DOI QR코드

DOI QR Code

HEAT-UP AND COOL-DOWN TEMPERATURE-DEPENDENT HYDRIDE REORIENTATION BEHAVIORS IN ZIRCONIUM ALLOY CLADDING TUBES

  • Won, Ju-Jin (Dongguk University, Nuclear & Energy System Engineering Dept.) ;
  • Kim, Myeong-Su (Dongguk University, Nuclear & Energy System Engineering Dept.) ;
  • Kim, Kyu-Tae (Dongguk University, Nuclear & Energy System Engineering Dept.)
  • Received : 2014.04.30
  • Accepted : 2014.05.25
  • Published : 2014.10.25

Abstract

Hydride reorientation behaviors of PWR cladding tubes under typical interim dry storage conditions were investigated with the use of as-received 250 and 485ppm hydrogen-charged Zr-Nb alloy cladding tubes. In order to evaluate the effect of typical cool-down processes on the radial hydride precipitation, two terminal heat-up temperatures of 300 and $400^{\circ}C$, as well as two terminal cool-down temperatures of 200 and $300^{\circ}C$, were considered. In addition, two cooling rates of 2.5 and $8.0^{\circ}C/min$ during the cool-down processes were taken into account along with zero stress or a tensile hoop stress of 150MPa. It was found that the 250ppm hydrogen-charged specimen experiencing the higher terminal heat-up temperature and the lower terminal cool-down temperature generated the highest number of radial hydrides during the cool-down process under 150MPa hoop tensile stress, which may be explained by terminal solid hydrogen solubilities for precipitation, and dissolution and remaining circumferential hydrides at the terminal heat-up temperatures. In addition, the slower cool-down rate generates the larger number of radial hydrides due to a cooling rate-dependent, longer residence time at a relatively high temperature that can accelerate the radial hydride nucleation and growth.

Keywords

References

  1. S. Kim, Y. Kwon and Y. Kim, "The Effect of Texture Variation on Delayed Hydride Cracking Behavior of Zr-2.5%Nb Plate," J. Nucl. Mater. vol. 273, pp. 52-59 (1999). https://doi.org/10.1016/S0022-3115(99)00017-3
  2. A. Varias and A. Massih, "Simulation of Hydrogen Embrittlement in Zirconium Alloys under Stress and Temperature Gradients ," J. Nucl. Mater. vol. 279, pp. 273-285 (2000). https://doi.org/10.1016/S0022-3115(99)00286-X
  3. G. Bertolino, G. Meyer, and J., Perez Ipina, "Effects of Hydrogen Content and Temperature on Fracture Toughness of Zircaloy-4," J. Nucl. Mater. vol. 320, pp. 272-279 (2003). https://doi.org/10.1016/S0022-3115(03)00193-4
  4. K. Une and S. Ishimoto, "Dissolution and Precipitation Behavior of Hydrides in Zircaloy-2 and High Fe Zircaloy," J. Nucl. Mater. vol. 322, pp. 66-72 (2003). https://doi.org/10.1016/S0022-3115(03)00320-9
  5. J. Bai, J. Ni, D. Gilbon, C. Prioul and D. Francois, "Hydride Embrittlement in Zircaloy-4 Plate, II. Interaction between the Tensile Stress and the Hydride Morphology," Metall. Mater. Trans. vol. 25A, pp. 1199-1208 (1994).
  6. B. Cox and Y. Wong, "A Hydrogen Uptake Micro-mechanism for Zr alloys ," J. Nucl. Mater. vol. 270, pp.134-146 (1999). https://doi.org/10.1016/S0022-3115(98)00898-8
  7. M. Kim, H. Kim, S. Min and K. Kim, "Cladding Cooling Rate-Dependent Hydride Reorientation and Configuration," Korean J. Met. Mater. vol. 51, pp. 477-486 (2013).
  8. S. Min, M. Kim and K., Kim, "Cooling rate- and hydrogen content-dependent hydride reorientation and mechanical property degradation of Zr-Nb alloy claddings," J. Nucl. Mater. vol. 441, pp. 306-314 (2013). https://doi.org/10.1016/j.jnucmat.2013.06.006
  9. S. Min, M. Kim, C. Won and K. Kim, "Effects of Cooling Rates on Hydride Reorientation and Mechanical Properties of Zirconium Alloy Claddings under Interim Dry Storage Conditions," Korean J. Met. Mater. vol. 51, pp. 487-495 (2013).
  10. Q. Chen, J. Ostien and G. Hansen, "Development of a used fuel cladding damage model incorporating circumferential and radial hydride responses." J. Nucl. Mater. vol. 447, pp. 292-303 (2014). https://doi.org/10.1016/j.jnucmat.2014.01.001
  11. S. Hong, K. Lee and K. Kim, "Effect of the circumferential hydrides on the deformation and fracture of Zircaloy cladding tubes," J. Nucl. Mater. vol. 303, pp. 169-176 (2002). https://doi.org/10.1016/S0022-3115(02)00814-0
  12. S. Hong and K. Lee, "Stress-induced reorientation of hydrides and mechanical properties of Zircaloy-4 cladding tubes," J. Nucl. Mater. vol. 340, pp. 203-208 (2005). https://doi.org/10.1016/j.jnucmat.2004.11.014
  13. K. Lee, Y. Choi, K. Joo, K. Kim and. S. Hong, "Reorientation of Hydrides and Its Effect on the Mechanical Properties of Zr-Nb-Sn-Fe Cladding Tubes," J. Nucl. Sci. Tech., vol. 42, pp. 219-224 (2005). https://doi.org/10.1080/18811248.2005.9726382
  14. M. Louthan Jr. and R. Marshall, "Control of Hydride Orientation in Zircaloy ," J. Nucl. Mater. vol. 9, pp. 170 (1963). https://doi.org/10.1016/0022-3115(63)90132-6
  15. R. Marshall, "Influence of Fabrication History on Stressoriented Hydrides in Zircaloy Tubing," J. Nucl. Mater. vol. 24, pp. 34 (1967). https://doi.org/10.1016/0022-3115(67)90078-5
  16. R. Marshall and M. Louthan Jr., "Tensile Properties of Zircaloy with Oriented Hydrides," Trans. ASM. vol. 56, pp. 693 (1963).
  17. H. Chung, "Understanding Hydride- and Hydrogen-related Processes in High-burnup Cladding in Spent-fuel Storage and Accident Situations," Proceedings of the International Meeting on LWR Fuel Performance, Orlando, FL, U.S.A., pp. 470 (2004).
  18. A. Colas et al., "In-situ Study of Hydride Precipitation Kinetics and Re-orientation in Zircaloy Using Synchrotron Radiation," Acta Mater. vol. 58, pp. 6575 (2010). https://doi.org/10.1016/j.actamat.2010.07.018
  19. H. Kim, Y. Jeong and K. Kim, "The Effects of Creep and Hydride on Spent Fuel Integrity during Interim Dry Storage," Nucl. Eng. Tech. vol. 49, pp. 249 (2010). https://doi.org/10.5516/NET.2010.42.3.249
  20. H. Kim et al., "Evaluation of Hydride Effect on Fuel Cladding Degradation," Korean J. Met. Mater. vol. 48, pp. 717 (2010).
  21. B. Kammenzind et al., "Hydrogen Pickup and Redistribution in Alpha-Annealed Zircaloy-4," International Symposium on Zirconium in the Nuclear Industry, Garmisch-Partenkirchen, Germany, Sep. 11-14, pp. 338 (1995).