Comparison of the PSR and the License Renewal

• Lee, J.B.;Park, Y.S.;Bae, B.H.;Kim, B.S.;Roh, M.S.
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.10a
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  • pp.1403-1404
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  • 2004
• PDF

An Analytical Evaluation for the Pressure Drop Characteristics of Bottom Nozzle Flow Holes

• S.G. Yang;Kim, H.J.;H.T. Lim;Park, E.J.;K.L. Jeon
• • Proceedings of the Korean Nuclear Society Conference
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  • 2002.10a
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  • pp.147-147
  • /
  • 2002
• PDF

Analysis of Unsaturated Hydraulic Characteristics Based on Analysis of Grain Size Distribution

• Lee, Jae-Min;Lee, Soo-Hong;Shin, Sang-Won;Park, Jong-Ick;Chung, Hee-Jun;Whang, Joo-Ho;Park, Joo-Wan
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 2004.10a
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  • pp.797-798
  • /
  • 2004
• PDF

Comparison of Safety Assessment Codes for Near-Surface Disposal of LILW with the Compartment Model: SAGE and VR-KHNP

• Kim, H.J.;Park, J.W.;Park, J.B.;Kim, C.L.
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.10a
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  • pp.795-796
  • /
  • 2004
• PDF

The comparison of OFS simulation and measurement results to verify the Wolsong spent fuels in pond area

• Ko, Kwang-Ok;Park, Il-Jin;Kim, Jung-Soo;Kim, Jong-Soo;Min, Gyung-Sik
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.1195-1196
  • /
  • 2005
• PDF

Enhancement of Safety Analysis Reliability For A CANDU-6 Reactor Using RELAP-CANDU/SCAN Coupled Code System

• Kim, Man-Woong;Choi, Yong-Seog;Sin, Chul;Kim, Hyun-Koon;Kim, Hho-Jung;Hwang, Su-Hyun;Hong, In-Seob;Kim, Chang-Hyo
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.575-576
  • /
  • 2005
• PDF

A Visual Inspection System Development for the Reactor Vessel Bottom-mounted Instrument Penetrations

• Jeong, Kyung-Min;Choi, Young-Su;Lee, Sung-Uk;Choi, Chang-Whan;Seo, Yong-Chil;Kim, Chang-Hoi;Jeon, Poong-Woo;Kim, Seung-Ho
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.1337-1338
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  • 2005
• PDF

Seismic Soil-Structure Interaction Analysis of a Consolidated Dry Storage Module for CANDU Spent Fuels

• Kang, Young-Gon;Yoon, Jeong-Hyoun;Cho, Chun-Hyung;Lee, Heung-Young;Choi, Kyu-Sup;Jeong, In-Su;Kim, Jong-Soo
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.10a
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  • pp.434-435
  • /
  • 2005
• PDF

Evaluation of Acceptable pH Control Schemes Based on PWR Fuel Cladding Corrosion

• Kim, Jae-Won;Kim, Hong-Jin;Kim, Oh-Hwan;Joo, Cha-Won;Um, Kil-Sup;Kim, Young-Koo
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.10a
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  • pp.1026-1027
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  • 2004
• PDF

A Review on Investigation Ranges Used in Geological and Seismological Standards for Nuclear Power Plant Siting

• Choi, H.S.;Im, C.B.;Shim, T.M.;Noh, M.;Lee, H.
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.10a
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  • pp.1319-1320
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  • 2004
• PDF

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