과제정보
본 연구는 한국연구재단을 통해 과기부 원자력연구개발사업(2021M2E4A1037979, RS-2022-00143718)의 지원을 받아 수행되었다.
참고문헌
- Kim, S. W., Kim, D. J., and Jin, Y. G., 2015, "Benchmarking of Recent Technology for IASCC Evaluation of Neutron-irradiated Materials," Korea Atomic Energy Research Institute, Daejeon, KAERI/AR/1078.
- Hong, J. H., 2013, chapter 4.3 Structural Materials, Nuclear Materials, 2nd ed, Hans House, Seoul.
- Kim, S. W., Kim, H. P., Choi, M. J., Cho, S. H., Lee, J. Y., Lim, Y. S., and Kim, D. J., 2023, "Technical Report on Corrosion Resistance of Stainless Steel for Welded Reactor Vessel Internals," Korea Atomic Energy Research Institute, Daejeon, KAERI/TR-10038/2023.
- Kim, S. W., Hwang, S. S., Lim, Y. S., Kim, D. J., Choi, M. J., Kwon, J. H., Jin, H. H., and Lee, S. R., 2016, "Technical Report on IASCC models of PWR reactor internals," Korea Atomic Energy Research Institute, Daejeon, KAERI/TR-6404/2016.
- Lim, Y. S., Kim, D. J., Kim, S. W., Jin, H. H., Kim, H. P., Choi, M. J., Cho, S. H., Lee, J. Y., and Lee, S. R., 2022, "Microstructural analyses of the core structural components and their welds in domestic nuclear power plants," Korea Atomic Energy Research Institute, Daejeon, KAERI/TR-9552/2022.
- Fukuya, K., Fujii, K., and Kitsunai, Y., 2005, "DEFORMATION STRUCTURE IN 316 STAINLESS STEEL IRRADIATED IN A PWR," Proc. of the 12th International Conference on Environmental Degradation of Materials in Nuclear Power System-Water Reactors, TMS, pp. 389-393.
- Cho, S. H., Kim, S. W., and Hwang, S. S., "Study of Stainless Steel 304 using IASCC Test Facility(ITF) Mock-up," The Korean Institute of Surface Engineering, Jeju, 2023 May 17-19, pp. 170.
- Kim, S. W., Hwang, S. S., and Lee, J. M., 2015, "Effect of Local Strain Distribution on Stress Corrosion Cracking of Cold-Rolled Alloy 690 With Inhomogeneous Microstructure," Corrosion Science Section, Vol. 71, No. 9, doi:http://dx.doi.org/10.5006/1652.
- Kim, H. P., Lee, J. Y., Cho, S. H., Choi, M. J., Kim, S. W., Kim, D. J., Hwang, S. S., and Lim, Y. S., 2021, "Analysis on relationship between delta ferrite and cracking in austenitic stainless steels," Korea Atomic Energy Research Institute, Daejeon, KAERI/AR1336/2021.