Use of Virtual Steam Generator Cassette for Tube Spatial Design and SGC Assembling Procedure (가상증기발생기카세트를 활용한 전열관 공간설계와 카세트 조립)

• 김용완;김종인;지성균
• • Proceedings of the Korean Nuclear Society Conference
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  • 2003.05a
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  • pp.401.1-401.1
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  • 2003
• PDF

한국표준원전 증기발생기 전열관 검사의 방사성폐기물 발생량 분석 및 처리방법에 대한 고찰

• Sim, Eun-Seop;Jin, Jeong-Hwa
• • Proceedings of the Korean Radioactive Waste Society Conference
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  • 2006.11a
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  • pp.144-145
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  • 2006
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Laser weld process monitoring technique for repair welding of steam generator tube (증기발생기 전열관 보수를 위한 레이저 용접공정 감시기술)

• 정진만;백성훈;김철중;장인성
• • Proceedings of the Korean Nuclear Society Conference
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  • 2001.10a
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  • pp.216-216
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  • 2001
• PDF

A Study on the Wear Mechanism of Steam Generator Tube Materials in Room Temperature Water (상온 물분위기에서 증기발생기 전열관 재료의 마모기구에 대한 연구)

• 이영호;김인섭;박영섭;김병섭
• • Proceedings of the Korean Nuclear Society Conference
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  • 2001.10a
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  • pp.263.1-263
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  • 2001
• PDF

Improvement of RELAP5/MOD3 horizontal liquid entrainment/vapor pull-through model for modeling of CANDU reactor outlet and inlet headers (CANDU 원자로의 입.출구 헤더 모의를 위한 RELAP5/MOD3 수평관 액체혼입/증기흡입 모델의 개선)

• 정법동;방영석
• • Proceedings of the Korean Nuclear Society Conference
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  • 2002.05a
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  • pp.133-133
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  • 2002
• PDF

Characteristics for Flaws at Steam Generator Tubes of Korean Standard Nuclear Power Plants (표준형 증기발생기 전열관에 발생한 결함 특성 분석)

• 조찬희;남민우;정지흥;이희종;김세경
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.05a
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  • pp.457.1-457.1
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  • 2004
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Study on the Design Verification of Flow-induced Vibration Analysis in APR1400 S/G (신형경수로 1400 증기발생기 전열관의 유동유발진동해석에 대한 설계검증연구)

• 정대율;이광한;변성철;김무용;박태정
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.05a
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  • pp.91.1-91.1
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  • 2004
• PDF

Evaluation of PbSCC resistance of archive materials of Korean nuclear power plants (국내 원전 증기발생기 전열관 재료의 PbSCC 저항성 평가)

• 황성식;김홍표;한정호;김정수;김주엽
• • Proceedings of the Korean Institute of Surface Engineering Conference
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  • 1999.05a
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  • pp.40-40
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  • 1999
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Development of Tube Leak Model for Analysis Code of SWR in LMR (액체금속로 소듐-물 반응사고 해석코드 전열관 물/증기 누출모형 개발)

• 어재혁;김의광;김성오
• • Proceedings of the Korean Nuclear Society Conference
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  • 2002.10a
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  • pp.154.2-154
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  • 2002
• PDF

Integrity Evaluation for Steam Generator Tube of System Integrated Modular Advanced Reactor (일체형원자로 증기발생기 전열관 건전성 평가)

• 김종성;진태은;정명조;최영환;조종철
• • Proceedings of the Korean Nuclear Society Conference
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  • 2003.10a
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  • pp.319.1-319.1
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  • 2003
• PDF

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