Failure Evaluation Plan of a Reactor Internal Components of a Decommissioned Plant |
Hwang, Seong Sik
(Korea Atomic Energy Research Institute)
Kim, Sung Woo (Korea Atomic Energy Research Institute) Choi, Min Jae (Korea Atomic Energy Research Institute) Cho, Sung Hwan (Korea Atomic Energy Research Institute) Kim, Dong Jin (Korea Atomic Energy Research Institute) |
1 | Z. Jiao, J. T. Busby, and G. S. Was, Deformation microstructure of proton-irradiated stainless steels, Journal of Nuclear Materials, 361, 218 (2007). Doi: https://doi.org/10.1016/j.jnucmat.2006.12.012 DOI |
2 | O. K. Chopra and A. S. Rao, A review of irradiation effects on LWR core internal materials - IASCC susceptibility and crack growth rates of austenitic stainless steels, Journal of Nuclear Materials, 409, 235 (2011). Doi: https://doi.org/10.1016/j.jnucmat.2010.12.001 DOI |
3 | C. G Lee, Project for facility modification of baffle former bolt retrieval from Kori unit 1, KEPCO KPS (2020). |
4 | ASTM E 8-01, Standard Test Methods for Tension Testing of Metallic Materials, ASTM International, West Conshohocken, PA (2001). Doi: https://doi.org/10.1520/E0008-01 |
5 | K. H. Na, et al., KNS workshop, Research progress and plan for the utilization of Kori 1 harvesting materials, Oct. 23, Ilsan, Korea (2019). |
6 | S. Hwang, et al., Development of Life Prediction and Extension Technologies of Nuclear Reactor Internals, KAERI/RR-4098/2016, Daejeon, Korea (2016). |
7 | G. F. Somville, Proc. 17th International conference on nuclear engineering (ICONE17), ASME, July 12-16, Brussels, Belgium (2009). |
8 | Y. S. Lim, D. J. Kim, S. S.Hwang, M. J. Choi, and S. W. Cho, Effects of Proton Irradiation on the Microstructure and Surface Oxidation Characteristics of Type 316 Stainless Steel, Corrosion Science and Technology, 20, 158 (2021). Doi: https://doi.org/10.14773/cst.2021.20.3.158 DOI |
9 | Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines (MRP-227, Revision 1-A), EPRI, Palo Alto, CA, USA (2019). |
10 | S. S. Hwang, et al., PRIMA-NET workshop, Development of failure and degradation analysis technologies of reactor internal baffle former bolts from decommissioning NPP, Jan. 16, Gimcheon, Korea (2020). |
11 | J. Smith, EPRI - NRC Materials Meeting, EPRI Irradiated Materials Testing Programs, ML13162A571, USNRC, USA (2013). https://www.nrc.gov/docs/ML1316/ML13162A571.pdf |