An Investigation of Structural Integrity and Dynamic Response of CSB in Case of Slanted Contact with RV Outlet Nozzle

Pham Quang Hieu and Ihn Namgung ()
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Pham Quang Hieu: Department of Nuclear Power Plant Engineering, KEPCO International Nuclear Graduation School, 658-91, Haemaji-ro, Seosaeng-myeon, Ulju-gun, Ulsan 45014, Republic of Korea
Ihn Namgung: Department of Nuclear Power Plant Engineering, KEPCO International Nuclear Graduation School, 658-91, Haemaji-ro, Seosaeng-myeon, Ulju-gun, Ulsan 45014, Republic of Korea

Energies, 2024, vol. 17, issue 23, 1-24

Abstract: One of the challenges in the current reactor is the gap between the outlet nozzle of the Reactor Vessel (RV) and the outlet opening of the Core Support Barrel (CSB). This gap causes bypass flow, reducing the overall efficiency. To address this issue, RV and CSB designs were modified with various configurations. Through finite element analysis, this study evaluated the structural integrity and dynamic response of an RV and CSB with these modified designs. The structural integrity was assessed against ASME code to determine the limits of design parameter changes that met code requirements. Additionally, the natural vibration characteristics of the CSB and RV were analyzed to evaluate improvements in the seismic response by modal analysis. The findings revealed that the CSB design in the case of 3-degree slanted contact with the RV outlet nozzle provided the most optimized results. Moreover, modal analysis indicated a substantial enhancement in seismic response, with the dominant CSB mode frequencies increasing by 30%. This shift, from the 15–20 Hz range to the 20–30 Hz range, is especially noteworthy given the concentration of seismic energy within the 1–20 Hz band.

Keywords: bypass flow; Core Support Barrel; dynamic response; structural integrity; slanted contact; Reactor Vessel (search for similar items in EconPapers)
JEL-codes: Q Q0 Q4 Q40 Q41 Q42 Q43 Q47 Q48 Q49 (search for similar items in EconPapers)
Date: 2024
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