反应堆主泵抗震强度的三维实体模型计算

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Aseismatic Strength Analysis of Main Nuclear Reactor Pump Based on Real Three Dimension Model

Institute of Nuclear Energy and New Energy Technology, Tsinghua University, Beijing, 100084, China

摘要: 用有限元方法做泵的强度验算,一般是使用壳单元,泵的厚度为一个固定值。本文通过CATIA软件建立了与真实主泵完全一致的三维模型,使用四面体单元对建立的模型划分有限元网格,克服了采用壳体单元的近似,使模型的计算结果更加可靠。计算了反应堆主泵的抗震性能。在地震载荷、温度场的作用下,反应堆主泵的最大Mises等效应力为29.9MPa,根据ASME-IIIND3400所确定的该材料许用应力极限值132.825MPa,其完全满足相关规范抗震强度的要求。
- 泵 /
- 反应堆 /
- 抗震 /
- 三维模型
Abstract: When the finite element method is used in the pump strength analysis,the shell element is often used,which has the same thickness for the whole pump.3 dimension main pump model that has the same size and shape as the real main pump is built on the software CATIA.Tetrahedron element,instead of shell element,is used to build the finite element grid that may overcome the same thickness approximation.The calculation is more reliable by the tetrahedron element.The strength of auxiliary reactor pump is safe and fulfills the requirement of the standard document.calculated under the seismic load and temperature field.The maxim Von Mises equivalent stress is 29.9MPa,which is smaller than the allowable stress strength 132.825 MPa in ASME-III ND3400.The main pump is
- Pump /
- Nuclear reactor /
- Aseismatic /
- 3-dimension model