Axial SPN and Radial MOC Coupled Whole Core Transport Calculation
CHO, Jin-Young, KIM, Kang-Seog, LEE, Chung-Chan, ZEE, Sung-Quun, JOO, Han-Gyu
Published in Journal of nuclear science and technology (01.09.2007)
Published in Journal of nuclear science and technology (01.09.2007)
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Journal Article
Overpressure protection analysis of an advanced integral reactor
Yang, Soo Hyung, Chung, Young-Jong, Kim, Hee Cheol, Zee, Sung Quun
Published in Nuclear engineering and design (01.11.2006)
Published in Nuclear engineering and design (01.11.2006)
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Journal Article
Analysis of the OECD Main Steam Line Break Benchmark Problem Using the Refined Core Thermal-Hydraulic Nodalization Feature of the MARS/MASTER Code
Joo, Han Gyu, Jeong, Jae-Jun, Cho, Byung-Oh, Lee, Won Jae, Zee, Sung Quun
Published in Nuclear technology (01.05.2003)
Published in Nuclear technology (01.05.2003)
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Journal Article
Conference Proceeding
A Conservative Analysis Methodology for a Steam-Line-Break Accident of the SMART-P Plant
Chung, Young-Jong, Kim, Hee-Kyung, Kim, Hee-Cheol, Zee, Sung-Quun
Published in Nuclear technology (01.01.2006)
Published in Nuclear technology (01.01.2006)
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Journal Article
Assessment of the interchannel mixing model with a subchannel analysis code for BWR and PWR conditions
Hwang, Dae-Hyun, Yoo, Yeon-Jong, In, Wang-Kee, Zee, Sung-Quun
Published in Nuclear engineering and design (01.07.2000)
Published in Nuclear engineering and design (01.07.2000)
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Journal Article
Thermo-mechanical simulation for nozzle header of once-through steam generator by experiment and finite element method
Kim, Yong Wan, Kim, Dong Ok, Lee, Jae Seon, Choi, Suhn, Zee, Sung Quun
Published in The International journal of pressure vessels and piping (01.08.2005)
Published in The International journal of pressure vessels and piping (01.08.2005)
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Journal Article
Shielding Analyses for the Reactor Pressure Vessel of SMART-P
Kim, Kyo-Youn, Kim, Ha-Yong, Kim, Kang-Seog, Lee, Chung-Chan, Chang, Moon-Hee, Zee, Sung-Quun
Published in Journal of nuclear science and technology (01.03.2004)
Published in Journal of nuclear science and technology (01.03.2004)
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Journal Article
Evaluation of Vessel Fluence for SMART by DORT and MCNP Codes
Kim, Kyo-Youn, Kim, Ha-Yong, Zee, Sung-Quun, Chang, Moon-Hee
Published in Journal of nuclear science and technology (01.03.2000)
Published in Journal of nuclear science and technology (01.03.2000)
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Journal Article
Axial SPN and Radial MOC Coupled Whole Core Transport Calculation
CHO, Jin-Young, KIM, Kang-Seog, LEE, Chung-Chan, ZEE, Sung-Quun, JOO, Han-Gyu
Published in Journal of nuclear science and technology (01.09.2007)
Published in Journal of nuclear science and technology (01.09.2007)
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Journal Article
Development of a physics analysis procedure for the prismatic very high temperature gas-cooled reactors
Kim, Kang-Seog, Cho, Jin-Young, Lee, Hyun Chul, Noh, Jae Man, Zee, Sung Quun
Published in Annals of nuclear energy (01.11.2007)
Published in Annals of nuclear energy (01.11.2007)
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Journal Article
Trip setpoint analysis for the reactor protection system of an advanced integral reactor
Yang, Soo Hyung, Kim, Soo Hyung, Chung, Young Jong, Zee, Sung Quun
Published in Annals of nuclear energy (01.04.2007)
Published in Annals of nuclear energy (01.04.2007)
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Journal Article
Axial SP N and Radial MOC Coupled Whole Core Transport Calculation
CHO, Jin-Young, KIM, Kang-Seog, LEE, Chung-Chan, ZEE, Sung-Quun, JOO, Han-Gyu
Published in Journal of nuclear science and technology (01.09.2007)
Published in Journal of nuclear science and technology (01.09.2007)
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Journal Article
Performance evaluation of an advanced integral reactor against an anticipated transient without scram
Yang, Soo Hyung, Chung, Young Jong, Kim, Hee Cheol, Zee, Sung Quun
Published in Annals of nuclear energy (01.05.2006)
Published in Annals of nuclear energy (01.05.2006)
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Journal Article