Development of 3D CAD O&M Support System for Wolsong Nuclear Power Plant (3차원 CAD 모델을 활용한 월성원자력발전소 운전 및 정비지원 시스템개발)

• 김형진;안호준;장태휘;장희승;창영선
• • Proceedings of the Korea Society for Energy Engineering kosee Conference
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  • 2000.04a
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  • pp.131-136
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  • 2000
• PDF

Components and Operating Characteristics of Vapor Recompression Desalination plant (증기재압축식 해수담수화장치의 구성 및 운전특성)

• 양귀철;김동국;김상현;전원표
• • Proceedings of the Korea Society for Energy Engineering kosee Conference
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  • 2000.04a
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  • pp.243-248
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  • 2000
• PDF

A study on STEP data model of the piping system applicable to nuclear power plant (원자력 플랜트의 배관 시스템 STEP 데이터모델 개발에 관한 기초연구)

• 구여운;박찬국;조광종;안호준;신영균;한순홍
• • Proceedings of the Korea Society for Energy Engineering kosee Conference
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  • 2004.05a
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  • pp.389-394
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  • 2004
• PDF

Common Cause Failure Analysis for the Digital Plant Protection System

• Kang, Hyun-Gook;Jang, Seung-Cheol
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.1313-1314
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  • 2005
• PDF

A Study on the Gasification Characteristics of Chemical plant Liquid Waste through Continuous Operation (연속운전을 통한 화학공장 발생 액상폐기물의 가스화 특성연구)

• 주지선;이정묵;김나랑;정석우;윤용승
• • Proceedings of the Korea Society for Energy Engineering kosee Conference
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  • 2004.11a
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  • pp.103-108
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  • 2004
• PDF

Heat Tracing Temperature Reduction due to Boron Concentration Design Change on BAT for Nuclear Power Plant (원전 붕산수저장탱크 농도 조정에 따른 Heat Tracing 설비 온도감소 연구)

• 송동수;이창섭
• • Proceedings of the Korea Society for Energy Engineering kosee Conference
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  • 2004.11a
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  • pp.335-340
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  • 2004
• PDF

An Application of Realistic Evaluation Methodology for Large Break LOCA of KSNP 2 loop Plant

• H. Y. Jun;Y. Jo;B. D. Chung;Lee, Y. J.
• • Proceedings of the Korean Nuclear Society Conference
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  • 1999.10a
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  • pp.164-164
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  • 1999
• PDF

The break-even point analysis due to the RBI application of the petrochemistry plant (석유화학 플랜트의 RBI 적용시 손익분기점 분석)

• Lee Mee-Hae;Choi Song-Chun;Kim Yong-Soo
• • Proceedings of the Korea Society for Energy Engineering kosee Conference
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  • 2006.05a
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  • pp.146-151
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  • 2006
• PDF

Development of Interfacial Drag Model for Bubbly Flow in Downcomer Annulus during Late-reflood phase of DVI Plant, APR1400

• Chung, Bub-Dong;Song, Chul-Hwa;Kwon, Tae-Soon;Kim, In-Goo;Kim, Hho-Jong
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.757-758
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  • 2005
• PDF

Thermal-Hydraulic Analyses for Low Power/Shutdown PSA in Various Plant Operating States

• Son, Young-Seok;Shin, Jee-Young;Lim, Ho-Gon;Park, Jin-Hee;Jang, Seung-Cheol
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.615-616
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  • 2005
• PDF

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