Structural Integrity Assessment of Once-Through Steam Generator under Density Wave Oscillation Using Finite Element Analysis

In this study, a stress evaluation was performed to verify the structural integrity of the small modular reactor (SMR) steam generator (SG) tube under the loading conditions of density wave oscillation (DWO). Finite element (FE) analysis was conducted using ANSYS Workbench, and the stress evaluation was carried out in accordance with the requirements of the Korea Electric Power Industry Code (KEPIC) MNB 3221.1 and 3222.2. The SMR SG consists of a total of 17 layers composed of multiple tubes. This study analyzed only the tubes in the 1st and 17th rows. The results of the stress evaluation showed that the maximum stress ratios to the allowable stress limits were 26.4% and 14.6% for the 1st and 17th row SG tubes, respectively. The maximum difference in alternating stress intensity was less than 52.4 MPa for Cases 1 and 2 on the 1st row SG tube. According to the design fatigue curve in Figure I-9.2M of ASME Section III Appendices, it was confirmed that the alternating stresses on the SG tubes due to DWO loading cycles can be sustained indefinitely.

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Publication Details

Journal
Nuclear Engineering and Technology
Published
2026-03-01
DOI
https://doi.org/10.1016/j.net.2026.104286
Primary Topic
Wave and Wind Energy Systems
Type
article
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article

Structural Integrity Assessment of Once-Through Steam Generator under Density Wave Oscillation Using Finite Element Analysis

Hun Sik Han, Kwanghyun Ahn, Seongmin Chang, Yunbum Park et al.
Nuclear Engineering and Technology
Wave and Wind Energy Systems
article

Structural Integrity Assessment of Once-Through Steam Generator under Density Wave Oscillation Using Finite Element Analysis

Hun Sik Han, Kwanghyun Ahn, Seongmin Chang, Yunbum Park, Juae Oh
article en

Abstract

In this study, a stress evaluation was performed to verify the structural integrity of the small modular reactor (SMR) steam generator (SG) tube under the loading conditions of density wave oscillation (DWO). Finite element (FE) analysis was conducted using ANSYS Workbench, and the stress evaluation was carried out in accordance with the requirements of the Korea Electric Power Industry Code (KEPIC) MNB 3221.1 and 3222.2. The SMR SG consists of a total of 17 layers composed of multiple tubes. This study analyzed only the tubes in the 1st and 17th rows. The results of the stress evaluation showed that the maximum stress ratios to the allowable stress limits were 26.4% and 14.6% for the 1st and 17th row SG tubes, respectively. The maximum difference in alternating stress intensity was less than 52.4 MPa for Cases 1 and 2 on the 1st row SG tube. According to the design fatigue curve in Figure I-9.2M of ASME Section III Appendices, it was confirmed that the alternating stresses on the SG tubes due to DWO loading cycles can be sustained indefinitely.

Nuclear Engineering and Technology
Korea Atomic Energy Research Institute (KR), Chungnam National University (KR)
Sustainable cities and communities
Openalex Percentile: Top 7%
Wave and Wind Energy Systems
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Structural Integrity Assessment of Once-Through Steam Generator under Density Wave Oscillation Using Finite Element Analysis — Hun Sik Han, Kwanghyun Ahn, et al. · Nuclear Engineering and Technology (2026) | TGRS Research Map | TGRS