본문 바로가기
KERD
논문KCI 등재

Two-way fluid-structure coupling analysis of liquid lead-bismuth main coolant pump based on three different blade materials

0

조회

0

다운로드

0

인용

0

참고문헌

키워드

주제분류원자력공학

초록

The main coolant pump (MCP) operates in a high-temperature, high-flow, and corrosive liquid heavy metal environment, and structure analysis have complicated fluid-structure coupling problems. In order to study the coupling characteristics between the MCP blade and coolant, the present study conducts a two-way fluidstructure coupling analysis of liquid lead-bismuth MCP based on three potential impeller materials: T91 steel, Ti3SiC2, and 304 stainless steel. The deformation, equivalent stress, and modal results on moving blades of MCP under different flow conditions are investigated by employing the CFX and Mechanical modules. The results show that the blades made of Ti3SiC2 material exhibit optimal deformation resistance under different flow conditions, which is 11.18 μm at1.0Qd, while blades made of T91 steel experience the lowest maximum equivalent stress at 1.0Qd, which is 8.62 MPa. The maximum equivalent stress is concentrated at the inner edge of the blade, while the maximum deformation occurs at the outer edge of the blade, with both the maximum equivalent stress and deformation decreasing with increasing flowrate. Compared without coupling, the outlet velocity of the T91 steel impeller is the highest with coupling, which is 5.01 m/s. And head attenuation of the T91 steel impeller is the most serious, which is 2 %.

Abstract

The main coolant pump (MCP) operates in a high-temperature, high-flow, and corrosive liquid heavy metal environment, and structure analysis have complicated fluid-structure coupling problems. In order to study the coupling characteristics between the MCP blade and coolant, the present study conducts a two-way fluidstructure coupling analysis of liquid lead-bismuth MCP based on three potential impeller materials: T91 steel, Ti3SiC2, and 304 stainless steel. The deformation, equivalent stress, and modal results on moving blades of MCP under different flow conditions are investigated by employing the CFX and Mechanical modules. The results show that the blades made of Ti3SiC2 material exhibit optimal deformation resistance under different flow conditions, which is 11.18 μm at1.0Qd, while blades made of T91 steel experience the lowest maximum equivalent stress at 1.0Qd, which is 8.62 MPa. The maximum equivalent stress is concentrated at the inner edge of the blade, while the maximum deformation occurs at the outer edge of the blade, with both the maximum equivalent stress and deformation decreasing with increasing flowrate. Compared without coupling, the outlet velocity of the T91 steel impeller is the highest with coupling, which is 5.01 m/s. And head attenuation of the T91 steel impeller is the most serious, which is 2 %.

관련 논문AI추천

Dynamic structural characteristics of rotor components during the start-up transition of the LFR main coolant pumpLiu Zhiwang, Lu Yonggang, Presas Alexandre, Zhang Zequan, Zhu Rongsheng한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제5호Study on the cantilever ratio optimization of high-temperature molten salt pump for molten salt reactor based on structural integrityFu Yuan, Li Zhi-Jun, Shen Xing-Chao, Yang Jin, Zhang Jian-Yu한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제9호Numerical analysis of the venturi flowmeter in the liquid lead-bismuth eutectic circuit after long-term operationMacian-Juan Rafael, Wang Xiang, Zhang Zhichao한국원자력학회 · Nuclear Engineering and Technology2024 · 제56권 제3호Research on transient hydraulic characteristics of the whole process of reactor coolant pump under shaft stuck accidentWang Xiuli, Wang Zhichen, Xia Qichao, Xu Wei, Yang Shenpeng, Zhao Yuanyuan, Zhu Rongsheng한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제2호Scale effect for hydraulic model of a mixed flow nuclear main pumpTang Shengnan, Zhou Tao, Zhu Yong한국원자력학회 · Nuclear Engineering and Technology2025 · 제57권 제1호Experimental and numerical investigation on the pressure pulsation in reactor coolant pumps under different inflow conditionsHuang Song, Song Yu, Wang Dezhong, Xu Rui, Yin Junlian한국원자력학회 · Nuclear Engineering and Technology2023 · 제55권 제4호

이 간행물의 다른 논문 (59건)