| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 1739905 | Nuclear Engineering and Technology | 2016 | 23 Pages |
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.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
Tae Kyu Kim, Sanghoon Noh, Suk Hoon Kang, Jin Ju Park, Hyun Ju Jin, Min Ku Lee, Jinsugn Jang, Chang Kyu Rhee,