참고문헌
- 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
- 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
- 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
- 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
- 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).
- 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
- 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).
- 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
- 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).
- 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
- 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
- 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
- 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
- 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
- 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
- R. Marshall and M. Louthan Jr., "Tensile Properties of Zircaloy with Oriented Hydrides," Trans. ASM. vol. 56, pp. 693 (1963).
- 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).
- 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
- 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
- H. Kim et al., "Evaluation of Hydride Effect on Fuel Cladding Degradation," Korean J. Met. Mater. vol. 48, pp. 717 (2010).
- 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).