Comparison of the PLCS Malfunction Event Analyses by using the CESEC III and MEDUSA Codes

• Oh, Myung-Taek;Park, Chan-Eok;Kim, Shin-Whan;Seo, Jong-Tae
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 2004.10a
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  • pp.443-444
  • /
  • 2004
• PDF

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
  • /
  • 2004.10a
  • /
  • pp.425-426
  • /
  • 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
  • /
  • pp.207-208
  • /
  • 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
  • /
  • 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

An Analysis of the Passive Autocatalytic Recombiner performance Under a Design Basis Accident for an Implementation into the KNGR

• Lee, Byung-Chul;Jang, Young-Sik;Ko, Hee-Jin;Lee, Se-Won;Park, Jong-Woon
• • Proceedings of the Korean Nuclear Society Conference
  • /
  • 1999.05a
  • /
  • pp.185-185
  • /
  • 1999
• PDF

In-Core LOCA (PTR) Analysis with Poisoned Moderator

• Kim, S.R.;Kim, B.G.;Kim, T.M.;Choi, J.H.;Kim, Yun-Ho;Choi, Hoon
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.645-646
  • /
  • 2005
• PDF

Evaluation of Time Study for YGN 1 and 2 Fuel Handling Equipment Modifications

• An, B.C.;Sohn, J.H.;Kim, B.S.;Chang, S.G.;Hwang, J.K.;Choi, T.S.
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.1150-1151
  • /
  • 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
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  • pp.167.1-167
  • /
  • 1999
• PDF

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