Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea
Korea imports about 97% of its energy resources due to a lack of available energy resources. In this status, the role of nuclear power in electricity generation is expected to become more important in future years. In particular, a fast reactor system is one of the most promising reactor types for e...
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| Main Authors: | , , , , |
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| Format: | Article |
| Language: | English |
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Wiley
2013-01-01
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| Series: | Science and Technology of Nuclear Installations |
| Online Access: | http://dx.doi.org/10.1155/2013/290362 |
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| _version_ | 1850215427825729536 |
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| author | Yeong-il Kim Yong Bum Lee Chan Bock Lee Jinwook Chang Chiwoong Choi |
| author_facet | Yeong-il Kim Yong Bum Lee Chan Bock Lee Jinwook Chang Chiwoong Choi |
| author_sort | Yeong-il Kim |
| collection | DOAJ |
| description | Korea imports about 97% of its energy resources due to a lack of available energy resources. In this status, the role of nuclear power in electricity generation is expected to become more important in future years. In particular, a fast reactor system is one of the most promising reactor types for electricity generation, because it can utilize efficiently uranium resources and reduce radioactive waste. Acknowledging the importance of a fast reactor in a future energy policy, the long-term advanced SFR development plan was authorized by KAEC in 2008 and updated in 2011 which will be carried out toward the construction of an advanced SFR prototype plant by 2028. Based upon the experiences gained during the development of the conceptual designs for KALIMER, KAERI recently developed advanced sodium-cooled fast reactor (SFR) design concepts of TRU burner that can better meet the generation IV technology goals. The current status of nuclear power and SFR design technology development program in Korea will be discussed. The developments of design concepts including core, fuel, fluid system, mechanical structure, and safety evaluation have been performed. In addition, the advanced SFR technologies necessary for its commercialization and the basic key technologies have been developed including a large-scale sodium thermal-hydraulic test facility, super-critical Brayton cycle system, under-sodium viewing techniques, metal fuel development, and developments of codes, and validations are described as R&D activities. |
| format | Article |
| id | doaj-art-7fd7a68b6a7e49288ab731fdccbc995f |
| institution | OA Journals |
| issn | 1687-6075 1687-6083 |
| language | English |
| publishDate | 2013-01-01 |
| publisher | Wiley |
| record_format | Article |
| series | Science and Technology of Nuclear Installations |
| spelling | doaj-art-7fd7a68b6a7e49288ab731fdccbc995f2025-08-20T02:08:36ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832013-01-01201310.1155/2013/290362290362Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in KoreaYeong-il Kim0Yong Bum Lee1Chan Bock Lee2Jinwook Chang3Chiwoong Choi4Korean Atomic Energy Research Institute (KAERI), 989-111 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of KoreaKorean Atomic Energy Research Institute (KAERI), 989-111 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of KoreaKorean Atomic Energy Research Institute (KAERI), 989-111 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of KoreaKorean Atomic Energy Research Institute (KAERI), 989-111 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of KoreaKorean Atomic Energy Research Institute (KAERI), 989-111 Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of KoreaKorea imports about 97% of its energy resources due to a lack of available energy resources. In this status, the role of nuclear power in electricity generation is expected to become more important in future years. In particular, a fast reactor system is one of the most promising reactor types for electricity generation, because it can utilize efficiently uranium resources and reduce radioactive waste. Acknowledging the importance of a fast reactor in a future energy policy, the long-term advanced SFR development plan was authorized by KAEC in 2008 and updated in 2011 which will be carried out toward the construction of an advanced SFR prototype plant by 2028. Based upon the experiences gained during the development of the conceptual designs for KALIMER, KAERI recently developed advanced sodium-cooled fast reactor (SFR) design concepts of TRU burner that can better meet the generation IV technology goals. The current status of nuclear power and SFR design technology development program in Korea will be discussed. The developments of design concepts including core, fuel, fluid system, mechanical structure, and safety evaluation have been performed. In addition, the advanced SFR technologies necessary for its commercialization and the basic key technologies have been developed including a large-scale sodium thermal-hydraulic test facility, super-critical Brayton cycle system, under-sodium viewing techniques, metal fuel development, and developments of codes, and validations are described as R&D activities.http://dx.doi.org/10.1155/2013/290362 |
| spellingShingle | Yeong-il Kim Yong Bum Lee Chan Bock Lee Jinwook Chang Chiwoong Choi Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea Science and Technology of Nuclear Installations |
| title | Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea |
| title_full | Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea |
| title_fullStr | Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea |
| title_full_unstemmed | Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea |
| title_short | Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea |
| title_sort | design concept of advanced sodium cooled fast reactor and related r d in korea |
| url | http://dx.doi.org/10.1155/2013/290362 |
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