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Volume 32 Issue S1
Mar.  2025
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XU Yu, DONG Jian-ling. Study on Simplified Stress Analysis Model of Steam Generator Tube in 10 MW High Temperature Gas Cooled Reactor[J]. Nuclear Power Engineering, 2011, 32(S1): 61-64.
Citation: XU Yu, DONG Jian-ling. Study on Simplified Stress Analysis Model of Steam Generator Tube in 10 MW High Temperature Gas Cooled Reactor[J]. Nuclear Power Engineering, 2011, 32(S1): 61-64.

Study on Simplified Stress Analysis Model of Steam Generator Tube in 10 MW High Temperature Gas Cooled Reactor

  • Received Date: 2010-12-04
  • Rev Recd Date: 2011-01-26
  • Available Online: 2025-03-08
  • The steam generator tube of 10 MW high temperature gas cooled reactor in Tsinghua University adopts the spiral tube module structure with single-end and small bending radius,and the structure stress shall be ensured below the threshold under normal operation,accident and other operation conditions,to prevent the structure from failure caused by large deformation.This paper uses the finite element software ABAQUS to analyze the stress distribution of such tube under specific operation condition to obtain the stress distribution of spiral tubes of different cycles,to establish the simplified stress analysis model of such type tube,and prepare for the fracture analysis of vulnerable area.

     

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