A Study on Improvement of PHWR Safety Analysis Methdology through LBLOCA Assessment for Wolsong Unit 2 (월성 2호기 대형냉각재상실사고 평가를 통한 가압중수로형 원자로 안전해석방법론 개선에 관한 연구)

• 김용수;박군철;이재영;이상규;김만웅;김효정
• • Proceedings of the Korean Nuclear Society Conference
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  • 2002.05a
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  • pp.131.1-131
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  • 2002
• PDF

Thermal Hydraulic Safety Analysis of Inlet Feeder Stagnation Break Accident for Wolsong NPP Unit 1 Loaded with CANFLEX-NU Fuel with respect to the 37-Element Fuel (CANFLEX-NU 연료장전 월성1호기 입구피더관 정체파단사고의 열수력적 해석 (37봉연료장전 월성1호기 대비))

• 김종현;김윤호;전황용
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.05a
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  • pp.166.1-166.1
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  • 2004
• PDF

Development of CANDU Core Operation Support System Based on Core Monitoring System

• Park, Dae-Yu;Lee, Sang-Hoon;Yeom, Choong-Sub;Kim, Yun-Ho;Kim, Yong-Bae;Kim, Seong-Min
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.1243-1244
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  • 2005
• PDF

Risk Analysis due to the Extension of STI for CANDU Diesel Generators

• Jee, Moon-Hak;Choi, Kwang-Hee;Jung, Hyun-Jong;Choi, Seong-Soo;Lim, Jae-Won;Song, Jin-Bae
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.841-842
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  • 2005
• PDF

An Estimation of $^{14}$ C Inventory on Each Unit of Wolsong N.P.P. (월성원전의 각 호기별 $^{14}$ C Inventory 평가)

• Son, Wook;Ji, Jun-Hwa;Kang, Duk-Won;Lee, Dong-Hoon
• • Proceedings of the Korean Nuclear Society Conference
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  • 2002.10a
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  • pp.363-363
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  • 2002
• PDF

Wolsong 2,3&4 Fuel Channel Analysis During a Large Break Loss of Coolant Accident with Loss of ECCS Injection

• Kim, Hyoung-Tae;Rhee, Bo-Wook;Min, Byung-Joo
• • Proceedings of the Korean Nuclear Society Conference
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  • 2002.10a
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  • pp.169-169
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  • 2002
• PDF

Mineralogical Characteristics of the Wolsong LILW Repository (월성 중저준위 방사성폐기물 처분장의 광물학적 특성)

• Kim, Geon-Young;Koh, Yong-Kwon;Park, Kyung-Woo;Choi, Jong-Won;Lee, Eun-Yong
• • Proceedings of the Petrological Society of Korea Conference
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  • 2009.05a
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  • pp.98-100
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  • 2009
• PDF

Fuel Safety Analysis of the Stagnation Feeder Break Accident for Wolsong1 NPP Loaded with CANFLEX-NU Fuel

• Kim Yong-Deog;Kim yun-Ho;Jun Hwang-Yong;Kim Yong-Bae;Lee Chang-Sup
• • Proceedings of the Korean Nuclear Society Conference
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  • 2003.10a
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  • pp.154-154
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  • 2003
• 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

Status of the Demonstration Irradiation of the CANDU New Fuel Bundle CANFLEX-NU in Wolsong Generation Station $\#1$ (중수로용 개량핵연료 CANFLEX-NU의 월성 1호기 시범장전 조사 현황)

• 석호천;전지수;정종엽;조문성;이창섭;김용배;김용덕;이성덕;서형범
• • Proceedings of the Korean Nuclear Society Conference
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  • 2003.10a
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  • pp.316-316
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  • 2003
• PDF

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