Effect of Specimen Geometry, Orientation and Temperature on the Impact Toughness of Zr-2.5Nb Pressure Tube

  • Priti Kotak ShahEmail author
  • J. S. Dubey
  • R. N. Singh
  • Ashwini Kumar
  • B. N. Rath
Conference paper
Part of the The Minerals, Metals & Materials Series book series (MMMS)


Impact toughness of Zr-2.5Nb pressure tube material was evaluated as a function of specimen geometry, orientation and test temperature. Two types of samples were used. Curved impact specimens were machined directly from the tube section thereby retaining the pressure tube curvature and flat impact specimens were machined from a flattened tube section subjected to stress relieving treatment. In both the cases the specimen thickness was the actual pressure tube thickness that is 3.5 mm and the other dimension of the impact specimen was 55 mm × 10 mm. The tests were carried out for both as-received and hydrided pressure tubes between room temperature and 300 °C. As the Zr-2.5Nb pressure tube material is anisotropic, the studies were also carried out using specimens with crack growth either along axial or along transverse direction of the tube. The paper describes the results generated and discusses the materials impact toughness behaviour under different conditions.


Zr-2.5Nb Pressure tubes PHWR Impact properties Orientation effects Axial notch Transverse notch 


  1. 1.
    S.A. Bharadwaj, in Design Criterion For Zirconium Alloy Components in NPPs. Proceedings of the Symposium Zirconium-2002, ZIRC-2002 (BARC, Sept 2002), pp. 66–72Google Scholar
  2. 2.
    D. Rodgers, M. Griffiths, G. Bickel, A. Buyers, C. Coleman, H. Nordin, S. St Lawrence, Irradiation effects on Zr-2.5Nb in power reactors. CNL Nucl Rev 5(1), 1–15 (2016)Google Scholar
  3. 3.
    B.A. Cheadle, The development of Zr-2.5Nb pressure tubes for CANDU reactors. J. ASTM Int. JAI 103057. 7(8), 67–87 (2010)Google Scholar
  4. 4.
    N. Saibaba, S.K. Jha, S. Tonpe, K. Vaibhaw, V. Deshmukh, S.V. Ramana Rao, K.V. Mani Krishna, S. Neogy, D. Srivastava, G.K. Dey, B.B. Rath, R.V. Kulkarni, E. Ramadasan, S.A. Anantharaman, tensile properties and fracture toughness of Zr-2.5Nb alloy pressure tubes of IPHWR220. Nucl. Eng. Des. 293, 138–149 (2015)Google Scholar
  5. 5.
    A.K. Bind, R.N. Singh, S. Sunil, J.K. Chakravartty, A. Ghosh, P. Dhandharia, N.S. More, S. Vijayakumar, A.G. Chhatre, Mechanical properties of Zr-2.5Nb pressure tube material manufactured employing forging routes For PHWR700—part 1: tensile behavior. Technical Report BARC/2012/E/002, BARC (2012)Google Scholar
  6. 6.
    R.N. Singh, P. Ståhle, J.K. Chakravartty, A.A. Shmakov, Threshold stress intensity factor for delayed hydride cracking in Zr-2.5%Nb pressure tube alloy. Mater. Sci. Eng. A 523, 112–117 (2009)CrossRefGoogle Scholar
  7. 7.
    Atomic Energy of Canada Limited, Canada Enters the Nuclear Age: A Technical History of Atomic Energy of Canada Limited (McGill–Queens University Press, 1997)Google Scholar
  8. 8.
    C. Song, Irradiation effects on Zr-2.5Nb in power reactors. CNL Nucl. Rev. 5(1), 17–36 (2016)Google Scholar
  9. 9.
    R.N. Singh, S. Mukherjee, A. Gupta, S. Banerjee, Terminal solid solubility of hydrogen in Zr-alloy pressure tube materials. J. Alloys Compd. 389, 102–112 (2005)Google Scholar
  10. 10.
    R.N. Singh, R. Lala Mikin, G.K. Dey, D.N. Sah, I.S. Batra, P. Ståhle, Influence of temperature on threshold stress for reorientation of hydrides and residual stress variation across thickness of Zr-2.5Nb alloy pressure tube. J. Nucl. Mat. 359, 208–219 (2006)Google Scholar
  11. 11.
    R.N. Singh, R. Kishore, S.S. Singh, T.K. Sinha, B.P. Kashyap, Stress-reorientation of hydrides and hydride embrittlement of Zr-2.5 Wt. % Nb pressure tube alloy. J. Nucl. Mater. 325, 26–33 (2004)CrossRefGoogle Scholar
  12. 12.
    P.K. Shah, P.M. Satheesh, R.N. Singh, J.S. Dubey, R.S. Shriwastaw, K.S. Balakrishnan, A.P. Kulkarni, P. Mishra, V.P. Jathar, S. Majumdar, V.D. Alur, S. Anantharaman, J.K. Chakravartty, Anisotropy in impact behavior of Zr-2.5Nb pressure tube alloy. Trans. Indian Inst. Met. 64, 67–70 (2011)Google Scholar
  13. 13.
    R.N. Singh, Flow behavior and hydrogen embrittlement in Zr- 2.5Nb pressure tube alloy. Ph.D. thesis, Indian Institute of Technology, Mumbai, India, 2003Google Scholar
  14. 14.
    U.K. Viswanathan, R.N. Singh, C.B. Basak, S. Anantharaman, K.C. Sahoo, Evaluation of effect of hydrogen on toughness of Zircaloy-2 by instrumented drop weight impact testing. J. Nucl. Mater. 350, 310–319 (2006)CrossRefGoogle Scholar

Copyright information

© The Minerals, Metals & Materials Society 2017

Authors and Affiliations

  • Priti Kotak Shah
    • 1
    Email author
  • J. S. Dubey
    • 1
  • R. N. Singh
    • 1
  • Ashwini Kumar
    • 1
  • B. N. Rath
    • 1
  1. 1.Post Irradiation Examination Division, Mechanical Metallurgy DivisionBhabha Atomic Research CentreMumbaiIndia

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