Share This Article:

Development of Advanced Radiation Resistant ODS Steel for Fast Reactor System Applications

Abstract Full-Text HTML XML Download Download as PDF (Size:233KB) PP. 125-128
DOI: 10.4236/wjet.2015.33C019    3,174 Downloads   3,498 Views   Citations

ABSTRACT

A sodium-cooled fast reactor (SFR) is being developed at the Korea Atomic Energy Research Institute (KAERI). As in-core structural material for a SFR, advanced radiation resistant ODS steel (ARROS) has been developed. This paper summarizes the current status of ARROS development regarding an ODS steel composition, fabrication technology of ODS steel structural components and key joining technologies of ODS steel structural components.

Conflicts of Interest

The authors declare no conflicts of interest.

Cite this paper

Kim, T. , Noh, S. , Kang, S. , Jin, H. and Kim, G. (2015) Development of Advanced Radiation Resistant ODS Steel for Fast Reactor System Applications. World Journal of Engineering and Technology, 3, 125-128. doi: 10.4236/wjet.2015.33C019.

References

[1] Kim, T.K. and Kim, S.H. (2011) Study on the Cold Working Process for FM Steel Cladding Tubes. Journal of Nuclear Materials, 411, 208-212. http://dx.doi.org/10.1016/j.jnucmat.2011.02.017
[2] Noh, S. Choi, B.K., Kang, S.H. and Kim, T.K. (2014) Influence of Mechanical Alloying Atmospheres on the Microstructures and Mechanical Properties of 15Cr ODS Steels. Nuclear Engineering and Technology, 46, 857-862. http://dx.doi.org/10.5516/NET.07.2013.096
[3] Mao, X., Kim, T.K., Kim, S.S., Han, Y.S., Oh, K.H. and Jang, J. (2015) Crystallographic Relationship of YTaO4 Particles with Matrix in Ta-Containing 12Cr ODS Steel. Journal of Nuclear Materials, 461, 329-335. http://dx.doi.org/10.1016/j.jnucmat.2015.03.018
[4] Noh, S., Kimura, A. and Kim, T.K. (2014) Diffusion Bonding of 9Cr ODS Ferritic/Martensitic Steel with a Phase Transformation. Fusion Engineering and Design, 89, 1746-1750. http://dx.doi.org/10.1016/j.fusengdes.2013.12.023
[5] Jeong, Y.H., Kim, W.J., Kim, D.J., Jang, J., Kang, S.H., Chun, Y.B. and Kim, T.K. (2014) Development of Advanced Structural Materials for Future Nuclear Systems in Korea. Proce-dia Engineering, 86, 1-7. http://dx.doi.org/10.1016/j.proeng.2014.11.004
[6] Lee, J.G., Park, J.J., Lee, M.K., Rhee, C.K., Kim, T.K., Spirin, A., Krutikov, V. and Paranin, S. (2015) End Closure Joining of Ferritic-Martensitic and Oxide-Dispersion Strengthened Steel Cladding Tubes by Magnetic Pulse Welding. Metallurgical and Materials Transactions A, 46A, 3132-3139. http://dx.doi.org/10.1007/s116601-015-2905-5

  
comments powered by Disqus

Copyright © 2019 by authors and Scientific Research Publishing Inc.

Creative Commons License

This work and the related PDF file are licensed under a Creative Commons Attribution 4.0 International License.