Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Effect of a surface oxide-dispersion-strengthened layer on mechanical strength of zircaloy-4 tubes

  • Jung, Yang-Il (Nuclear Fuel Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Park, Dong-Jun (Nuclear Fuel Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Park, Jung-Hwan (Nuclear Fuel Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Kim, Hyun-Gil (Nuclear Fuel Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Yang, Jae-Ho (Nuclear Fuel Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Koo, Yang-Hyun (Nuclear Fuel Safety Research Division, Korea Atomic Energy Research Institute)
  • Received : 2017.10.16
  • Accepted : 2017.12.01
  • Published : 2018.03.25
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Abstract

An oxide-dispersion-strengthened (ODS) layer was formed on Zircaloy-4 tubes by a laser beam scanning process to increase mechanical strength. Laser beam was used to scan the yttrium oxide ($Y_2O_3$)-coated Zircaloy-4 tube to induce the penetration of $Y_2O_3$ particles into Zircaloy-4. Laser surface treatment resulted in the formation of an ODS layer as well as microstructural phase transformation at the surface of the tube. The mechanical strength of Zircaloy-4 increased with the formation of the ODS layer. The ring-tensile strength of Zircaloy-4 increased from 790 to 870 MPa at room temperature, from 500 to 575 MPa at $380^{\circ}C$, and from 385 to 470 MPa at $500^{\circ}C$. Strengthening became more effective as the test temperature increased. It was noted that brittle fracture occurred at room temperature, which was not observed at elevated temperatures. Resistance to dynamic high-temperature bursting improved. The burst temperature increased from 760 to $830^{\circ}C$ at a heating rate of $5^{\circ}C/s$ and internal pressure of 8.3 MPa. The burst opening was also smaller than those in fresh Zircaloy-4 tubes. This method is expected to enhance the safety of Zr fuel cladding tubes owing to the improvement of their mechanical properties.

Keywords

References

  1. Y.-H. Koo, J.-H. Yang, J.-Y. Park, K.-S. Kim, H.-G. Kim, D.-J. Kim, Y.-I. Jung, K.- W. Song, KAERI's development of LWR accident-tolerant fuel, Nucl. Technol. 186 (2014) 295-304. https://doi.org/10.13182/NT13-89
  2. H.-G. Kim, I.-H. Kim, Y.-I. Jung, D.-J. Park, J.-Y. Park, Y.-H. Koo, Microstructure and mechanical strength of surface ODS treated Zircaloy-4 sheet using laser beam scanning, Nucl. Eng. Technol. 46 (2014) 521-528. https://doi.org/10.5516/NET.07.2014.027
  3. H.-G. Kim, J.-H. Yang, W.-J. Kim, Y.-H. Koo, Development status of accident-tolerant fuel for light water reactors in Korea, Nucl. Eng. Technol. 48 (2016) 1-15. https://doi.org/10.1016/j.net.2015.11.011
  4. Y.-I. Jung, H.-G. Kim, I.-H. Kim, S.-H. Kim, J.-H. Park, D.-J. Park, J.-H. Yang, Y.-H. Koo, Strengthening of Zircaloy-4 using $Y_2O_3$ particles by a laser-beam-induced surface treatment process, Mater. Des. 116 (2017) 325-330. https://doi.org/10.1016/j.matdes.2016.12.023
  5. Y.-I. Jung, H.-G. Kim, H.-U. Guim, Y.-S. Lim, J.-H. Park, D.-J. Park, J.-H. Yang, Surface treatment to form a dispersed $Y_2O_3$ layer on Zircaloy-4 tubes, Appl. Surf. Sci. 429 (2018) 272-277. https://doi.org/10.1016/j.apsusc.2017.06.108
  6. W.H. Meiklejohn, R.E. Skoda, Dispersion hardening, Acta Metall. Mater. 8 (1960) 773-780. https://doi.org/10.1016/0001-6160(60)90172-3
  7. B. Reppich, On the attractive particle-dislocation interaction in dispersion-strengthened material, Acta Mater. 46 (1998) 61-67. https://doi.org/10.1016/S1359-6454(97)00234-6
  8. L. Proville, B. Bako, Dislocation depinning from ordered nanophases in a model fcc crystal: from cutting mechanism to Orowan looping, Acta Mater. 58 (2010) 5565-5571. https://doi.org/10.1016/j.actamat.2010.06.018
  9. D.W. Lim, D.J. Park, J.Y. Park, H. Jang, J.S. Yoo, Y.K. Mok, J.M. Suh, K.M. Lee, Effect of pre-hydriding on the burst behavior of the zirconium cladding under loss-of-coolant accident condition, Korean J. Met. Mater. 52 (2014) 493-502. https://doi.org/10.3365/KJMM.2014.52.7.493
  10. D.J. Park, H.G. Kim, Y.I. Jung, J.H. Park, J.H. Yang, Y.H. Koo, Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions, J. Nucl. Mater. 482 (2016) 75-82. https://doi.org/10.1016/j.jnucmat.2016.10.021
  11. W.G. Burgers, On the process of transition of the cubic-body-centered modification into the hexagonal-close-packed modification of zirconium, Physica 1 (1934) 561-586. https://doi.org/10.1016/S0031-8914(34)80244-3
  12. D. Ciurchea, A.V. pop, C. Gheorghiu, I. Furtuna, M. Todica, A. Dinu, M. Roth, Texture morphology and deformation mechanisms in ${\beta}$-transformed Zircaloy-4, J. Nucl. Mater. 231 (1996) 83-91. https://doi.org/10.1016/0022-3115(96)00350-9
  13. Y.M. Oh, Y.H. Jeong, K.J. Lee, S.J. Kim, Effect of various alloying elements on the martensitic transformation in Zr-0.8Sn alloy, J. Alloy. Compd. 307 (2000) 318-323. https://doi.org/10.1016/S0925-8388(00)00871-9

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