The Basic Reseach for Guided Wave application of U-Type Feedwater Heater (Guided wave를 이용한 U-Type 급수가열기 적용을 위한 사전 연구)

• Gil, D.S.;Ahn, Y.S.;Park, B.C.
• • Proceedings of the Korean Society of Precision Engineering Conference
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  • 2006.10a
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  • pp.361-362
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  • 2006
• PDF

Application Research of U-Type Feedwater Heater using Guided Wave (Guided Wave 를 이용한 U-Type 급수가열기 적용 연구)

• Park, S.K.;Gil, D.S.;Ahn, Y.S.;Kim, Y.K.;Park, S.J.
• • Proceedings of the Korean Society of Precision Engineering Conference
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  • 2008.06a
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  • pp.763-764
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  • 2008
• PDF

A Study on Applicability of Ultrasonic Flowmeter for Feedwater Flow Measurements Using Measurement Uncertainty Analysis (측정 불확실도 해석을 통한 초음파유량계의 급수유량 측정 적용성 고찰)

• 유성식;손석훈;이병진;손종주;장우현;서종태;황의환;이종선
• • Proceedings of the Korean Nuclear Society Conference
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  • 2003.05a
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  • pp.99.2-99.2
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  • 2003
• PDF

Feedwater Flowrate Monitoring Using the Advanced Signal Processing Based on De-noising and Principal Component Analysis in Nuclear Power Plants

• Gyunyoung Heo;Park, Seong-Soo;Chang, Soon-Heung
• • Proceedings of the Korean Nuclear Society Conference
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  • 1998.10a
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  • pp.105-105
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  • 1998
• PDF

Vibration Reduction for the Feedwater Pump Turbine Piping using Viscous Dampers (감쇠기를 이용한 배관진동 저감 사례)

• Jeon, Chang-Been;Kim, Jung-Soo;Bae, Jae-Whan
• • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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  • 2011.10a
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  • pp.35-37
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  • 2011
• PDF

Transient Thermal Stress Analysis for Module Feedwater Pipe of SMART Steam Generator (SMART증기발생기 모듈급수관의 천이 열응력 해석)

• Kim, Yong-Wan;Kim, Ji-Ho;Park, Jin-Seok;Heo, Hyeong;Kim, Jong-In
• • Proceedings of the Korean Nuclear Society Conference
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  • 1999.05a
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  • pp.437-437
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  • 1999
• PDF

Development and Application for the Main Feedwater Line Break Mass and Energy Releases Analysis Methodology with RETRAN-3D Code

• Song, Dong-Soo;Park, Young-Chan;Jun, Hwang-Yong
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.681-682
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  • 2005
• PDF

Improvement of ECCS and Steam Generator Feedwater Supply System Model in the Simulation of $35\%$ RIH Break Analysis using RELAP/CANDU for Wolsong units 2/3/4 (RELAP/CANDU를 이용한 월성 2, 3, 4호기 원자로 입구모관 $35\%$ 파단사고 평가시 비상노심냉각계통 및 증기발생기 급수조절계통 모델 개선)

• 황수현;박군철;유선오;김만웅;김효정
• • Proceedings of the Korean Nuclear Society Conference
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  • 2003.10a
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  • pp.157-157
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  • 2003
• PDF

Parameter Study for the Feedwater Pipe Break Analysis of an Integral Type Reactor

• Chung, Young-Jong;Kim, Soo-Hyung;Kim, Hee-Cheol;Zee, Sung-Quun
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.10a
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  • pp.522-523
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  • 2005
• PDF

Insulation Performance of a Tube-in-tube Modular Feedwater Line for an In-vessel Once-Through Steam Generator

• Seo, Jae-Kwang;Kang, Han-Ok;Kim, Young-In;Yoon, Ju-hyeon;Zee, Sung-Qunn
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.10a
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  • pp.530-531
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  • 2005
• PDF

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