Best Estimate Evaluation of Steam Line Break Accident Using Uncertainty Quantification Method

• Lee C. S.;Jin Y. K.;Kim S. W.;Choi C. J.;Lee S. Y.;Seo J. T.
• • Proceedings of the Korean Nuclear Society Conference
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  • 2003.10a
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  • pp.131-131
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  • 2003
• PDF

Performance Analysis of Westinghouse 3-Loop Plants with CENTS Code

• Song, In-Ho;Sohn, Suk-Whun;Huh, Jae-Young;Lee, Gyu-Cheon;Sohn, Jong-Joo;Kim, Eun-Kee
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.10a
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  • pp.1083-1084
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  • 2005
• PDF

Non-Linear Structural Analysis of Reactor Cavity Permanent Pool Seal Assembly

• Kim, M.G.;Kim, T.H.;Lee, D.H.;Kim, I.Y.;Choi, T.S.
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.10a
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  • pp.1357-1358
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  • 2004
• PDF

Study on Minimization of Weld Deformation for Core Shroud by Application of Design Optimization Technique

• Kim, J. G.;Park, K. W.;J. S. Moon;Y. H. Cho;J. H. Bae
• • Proceedings of the Korean Nuclear Society Conference
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  • 1999.10a
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  • pp.355.1-355
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  • 1999
• PDF

A Study on the Improvement of RCS Leak Rate Calculation Program

• Choi, N.I.;Suh, S.K.;Cho, J.H.;Yune, S.J.;Baik, S.J.;Ko, Y.B.;Shin, D.J.
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.10a
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  • pp.663-664
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  • 2004
• 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
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.10a
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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
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.10a
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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
• • Proceedings of the Korean Nuclear Society Conference
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  • 2001.05a
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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
• • Proceedings of the Korean Nuclear Society Conference
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  • 1999.05a
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  • pp.183-183
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  • 1999
• PDF

Evaluation of Model Driven Development of Safety Critical Software in the Nuclear Power Plant I&C system

• Jung, Jae-Cheon;Chang, Hoon-Seon;Chang, Young-Woo;Kim, Jae-Hack;Sohn, Se-Do
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.10a
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  • pp.1079-1080
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  • 2005
• PDF

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