Advertisement

Creep–Fatigue Assessment for Interaction Between IHX Seal Holder and Inner Vessel Stand Pipe in a Pool-Type Fast Reactor as Per RCC-MR

  • Sanjay Kumar PandeyEmail author
  • S. Jalaldeen
  • K. Velusamy
  • P. Puthiyavinayagam
Conference paper
  • 879 Downloads
Part of the Lecture Notes in Mechanical Engineering book series (LNME)

Abstract

Structural analysis of IHX seal holder and inner vessel stand pipe due to interference has been carried out as per RCC-MR code. The phenomenon of progressive deformation/ratcheting, due to combination of primary stress and secondary stress intensity range, has been checked. The damage due to creep–fatigue interaction has been estimation for IV stand pipe, IHX shroud shell and IHX tubes to avoid the failure. The effective primary stress intensities (P 1 and P 2) and the plastic plus creep strains are found to be within allowable limits for IV and shroud shell. The detailed 3D analysis of IHX due to 4.5-mm interference between shroud shell and tube of IHX has been carried. The stress in the tube is 320 MPa. The fatigue damage and creep damages are 0.043 and 0.271, respectively.

Keywords

Fatigue Creep Creep–fatigue interaction Ratcheting Progressive deformation 

References

  1. 1.
    RCC-MRx, Section III, Tome 1, Sub section Z, Technical Appendix A3, 2012Google Scholar
  2. 2.
    RCC-MRx, Section III, Tome 1, Sub section B: Class N1RX reactor component and supports, 2012Google Scholar

Copyright information

© Springer Nature Singapore Pte Ltd. 2018

Authors and Affiliations

  • Sanjay Kumar Pandey
    • 1
    Email author
  • S. Jalaldeen
    • 1
  • K. Velusamy
    • 1
  • P. Puthiyavinayagam
    • 1
  1. 1.Structural Mechanics Section, Reactor Design GroupIndira Gandhi Centre for Atomic ResearchKalpakkamIndia

Personalised recommendations