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

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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Main Authors: Tae Kyu Kim, Sanghoon Noh, Suk Hoon Kang, Jin Ju Park, Hyun Ju Jin, Min Ku Lee, Jinsugn Jang, Chang Kyu Rhee
Format: Article
Language:English
Published: Elsevier 2016-04-01
Series:Nuclear Engineering and Technology
Subjects:
ARROS
Fuel Cladding Tube
ODS
SFR
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573315002648
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spelling doaj-97d9936d370a4971803340dc7756622f2020-11-24T22:32:04ZengElsevierNuclear Engineering and Technology1738-57332016-04-0148257259410.1016/j.net.2015.12.005Current Status and Future Prospective of Advanced Radiation Resistant Oxide Dispersion Strengthened Steel (ARROS) Development for Nuclear Reactor System ApplicationsTae Kyu KimSanghoon NohSuk Hoon KangJin Ju ParkHyun Ju JinMin Ku LeeJinsugn JangChang Kyu RheeAs 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.http://www.sciencedirect.com/science/article/pii/S1738573315002648ARROSFuel Cladding TubeODSSFR
collection DOAJ
language English
format Article
sources DOAJ
author Tae Kyu Kim
Sanghoon Noh
Suk Hoon Kang
Jin Ju Park
Hyun Ju Jin
Min Ku Lee
Jinsugn Jang
Chang Kyu Rhee
spellingShingle Tae Kyu Kim
Sanghoon Noh
Suk Hoon Kang
Jin Ju Park
Hyun Ju Jin
Min Ku Lee
Jinsugn Jang
Chang Kyu Rhee
Current Status and Future Prospective of Advanced Radiation Resistant Oxide Dispersion Strengthened Steel (ARROS) Development for Nuclear Reactor System Applications
Nuclear Engineering and Technology
ARROS
Fuel Cladding Tube
ODS
SFR
author_facet Tae Kyu Kim
Sanghoon Noh
Suk Hoon Kang
Jin Ju Park
Hyun Ju Jin
Min Ku Lee
Jinsugn Jang
Chang Kyu Rhee
author_sort Tae Kyu Kim
title Current Status and Future Prospective of Advanced Radiation Resistant Oxide Dispersion Strengthened Steel (ARROS) Development for Nuclear Reactor System Applications
title_short Current Status and Future Prospective of Advanced Radiation Resistant Oxide Dispersion Strengthened Steel (ARROS) Development for Nuclear Reactor System Applications
title_full Current Status and Future Prospective of Advanced Radiation Resistant Oxide Dispersion Strengthened Steel (ARROS) Development for Nuclear Reactor System Applications
title_fullStr Current Status and Future Prospective of Advanced Radiation Resistant Oxide Dispersion Strengthened Steel (ARROS) Development for Nuclear Reactor System Applications
title_full_unstemmed Current Status and Future Prospective of Advanced Radiation Resistant Oxide Dispersion Strengthened Steel (ARROS) Development for Nuclear Reactor System Applications
title_sort current status and future prospective of advanced radiation resistant oxide dispersion strengthened steel (arros) development for nuclear reactor system applications
publisher Elsevier
series Nuclear Engineering and Technology
issn 1738-5733
publishDate 2016-04-01
description 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.
topic ARROS
Fuel Cladding Tube
ODS
SFR
url http://www.sciencedirect.com/science/article/pii/S1738573315002648
work_keys_str_mv AT taekyukim currentstatusandfutureprospectiveofadvancedradiationresistantoxidedispersionstrengthenedsteelarrosdevelopmentfornuclearreactorsystemapplications
AT sanghoonnoh currentstatusandfutureprospectiveofadvancedradiationresistantoxidedispersionstrengthenedsteelarrosdevelopmentfornuclearreactorsystemapplications
AT sukhoonkang currentstatusandfutureprospectiveofadvancedradiationresistantoxidedispersionstrengthenedsteelarrosdevelopmentfornuclearreactorsystemapplications
AT jinjupark currentstatusandfutureprospectiveofadvancedradiationresistantoxidedispersionstrengthenedsteelarrosdevelopmentfornuclearreactorsystemapplications
AT hyunjujin currentstatusandfutureprospectiveofadvancedradiationresistantoxidedispersionstrengthenedsteelarrosdevelopmentfornuclearreactorsystemapplications
AT minkulee currentstatusandfutureprospectiveofadvancedradiationresistantoxidedispersionstrengthenedsteelarrosdevelopmentfornuclearreactorsystemapplications
AT jinsugnjang currentstatusandfutureprospectiveofadvancedradiationresistantoxidedispersionstrengthenedsteelarrosdevelopmentfornuclearreactorsystemapplications
AT changkyurhee currentstatusandfutureprospectiveofadvancedradiationresistantoxidedispersionstrengthenedsteelarrosdevelopmentfornuclearreactorsystemapplications
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