temperature difference between the hot side and cold side fluids is obtained. Moreover, it is found that the heat transfer coefficient of convective evaporation and film boiling regimes play an essential role in the fatigue life cycle as well as the temperature difference.
【 授权许可】
Unknown