Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Evaluation of axial and tangential ultimate tensile strength of zirconium cladding tubes

  • Kiraly, Marton (Centre for Energy Research of the Hungarian Academy of Sciences (MTA EK)) ;
  • Antok, Daniel Mihaly (Centre for Energy Research of the Hungarian Academy of Sciences (MTA EK)) ;
  • Horvath, Laszlone (Centre for Energy Research of the Hungarian Academy of Sciences (MTA EK)) ;
  • Hozer, Zoltan (Centre for Energy Research of the Hungarian Academy of Sciences (MTA EK))
  • Received : 2017.11.02
  • Accepted : 2018.01.10
  • Published : 2018.04.25
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Abstract

Different methods of axial and tangential testing and various sample geometries were investigated, and new test geometries were designed to determine the ultimate tensile strength of zirconium cladding tubes. The finite element method was used to model the tensile tests, and the results of the simulations were evaluated. Axial and tangential tensile tests were performed on as-received and machined fuel cladding tube samples of both E110 and E110G Russian zirconium alloys at room temperature to compare their ultimate tensile strengths and the different sample preparation methods.

Keywords

References

  1. A. Kaplar, L. Yegorova, K. Lioutov, A. Konobeyev, N. Jouravkova, Mechanical Properties of Unirradiated and Irradiated Zr-1% Nb Cladding, NUREG/IA-0199, 2001.
  2. J. Desquines, B. Cazalis, C. Bernaudat, C. Poussard, X. Averty, P. Yvon, Mechanical properties pf Zircaloy-4 PWR fuel cladding with burnup 54-64 MWd/kgu and implications for RIA behavior, in: Zirconium in the Nuclear Industry, 14th International Symposium, 2004.
  3. A. Griger, L. Maroti, L. Matus, P. Windberg, Ambient and high temperature mechanical properties of ZrNb1 cladding with different oxygen and hydrogen content, Enlarged Halden Programme Group Meeting 24th -29th May 1999, Loen.
  4. E. Hamanishi, True stress vs true strain analysis with results of ring tensile tests, in: Fuel Safety Research Meeting, April 2006. Tokai (Japan).
  5. Sun-Ki Kim, Je-Geon Bang, Dae-Ho Kim, Yong-Sik Yang, Kun-Woo Song, Do-Sik Kim, Mechanical property evaluation of high burn-up nuclear fuel cladding using the ring tensile test, Met. Mater. Int. 15 (4) (August 2009) 547-553. https://doi.org/10.1007/s12540-009-0547-0
  6. Bong-Kook Bae, Sung-Keun Cho, Chang-Sung Seok, A study on ring tensile specimens, Mater. Sci. Eng. A 483-484 (2008) 248-250. https://doi.org/10.1016/j.msea.2006.10.203
  7. S. Majumdar, R. Daum, M. Billone, Update of ANL approach to derivation of stress-strain curves from ring-stretch tensile tests, in: 6th Mechanical Properties Expert Meeting, October 2005. Kyoto (Japan).
  8. V. Grigoriev, R. Jakobsson, B. Josefsson, D. Schrire, Advanced techniques for mechanical testing of irradiated cladding materials, in: Advanced Postirradiation Examination Techniques for Water Reactor Fuel, Proceedings of an IAEA Technical Committee Meeting, Dimitrovgrad, May 2001, pp. 14-18.
  9. L. Yegorova, et al., Database on the Behavior of High Burnup Fuel Rods With Zr1%Nb Cladding and UO2 Fuel (VVER Type) Under Reactivity Accident Conditions, NUREG/IA-0156, Vol. 2, July 1999.
  10. Zoltan Hozer, E. Perez-Fero, Cs Gyori, L. Matus, L. Vasaros, P. Windberg, L. Maroti, M. Horvath, I. Nagy, A. Pinter-Csordas, T. Novotny, Experimental Database of E110 Claddings Under Accident Conditions AEKI-FRL-2007-123-01/01, NEA-1799/01 IFPE/AEKI-EDB-E110. Documentation, Hungarian Academy of Sciences KFKI Atomic Energy Research Institute, Budapest, 2007.
  11. R. Thorpe, I.O. Smith, Tensile properties of Zr-wt1%Nb alloy, J. of Nuclear Materials 78 (1978) 49-57. https://doi.org/10.1016/0022-3115(78)90503-2
  12. A.V. Nikulina, V.A. Markelov, M.M. Peregud, Y.K. Bibiasvili, V.A. Kotrehkov, A.F. Lositsky, N.V. Kuzmenko, Y.P. Shevin, V.K. Shamardin, G.P. Kobylyansky, A.E. Novoselov, Zirconium alloy E635 as a material for fuel rod cladding and other components of VVER and RBMK Cores Zirconium in the nuclear industry: eleventh International Symposium, in: E. Ross Bradley, G.P. Sabol(Eds.), ASTM STP1295, 1996, pp. 785-804.
  13. J. Vesely, M. Valach, Z. Frejtich, V. Priman, Creep Properties of Non-Irradiated ZrNb1 Cladding Tubes under Normal and Abnormal Storage Conditions, vol. 1089, International Atomic Energy Agency -Publications- IAEA TECDOC, 1998, pp. 305-312.

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