Feedwater Flow Measurement Using Transit-time Ultrasonic Flow Meter in Nuclear Power Plant

• Ha, Jae-Hong;Jang, Woo-Hyeun;Lee, Byung-Jin;Han, Hee-Han;Kim, Hang-Bae
• • 한국원자력학회:학술대회논문집
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  • 한국원자력학회 2005년도 추계학술발표회
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  • pp.1087-1088
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  • 2005
• PDF

Total Loss of Feedwater Analysis of Power Uprated Kori 3&4

• Park, Seok-Jeong;Han, Kee-Soo;Kim, Cheol-Woo;Choi, Han-Rim;Kim, Eun-Kee
• • 한국원자력학회:학술대회논문집
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  • 한국원자력학회 2005년도 추계학술발표회
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  • pp.420-421
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  • 2005
• PDF

Reactor Coolant System Hot Leg Temperature Reduction in Korean Next Generation Reactor

• Lee, Jung-Pyo;Kim, Jeong-Mann;Yune, Seok-Jeong;Baik, Se-Jin;Ro, Tae-Sun
• • 한국원자력학회:학술대회논문집
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  • 한국원자력학회 1999년도 추계학술발표회요약집
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  • pp.157.1-157
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  • 1999
• PDF

An Estimation of ECC Heat-up During the Reflood Phase of a Cold Leg Break LOCA in KNGR

• Lee, Sang-Yong;Park, Chan-Eok;Lee, Sang-Il;Park, Han-Rim;Park, Chul-Jin
• • 한국원자력학회:학술대회논문집
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  • 한국원자력학회 1999년도 추계학술발표회요약집
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  • pp.132-132
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  • 1999
• PDF

Conservation of the Screm Curve Corresponding to $\pm$0.3 Axial Shape Index in Safety Analysis

• Baek, Seung-Su;Lee, Gyu-Cheon;Kim, Cheol-Woo;Park, Chul-Jin;Jong tae Seo
• • 한국원자력학회:학술대회논문집
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  • 한국원자력학회 1999년도 추계학술발표회요약집
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  • pp.172.1-172
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  • 1999
• PDF

Preliminary Study on Load and Stress Characteristic Evaluation for Handling Reinforcement Device of Spent Nuclear Fuel

• Lee, Jaejun;Kim, Hyeongkoo;Do, Manseok;Lee, Seongki;Yoo, Jongsung
• • 한국방사성폐기물학회:학술대회논문집
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  • 한국방사성폐기물학회 2018년도 추계학술논문요약집
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  • pp.127-128
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  • 2018
• PDF

Transient Analysis of Charging System with Centrifugal Charging Pumps

• Park, H.S.;J.S. Ahn;C.K. Chung;Kim, E.K.;T.S. Ro
• • 한국원자력학회:학술대회논문집
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  • 한국원자력학회 1998년도 추계학술발표회요약집
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  • pp.117-117
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  • 1998
• PDF

Transient Analysis of Letdown System with Letdown Orifices

• J. S. Ahn;Park, H. S.;C. K. Chung;Kim, E. K.;T. S. Ro
• • 한국원자력학회:학술대회논문집
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  • 한국원자력학회 1999년도 춘계학술발표회요약집
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  • pp.93-93
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  • 1999
• PDF

A Study on the Reduction of the Reactor Power Measurement Uncertainty for Use in the RCS Flow Measurement of KSNP

• Oh, Seung-Min;Jang, Oh-Cheol;Lee, Byung-Jin;Cheong, Jong-Sik;Baik, Se-Jin;Kim, Beom-Sik
• • 한국원자력학회:학술대회논문집
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  • 한국원자력학회 2001년도 춘계학술발표회요약집
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  • pp.167-167
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  • 2001
• PDF

Improvement of the Reactor Vessel Closure Head Insulation for the Visual Inspection in the Korean Standard Nuclear Power Plant

• Kim, Seoug-Beom;Chung, Chang-Kyu;Lim, Duck-Jae;Kim, Hyun-Min;Cho, Kwang-Hee;Seo, Jong-Tae
• • 한국원자력학회:학술대회논문집
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  • 한국원자력학회 2005년도 추계학술발표회
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  • pp.963-964
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  • 2005
• PDF

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