铅铋快堆中冷却剂对绕丝棒的冲刷会使棒束产生流致振动，进而使绕丝与包壳间发生微动磨擦，引起包壳磨损。然而在以往的研究中并未考虑热功率条件对流致振动的影响。鉴于此，采用流固热三场耦合方法对铅铋快堆中单根绕丝棒流致振动现象进行研究，研究绕丝棒在不同进口温度条件下的流致振动特性，得到流场参数，并获得绕丝棒变形特性。结果表明：考虑绕丝棒力学参数随温度变化时，振动幅值及模式发生变化；更高的热载荷、更低的换热系数会产生更强烈的流致振动振幅；流体力波动是流致振动加强的原因之一；壁面热功率分布改变不会改变绕丝棒的振动模式，而是通过影响流场与固体域温度从而影响棒的振动幅值。研究成果为铅铋快堆堆芯设计和布置提供改进和优化依据。

The flow-induced vibration of wire-wrapped rod bundles in lead-bismuth cooled fast reactors was caused by coolant erosion, which subsequently leads to fretting friction between the wire wrap and cladding, ultimately resulting in cladding wear. Previous studies has not comprehensively considered the influence of thermal power conditions on flow-induced vibration characteristics. In view of this, a fluid-structure-thermal tri-field coupling methodology was employed to systematically examine the flow-induced vibration phenomena of a single wire-wrapped rod in lead-bismuth cooled fast reactors. The vibration characteristics under different inlet temperature conditions were analyzed through numerical simulations, with both flow field parameters and structural deformation features being obtained. The results reveal that significant variations in vibration amplitude and modal patterns are observed when temperature-dependent mechanical parameters of the wire-wrapped rod are considered. Enhanced vibration amplitudes are identified under conditions of higher thermal loads and lower heat transfer coefficients. Fluid force fluctuations are demonstrated to constitute one of the primary mechanisms responsible for vibration intensification. Although the wall thermal power distribution is found not to alter the fundamental vibration modes, its indirect influence on vibration amplitude is achieved through thermal-structural interactions affecting both fluid dynamics and solid domain temperature fields. These findings are systematically organized to establish an optimized theoretical framework that provides a scientific basis for the improvement of core design and spatial configuration in lead-bismuth cooled fast reactors. The proposed methodology and derived conclusions are validated to offer effective solutions for mitigating flow-induced vibration challenges in advanced nuclear reactor systems.