Evaluation of Reflood HTC and CRF of RELAP5/MOD3.1/K for the New LOCA M/E Analysis

• Park, Seok-Jeong;Kim, Cheol-Woo;Choi, Han-Rim;Kim, Shin-Whan
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.10a
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  • pp.425-426
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  • 2004
• PDF

Development of the SCS Performance Analysis and Capacity Evaluation Code

• Kim, Gil-Gon;Huh, Jin;Park, Seong-Chan;Kim, Eun-Kee
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 2004.10a
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  • pp.207-208
  • /
  • 2004
• PDF

Evaluation of Mechanical Integrity for Helical Coil Hold-Down Spring of $PLUS7^{TM}$ Fuel

• Choi, Ki-Sung;Kim, Yong-Hwan;Kwon, Jung-Tack;Kim, Kyu-Tae
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.10a
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  • pp.843-844
  • /
  • 2004
• PDF

Evaluation of the Containment Integrity Effect for the SIT Fluidic Device Design of SKN 3&4

• Song, Jeung-Hyo;Kim, Cheol-Woo;Choi, Han-Rim;Kim, Shin-Whan
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 2004.10a
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  • pp.453-454
  • /
  • 2004
• PDF

An Evaluation of Non-LOCA Events with Concurrent Common Mode Failure in Digital Plant Protection System for KNGR

• Lee, Cheol-Shin;Lee, Gyu-Cheon;Park, Chul-Jin;Seo, Jong-Tae
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 1999.05a
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  • pp.182-182
  • /
  • 1999
• PDF

Performance Evaluation for Purification Ion Exchanger on the Breakthrough Curves

• Kim, Yu-Hwan;Choi, Hae-Yun;Lim, Duck-Jae;Chung, Chang-Kyu
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.167-168
  • /
  • 2005
• PDF

Temperature Distribution in the Thermal Mixing Tee of Shutdown Cooling System

• Kim, Tae-Han;Huh, Jin;Park, Seong-Chan;Kim, Eun-Kee
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.619-620
  • /
  • 2005
• PDF

Evaluation of Core Flow Rate Coastdown for Ulchin Nuclear Power Plant Unit 4

• Han, Byoung-Sub;Lee, Gyu-Cheon;Park, Chul-Jin;Seo, Jong-Tae
• • Proceedings of the Korean Nuclear Society Conference
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  • 1999.10a
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  • pp.76.1-76
  • /
  • 1999
• PDF

CPC Low Pressure/Low DNBR Trip Setpoint Determination for Steam Generator Tube Rupture Event

• Myeong Yong ohn;Lee, Gyu-Cheon;Park, Chul-Jin;Seo, Jong-Tae
• • Proceedings of the Korean Nuclear Society Conference
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  • 1999.10a
  • /
  • pp.167.1-167
  • /
  • 1999
• PDF

Estimation of Microstructures and Material Properties of HAZ in SA508 Reactor Pressure Vessel

• Kim, J. S.;Lee, S. G.;Park, J. S.;T. E. Jin
• • Proceedings of the Korean Nuclear Society Conference
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  • 2001.10a
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  • pp.203.1-203
  • /
  • 2001
• PDF

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