Assessment of thermal fatigue induced by dryout front oscillation in printed circuit steam generator
- 1. Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)
- 2. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
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
Additional details
Publishing Information
- Journal Title
- Nuclear Engineering and Technology
- Journal Volume
- 54
- Journal Issue
- 3
- Series
- 33 refs, 25 figs, 1 tab
- Journal Page Range
- p. 1085-1097
- ISSN
- 1738-5733
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 53091698
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- DRYOUT; FILM BOILING; FINITE ELEMENT METHOD; HEAT TRANSFER; LIFE CYCLE; OSCILLATIONS; PRESSURE VESSELS; PRINTED CIRCUITS; PWR TYPE REACTORS; SMALL MODULAR REACTORS; STEAM GENERATORS; STRESS ANALYSIS; THERMAL FATIGUE; THERMAL STRESSES
- Descriptors DEC
- BOILERS; BOILING; CALCULATION METHODS; CONTAINERS; ELECTRONIC CIRCUITS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FATIGUE; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; NUMERICAL SOLUTION; PHASE TRANSFORMATIONS; POWER REACTORS; REACTORS; STRESSES; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS