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      Decomposition analysis of the sodium void reactivity of the Korean sodium-cooled fast reactor Translated title: Dekompositionsanalyse der Void-Reaktivität des koreanischen Natrium-gekühlten schnellen Reaktors.

      1, , 2 , 1, , 3 , , 1, , 4
      Carl Hanser Verlag

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          To cope with increasing spent fuel disposals and limited domestic spent fuel storages in Korea, the Korea Atomic Energy Research Institute has developed an advanced sodium-cooled fast reactor for TRU transmutation with an electricity output of 600 MWe (called the KALIMER-600 TRU burner). The design philosophy of the KALIMER-600 TRU burner concept is highly focused on inherent safety mechanisms, i.e., passive responses to abnormal and emergency conditions, and thereby minimizes the need for engineered safety systems. Accordingly, the main concern is on the sodium coolant void reactivity, a very important safety parameter of the KALIMER-600 TRU burner. This study was therefore performed to analyze the sodium void reactivity of the KALIMER-600 TRU burner to the finest resolution possible, e.g., contributions from any isotope in each core region. Such detailed analysis could be valuable and applicable to further optimization of the core passive safety characteristics against severe coolant voiding accident conditions.


          Um dem Problem steigender Mengen abgebrannter Brennelemente und begrenzter eigener Lagermöglichkeiten in Korea gewachsen zu sein, hat das koreanische KAERI Forschungsinstitut einen fortgeschrittenen Natrium-gekühlten schnellen Reaktor für TRU Transmutation mit einer elektrischen Leistung von 600 MWe (den sogenannten KALIMER-600 TRU Brenner) entwickelt. Die Ausgestaltung des KALIMER-600 TRU Brennerkonzepts ist stark ausgerichtet auf inhärente Sicherheitsmechanismen und verringert dadurch die Notwendigkeit sicherheitstechnischer Anlagen. Dementsprechend liegt das Hauptinteresse bei der Void-Reaktivität des Natrium-Kühlmittels, einem wichtigen Sicherheitsparameter des KALIMER-600 TRU Brenners. Ziel dieser Studie war deshalb die Analyse der Natrium-Void-Reaktivität mit der bestmöglichen Auflösung. Eine solch detaillierte Analyse könnte auch für weitere Optimierungsmaßnahmen der passiven Sicherheitseigenschaften gegenüber schweren Kühlmittelverluststörfällen wichtig sein.

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          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 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.
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            Annular Fast Reactor Cores with Low Sodium Void Worth for TRU Burning

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              Advanced SFR design concepts and R&D activities


                Author and article information

                Carl Hanser Verlag
                30 November 2014
                : 79
                : 5
                : 385-392
                1 Fast Reactor Development Division, Korea Atomic Energy Research Institute, 1045 Daedeok-daero, Yuseong-gu, Daejeon 305–353, Korea
                2 E-mail: phamha@ 123456kaeri.re.kr
                3 E-mail: sjkim3@ 123456kaeri.re.kr
                4 E-mail: jwyoo@ 123456kaeri.re.kr
                © 2014, Carl Hanser Verlag, München
                : 24 April 2014
                Page count
                References: 13, Pages: 8
                Technical Contributions/Fachbeiträge

                Materials technology,Materials for energy,Nuclear physics
                Materials technology, Materials for energy, Nuclear physics


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