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가중평균을 이용한 핵연료 이물질 여과성능 평가에 관한 연구
박준규(Joon Kyoo Park),이성기(Seong Ki Lee),김재훈(Jae Hoon Kim) 대한기계학회 2017 大韓機械學會論文集A Vol.41 No.2
핵연료는 고도의 신뢰성과 안전성이 요구되는 구조물로서 손상유발 이물질이 유입되지 않도록 이물질여과 기구를 포함하고 있다. 핵연료의 이물질여과 성능은 건전성에 가장 중요한 영향 인자로 합리적이고 객관적으로 평가되어야 하는 지표이다. 본 연구에서는 표준 여과효율 성능지수를 수립하고자 가중평균을 이용하여 종합 이물질여과 효율 계산 방법을 제시하였다. 제안된 방법의 적합성을 확인하기 위해 대표 이물질 시편을 선정하고 이물질여과 실험을 통해 가중평균 여과 효율을 산술평균 여과 효율과 비교하였다. 가중평균법은 성능의 변별력을 강화하고자 이물질의 통과 가능 정도를 가중인자로 사용하였다. 부가적으로 이물질 시편의 크기와 여과 기구의 주요 치수에 따른 상용 핵연료의 여과 거동 분석을 수행하였다. Nuclear fuel requires high reliability and safety and therefore contains debris filtering devices to prevent failure-inducing debris from entering it. The debris filtering performance of nuclear fuel is one of the most important factors for fuel integrity. Therefore, the performance must be evaluated and the measurement must be reasonable. In this study, a calculation method of the comprehensive filtering efficiency using the weighted mean was proposed to establish a standard filtering efficiency index. To confirm the suitability of the proposed method, representative debris specimens were selected and the filtering efficiency with the weighted mean was compared with the efficiency of the arithmetic mean. The weighting factor of the weighted mean was introduced to produce a fair evaluation. In addition, the analysis of the debris filtering mechanism was performed according to the size of debris specimens, and the main dimensions of the filtering feature for commercial nuclear fuel.
와이어를 이용한 경수로 핵연료집합체의 이물질여과 성능 평가 방법론 고찰
박준규(Joon-Kyoo Park),나성현(Seong-Hyeon Na),김재훈(Jae-Hoon Ki) 대한기계학회 2015 대한기계학회 춘추학술대회 Vol.2015 No.11
Fuel failure due to debris is the one of the most severe cause of failure in PWR fuel assembly. To reduce this failure, PWR fuel vendors have developed various anti-debris features which is located at the bottom of fuel assembly. The vendors have performed the debris filtering test to evaluate their filtering efficiencies with their own test facilities and methods. Thus, it is difficult to compare the filtering performance objectively. The standard filtering test procedure and standardized debris specimens are necessary for the reliability of the debris filtering performance assessment. In this paper, debris filtering test facility, wire debris specimens, test procedure for the debris filtering test are described for the standard test procedure. The debris filtering test also performed based on the method KEPCO NF proposed to assess the filtering performance. A comprehensive filtering efficiency is introduced to compare the filtering efficiencies by using weight function for the wire debris size. As a result, the comprehensive filtering efficiency is very useful to compare the filtering performance and could contribute to the mitigation of the debris-induced fuel failure.
정동희,김재훈,윤용근,박준규,전경락,Jeong, Dong-Hee,Kim, Jae-Hoon,Yoon, Yong-Keun,Park, Joon-Kyoo,Jeon, Kyeong-Rak 대한용접접합학회 2012 대한용접·접합학회지 Vol.30 No.1
The spacer grid is one of the main structural components in a fuel assembly. It supports fuel rods, guides cooling water and maintains geometry from external impact load and cyclic stress by the vibration of nuclear fuel rod, it is necessary to have sufficient strength against dynamic external load and fatigue strength. In this study, the mechanical properties and fatigue characteristics of laser beam welded zircaloy thin sheet are examined. The material used in this study is a zirconium alloy with 0.66 mm of thickness. The fatigue strength under cyclic load was evaluated at stress ratio R=0.1. S-N curves are presented with statistical testing method recommend by JSME- S002 and compared with S-N curves at R.T. and $315^{\circ}C$. As a result of the experimental approach, the design guide of fatigue strength is proposed and the results obtained from this study are expected to be useful data for spacer gird design.
유영균(Young Gyun Yoo),김재훈(Jae Hoon Kim),이현승(Hyun Seung Lee),박진무(Jin Moo Park),박준규(Joon Kyoo Park),전경락(Kyeong lak Jeon) 대한기계학회 2010 대한기계학회 춘추학술대회 Vol.2010 No.11
Spacer grid is key-component to support fuel rod in nuclear fuel assembly. Contacting force from spring and dimple and fluid influenced vibration damage to fuel rod and spacer grid. In the study, the stress analysis of spacer grid performed under environment of inside the reactor. And the characteristic of stress distribution evaluated by boundary condition that suitable for this analysis.