Evaluation of the Natural Circulation Capability Test Results for Ulchin Nuclear Power Plant Unit 3

• Sung, Kang-Sik;Jeong, Weon-Sang;Lee, Ju-Han;Seo, Jong-Tae;Lee, Sang-Keun;Mo, Yong-Won;Ryuk, Keun-Su;Shin, Bong-Chul;Kim, Byung-Ho
• • 한국원자력학회:학술대회논문집
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  • 한국원자력학회 1998년도 추계학술발표회요약집
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  • pp.112-112
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  • 1998
• PDF

Development of a Multi-dimensional two Phase Thermal Hydraulic Analysis Code, MEDUSA, and its application to Feed Line Break Analysis

• Park, Chan-Eok;Lee, Sang-Il;Lee, Sang-Yong;Kim, Shin-Whan;Seo, Jong-Tae
• • 한국원자력학회:학술대회논문집
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  • 한국원자력학회 2004년도 추계학술발표회 발표논문집
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  • pp.427-428
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  • 2004
• PDF

Simulation of Three Main Feedwater Pump Operation for SKN 1&2 and SWN 1&2

• Song, In-Ho;Huh, Jae-Young;Lee, Gyu-Cheon;Kim, Shin-Whan;Sohn, Jong-Joo
• • 한국원자력학회:학술대회논문집
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  • 한국원자력학회 2004년도 추계학술발표회 발표논문집
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  • pp.557-558
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  • 2004
• PDF

SOFTWARE VERIFICATION AND VALIDATION METHODOLOGY FOR ADVANCED DIGITAL REACTOR PROTECTION SYSTEM USING DIVERSE DUAL PROCESSORS TO PREVENT COMMON MODE FAILURE

• Son, Ki-Chang;Shin, Hyun-Kook;Lee, Nam-Hoon;Baek, Seung-Min;Kim, Hang-Bae
• • 한국원자력학회:학술대회논문집
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  • 한국원자력학회 2001년도 춘계학술발표회요약집
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  • pp.105.2-105
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  • 2001
• PDF

Evaluation of Multiple Steam Generator Tube Rupture Events for KNGR

• Park, Seok-Jeong;Kim, Cheol-Woo;Park, Chul-Jin;Lee, Sang-Yong;Seo, Jong-Tae
• • 한국원자력학회:학술대회논문집
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  • 한국원자력학회 1999년도 춘계학술발표회요약집
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  • pp.183-183
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  • 1999
• 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

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