Finite Element Analysis of CAREM-25 Modular Reactor Pressure Vessel Using ASME-Sec8-Div2-Part5 Code

Document Type : Original Research Paper

Authors

1 Department of Mechanical Engineering, Arak University, Iran.

2 Department of Mechanical Engineering, Technical and Engineering Faculty, Arak University, Arak, Iran.

3 School of Mechanic Engineering, Shahrekord University, Shahrekord, Iran.

10.22084/jrstan.2025.28156.1247

Abstract

This paper deals with the simulation of the pressure vessel of a small modular reactor, which is one of the most key components of nuclear power plants. In this regard, based on the two main factors of pressure and temperature and
considering the operating realities, various load combinations were extracted based on ASME Sec. VIII Div. 2 Part 5, and finite element analysis was performed based on the ASME algorithm for reactor pressure vessel analysis and using standard failure modes, as well as other design considerations. Also, effective factors in the design and safety of the vessel were considered, and finally, by giving the required inputs to the Abaqus finite element software, the software outputs were analyzed. The results obtained indicate that the mechanical design based on ASME-Sec8-Div2-Part5 is largely consistent with the results of the design based on the nuclear section (ASME-Sec3). Because the results had almost the same thickness as the CAREM-25 small modular reactor vessel. Finally, it can be concluded that using the ASME standard along with finite element software and modern finite element-assisted solution methods largely meets the needs of the pressure vessel design department in small modular nuclear power plants.

Keywords

References

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Journal of Stress Analysis
Volume 9, Issue 1
2025
Pages 81-93

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