Choi, Chiwoong
(Sodium-Cooled Fast Reactor Design Division, Korea Atomic Energy Research Institute (KAERI), 989-111, Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea)
,
Ha, Kwiseok
(Sodium-Cooled Fast Reactor Design Division, Korea Atomic Energy Research Institute (KAERI), 989-111, Daedeok-Daero, Yuseong-Gu, Daejeon 305-353, Republic of Korea)
,
Jeong, Hae-Yong
(Nuclear Engineering, Sejong University, 209 Neungdong-ro, Gwangjin-gu, Seoul 143-747, Republic of Korea)
KAERI has been developing a prototype Gen-IV sodium cooled fast reactor (PGSFR), which is a pool type and metallic fueled fast reactor in Korea. Unprotected event is an accident accompanying by failure of a reactor protection system. PGSFR is featured by an excellent safety against unprotected event...
KAERI has been developing a prototype Gen-IV sodium cooled fast reactor (PGSFR), which is a pool type and metallic fueled fast reactor in Korea. Unprotected event is an accident accompanying by failure of a reactor protection system. PGSFR is featured by an excellent safety against unprotected events. Therefore, an inherent safety, characteristic such as reactivity feedback is an important parameter in the accident mitigation of the unprotected event. In addition, a metallic fuel has better expansion performance than an oxide fuel in terms of a fuel expansion reactivity feedback. An unprotected reactivity insertion accident is grouped in an unprotected transient over-power (UTOP) event in PGSFR. A typical initiating event for the UTOP is a control rod withdrawal. The withdrawal of a control rod can be limited by a control rod stop system (CRSS), which has been designed to prevent an over power excursion by reactivity insertion. In addition, step of the CRSS and operational logic should be determined by a safety analysis results for control rod withdrawal transients. In this study, analyses for UTOP event of control rod withdrawal in the PGSFR with different reactivity insertion amounts and times were conducted to provide a design guide for the CRSS. (C) 2016 Elsevier Ltd. All rights reserved.
KAERI has been developing a prototype Gen-IV sodium cooled fast reactor (PGSFR), which is a pool type and metallic fueled fast reactor in Korea. Unprotected event is an accident accompanying by failure of a reactor protection system. PGSFR is featured by an excellent safety against unprotected events. Therefore, an inherent safety, characteristic such as reactivity feedback is an important parameter in the accident mitigation of the unprotected event. In addition, a metallic fuel has better expansion performance than an oxide fuel in terms of a fuel expansion reactivity feedback. An unprotected reactivity insertion accident is grouped in an unprotected transient over-power (UTOP) event in PGSFR. A typical initiating event for the UTOP is a control rod withdrawal. The withdrawal of a control rod can be limited by a control rod stop system (CRSS), which has been designed to prevent an over power excursion by reactivity insertion. In addition, step of the CRSS and operational logic should be determined by a safety analysis results for control rod withdrawal transients. In this study, analyses for UTOP event of control rod withdrawal in the PGSFR with different reactivity insertion amounts and times were conducted to provide a design guide for the CRSS. (C) 2016 Elsevier Ltd. All rights reserved.
Nucl. Eng. Des. Cheng 92 227 1986 10.1016/0029-5493(86)90249-9 Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles-bundle friction factors, sub-channel friction factors and mixing parameters
Atomkernenergie Graber 19 23 1972 Experimentelle Untersuchung des Warmeubergangs an Flussigmetall (NaK) in parallel durchstromten Rohrbundeln bei konstanter und exponentieller Warmeflussdichteverteilung
Kazimi 1976 Clinch River Breeder Reactor Plant heat transfer correlation for analysis of CRBRP assemblies
Sci. Technol. Nucl. Installations Kim 21 2013 Advanced design concept of sodium-cooled fast reactor and related R&D
MARS CODE Manual, 2004. Vol. I: Code Structure, System Models, and Solution Methods, KAERI/TR-2812/2004. Koran Atomic Energy Research and Institute.
PRISM Preliminary Safety Information Document, 1986. Vol VI, GEFR-00793 UC-87Ta.
SSC-K Code User Manual Rev. 1, 2002. KAERI/TR-2014/2002. Koran Atomic Energy Research and Institute.
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