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Assessment of thermal fatigue induced by dryout front oscillation in printed circuit steam generator
Nuclear Engineering and Technology  (IF2.341),  Pub Date : 2021-09-08, DOI: 10.1016/j.net.2021.09.004
Jin Su Kwon, Doh Hyeon Kim, Sung Gil Shin, Jeong Ik Lee, Sang Ji Kim

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 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 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 temperature difference between hot side and cold side fluids is obtained. Moreover, it is found that heat transfer coefficient of convective evaporation and film boiling regimes play essential role in the fatigue life cycle as well as determining the hot cold temperature difference limit.