The Effect of a Rod Bundle Mixing Vane on the Critical Heat Flux (핵연료 집합체의 혼합날개가 임계 열유속에 미치는 영향에 대한 이상유동 영역별 고찰)

• 박주환;이준식;석호천
• • Transactions of the Korean Society of Mechanical Engineers
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  • v.18 no.11
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  • pp.2986-2998
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  • 1994
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Heat Transfer Enhancement for Nuclear Fuel Rod Bundle Using Mixing Vane (Mixing Vane에 의한 핵연료 봉다발에서 열전달 촉진)

• Yoo Seong-Yeon;Kim Byeong-Chae;Lee Sang-Sub
• • Proceedings of the SAREK Conference
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  • 2004.11a
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  • pp.126-126
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  • 2004
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Evaluation of a Nuclear Fuel Rod Model Based on Modal Testing Results (진동 테스트에 근거한 핵연료봉 모델 평가)

• Park, Nam-Gyu;Suh, Jung-Min;Jeon, Kyeong-Lak
• • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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  • 2009.04a
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  • pp.571-572
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  • 2009
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Effective Fabrication Method of Rod-shaped ${\gamma}-LiAlO_2$ Particles for Molten Carbonate Fuel Cell Matrices (융융탄산염 연료전지 매트릭스 강화용 봉산 ${\gamma}-LiAlO_2$입자의 제조 방법)

• Kim, Seon-Dong;Hyeon, Sang-Hun
• • Proceedings of the Korean Ceranic Society Conference
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  • 2003.04a
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  • pp.25.2-25
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  • 2003
• PDF

Development of Transportation & Loading device for Spent Nuclear Fuel Rod Cuts (절단연료봉 이송 및 장진장치 개발)

• Hong, D.H.;Jung, J.H.;Kim, H.D.;Yoo, K.S.;Lee, Y.P.;Lee, W.K.
• • Proceedings of the Korean Society of Precision Engineering Conference
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  • 2008.06a
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  • pp.785-786
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  • 2008
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Performance test on the automatic separation device of residual SNF powders from cladding hull (헐(hull)의 잔여분말 자동분리 장치 성능 평가)

• Jung, J.H.;Kim, Y.H.;Kim, G.H.;Lee, H.J.;Yoon, J.S.
• • Proceedings of the Korean Society of Precision Engineering Conference
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  • 2009.10a
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  • pp.379-380
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  • 2009
• PDF

Experimental Dynamic Characteristic Analysis of Annular Fuel Rod According to the Support Condition (환형 연료봉의 지지조건에 따른 동특성 분석)

• Lee, Kang-Hee;Kang, Heung-Seok;Kim, Hyung-Kyu
• • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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  • 2011.04a
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  • pp.700-705
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  • 2011
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A Study of Heat transfer Characteristics of Large Scale Vortex Flow Mixing Vane of Nuclear Fuel Rod Bundle (핵연료집합체에서의 대형이차와류 혼합날개의 열전달 특성에 관한 연구)

• An, Jeong-Su;Choe, Yeong-Don
• • Proceedings of the SAREK Conference
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  • 2005.06a
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  • pp.131-131
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  • 2005
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Prediction of Failure Enthalpy and Reliability of Irradiated Fuel Rod Under Reactivity-Initiated Accidents by Means Of Statistical Approach

• Cheol nam;Park, Byeong-Kwon;Jeong, Yong-Hwan;Jung, Youn-Ho
• • Proceedings of the Korean Nuclear Society Conference
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  • 2001.10a
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  • pp.227.1-227
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  • 2001
• PDF

Microstructure of the Pellet of the K23-M04 Fuel Rod Discharged from Ulchin 2 Nuclear Power Plant (울진 2호기 K23-M04 연료봉 소결체의 미세구조)

• 김영민;서항석;권형문;이찬복;양용식;김대호;김선기;전용범
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.05a
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  • pp.308.2-308.2
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  • 2004
• PDF

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