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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2017.6
- 수록면
- 855 - 864 (10page)
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The control rod assembly controls reactor power by adjusting its position during normaloperation and shuts down chain reactions by its free drop under scram conditions.
Therefore, the drop performance of the control rod assembly is important for the safety ofa nuclear reactor. In this study, the drop performance of the conceptually designed controlrod assembly for the prototype generation IV sodium-cooled fast reactor that is beingdeveloped at the Korea Atomic Energy Research Institute as a next-generation nuclearreactor was experimentally investigated. For the performance test, the test facility and testprocedure were established first, and several free drop performance tests of the control rodassembly under different flow rate conditions were then carried out. Moreover, performancetests under several types and magnitudes of seismic loading conditions were alsoconducted to investigate the effects of seismic loading on the drop performance of thecontrol rod assembly. The drop time of the conceptually designed control rod assembly for0% of the tentatively designed flow rate was measured to be 1.527 seconds, and this agreeswell with the analytically calculated drop time. It was also observed that the effect ofseismic loading on the drop time was not significant.
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참고문헌 (25)
참고문헌 신청
P. Dufour / 2015 / Sodium fast reactor / 3rd GIF Symposium 2015/ICONE23 Conference
R. Nakai / 2015 / Safety design criteria (SDC) development for generation-IV sodium-cooled fast reactor system / 3rd GIF Symposium 2015/ICONE23 Conference
P. Chellapandi / 2011 / Overview of SFR safety in India / Second Joint GIF-IAEA/INPRO Consultancy Meeting on Safety Aspects of SFRs
H. Kamide / 2013 / Sodium experiments on natural circulation decay heat removal and 3D simulation of plenum thermal hydraulics / International Conference on Fast Reactors and Related Fuel Cycle
유재운 / 2016 / Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea / Nuclear Engineering and Technology 48(5):1059~1070
R. Nakai / 2015 / Safety design criteria (SDC) development for generation-IV sodium-cooled fast reactor system / 3rd GIF Symposium 2015/ICONE23 Conference
P. Chellapandi / 2011 / Overview of SFR safety in India / Second Joint GIF-IAEA/INPRO Consultancy Meeting on Safety Aspects of SFRs
H. Kamide / 2013 / Sodium experiments on natural circulation decay heat removal and 3D simulation of plenum thermal hydraulics / International Conference on Fast Reactors and Related Fuel Cycle
유재운 / 2016 / Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea / Nuclear Engineering and Technology 48(5):1059~1070
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