Thermal-hydraulic Characteristics of Moderator for CANDU-6 Reactors (CANDU-6 감속재 열유동 해석방법론 개발 (II))

• 유선오;김만웅;김효정;윤철;민병주
• • Proceedings of the Korean Nuclear Society Conference
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  • 2004.05a
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  • pp.96-96
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  • 2004
• PDF

Thermal Hydraulic Analysis of Gas-Cooled Reactors with Annular Fuel Rods

• Han, Kyu-Hyun;Chang, Soon-Heung
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.35-36
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  • 2005
• PDF

Thermal Hydraulic Analyses of Lead-Bismuth Spallation Target System with due regard to Core Temperature Distribution

• Cho, C.H.;Kim, Y.;Song, T.Y.
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.05a
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  • pp.655-656
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  • 2005
• PDF

Development of Water Packing Mitigation Scheme for MARS 3-Dimensional Thermal-hydraulic Module (MARS 코드 3차원 열수력 모듈의 Water Packing완화 루틴 개발)

• 임호곤;이영진;김경두;정법동
• • Proceedings of the Korean Nuclear Society Conference
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  • 2002.10a
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  • pp.149-149
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  • 2002
• PDF

Development of the Thermal Hydraulic Analysis Code for a Copper Bonded Steam Generator (구리밀봉 증기발생기 열유체해석체제 개발)

• 김의광;위명환;어재혁;김성오;백병준
• • Proceedings of the Korean Nuclear Society Conference
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  • 2002.10a
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  • pp.153.1-153
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  • 2002
• PDF

The examination of the effects of the flow baffle on the thermal hydraulic performance of IHX shell side (유동배플이 중간열교환기 셀측 열수력성능에 미치는 영향조사)

• 김의광;심윤섭;김성오;백병준
• • Proceedings of the Korean Nuclear Society Conference
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  • 2002.10a
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  • pp.157.1-157
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  • 2002
• PDF

Improvement of the Thermal Hydraulic Capability of MAAP4 with Implementation of Pseudo Pressure Effect

• Park Chang Hwan;Kim Yong Soo;Lee U. C.;Park G. C.;Suh K. Y.
• • Proceedings of the Korean Nuclear Society Conference
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  • 2003.10a
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  • pp.179-179
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  • 2003
• PDF

A Study on Thermal Hydraulic Analysis of LMR Cores with Inter-assembly Flow Redistribution (집합체간 유량 재분배 현상을 고려한 액체금속로 노심 열유체 해석법)

• 임현진;김영균;김영일;오세기
• • Proceedings of the Korea Society for Energy Engineering kosee Conference
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  • 2004.11a
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  • pp.317-322
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  • 2004
• PDF

Thermal Hydraulic Analysis of Proliferation Resistant KALIMER-600 Single Enrichment Core (핵확산 저항성을 갖는 KALIMER-600 단일 농축 노심의 열유체 해석)

• 김영균;임현진;송훈;김영일
• • Proceedings of the Korea Society for Energy Engineering kosee Conference
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  • 2004.11a
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  • pp.323-328
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  • 2004
• PDF

Thermal Hydraulic Analysis of the MEGAPIE Target under Beam Wandering

• Cho, Chung-Ho;Tak, Nam-il;Song, Tae-Yung
• • Proceedings of the Korean Nuclear Society Conference
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  • 2005.10a
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  • pp.464-465
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  • 2005
• PDF

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