Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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DELAYED HYDRIDE CRACKING IN ZIRCALOY FUEL CLADDING - AN IAEA COORDINATED RESEARCH PROGRAMME

  • Coleman, C. (AECL, Chalk River Laboratories) ;
  • Grigoriev, V. (Studsvik Nuclear AB) ;
  • Inozemtsev, V. (IAEA, Nuclear Fuel Cycle and Materials Section, Division of Nuclear Fuel Cycle and Waste Technology, Department of Nuclear Energy) ;
  • Markelov, V. (VNIINM, A. A. Bochvar All Russia Research Institute of Inorganic Materials) ;
  • Roth, M. (Institute for Nuclear Research) ;
  • Makarevicius, V. (Lithuanian Energy Institute) ;
  • Kim, Y.S. (Korea Atomic Energy Research Institute) ;
  • Ali, Kanwar Liagat (Pakistan Institute of Nuclear Science and Technology) ;
  • Chakravartty, J.K. (Department of Atomic Energy, Bhabha Atomic Research Centre, Materials Science Division) ;
  • Mizrahi, R. (Comision Nacional de Energia Atomica) ;
  • Lalgudi, R. (Instituto de Pesquisas Energeticas e Nucleares)
  • Published : 2009.03.30
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Abstract

The rate of delayed hydride cracking (DHC), V, has been measured in cold-worked and stress-relieved Zircaloy-4 fuel cladding using the Pin-Loading Tension technique. At $250^{\circ}C$ the mean value of V from 69 specimens was $3.3({\pm}0.8)x10^{-8}$ m/s while the temperature dependence up to $275^{\circ}C$ was described by Aexp(-Q/RT), where Q is 48.3 kJ/mol. No cracking or cracking at very low rates was observed at higher temperatures. The fracture surface consisted of flat fracture with no striations. The results are compared with previous results on fuel cladding and pressure tubes.

Keywords

References

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  5. The Effect of Microstructure on Delayed Hydride Cracking Behavior of Zircaloy-4 Fuel Cladding—An International Atomic Energy Agency Coordinated Research Program vol.7, pp.5, 2010, https://doi.org/10.1520/JAI103008