Current Status and Future Prospective of Advanced Radiation Resistant Oxide Dispersion Strengthened Steel (ARROS) Development for Nuclear Reactor System Applications

As one of the Gen-IV nuclear energy systems, a sodium-cooled fast reactor (SFR) is being developed at the Korea Atomic Energy Research Institute. As a long-term national research project, advanced radiation resistant oxide dispersion strengthened steel (ARROS) is being developed as an in-core fuel c...

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Published inNuclear engineering and technology Vol. 48; no. 2; pp. 572 - 594
Main Authors Kim, Tae Kyu, Noh, Sanghoon, Kang, Suk Hoon, Park, Jin Ju, Jin, Hyun Ju, Lee, Min Ku, Jang, Jinsugn, Rhee, Chang Kyu
Format Journal Article
LanguageKorean
Published 2016
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Abstract As one of the Gen-IV nuclear energy systems, a sodium-cooled fast reactor (SFR) is being developed at the Korea Atomic Energy Research Institute. As a long-term national research project, advanced radiation resistant oxide dispersion strengthened steel (ARROS) is being developed as an in-core fuel cladding tube material for a SFR in the future. In this paper, the current status of ARROS development is reviewed and its future prospective is discussed.
AbstractList As one of the Gen-IV nuclear energy systems, a sodium-cooled fast reactor (SFR) is being developed at the Korea Atomic Energy Research Institute. As a long-term national research project, advanced radiation resistant oxide dispersion strengthened steel (ARROS) is being developed as an in-core fuel cladding tube material for a SFR in the future. In this paper, the current status of ARROS development is reviewed and its future prospective is discussed.
Author Noh, Sanghoon
Lee, Min Ku
Jin, Hyun Ju
Jang, Jinsugn
Rhee, Chang Kyu
Kim, Tae Kyu
Kang, Suk Hoon
Park, Jin Ju
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  fullname: Rhee, Chang Kyu
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Keywords Fuel Cladding Tube
SFR
ARROS
ODS
Language Korean
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Title Current Status and Future Prospective of Advanced Radiation Resistant Oxide Dispersion Strengthened Steel (ARROS) Development for Nuclear Reactor System Applications
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