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Chan-Young Paik
Chan-Young Paik
Nuclear engineering
Structural engineering
Engineering
Accident management
Boiler (power generation)
4
Papers
7
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0
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Effects of ATF cladding properties on PWR responses to an SBO accident: A sensitivity analysis
2022
Annals of Nuclear Energy
Ali Alraisi
Yongsun Yi
Suwon Lee
Saeed A. Alameri
Maryam Qasem
Chan-Young Paik
Changheui Jang
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Best-estimate severe accident and source term analysis for an ISLOCA scenario of a CANDU-6 plant using the MAAP-ISAAC code
2020
Nuclear Engineering and Design
Dong Sik Jin
Sook-Kwan Kim
Sang-Koo Han
Chul-Kyu Lim
Bong Jin Ko
Yong Ho Hong
Kwang-Il Ahn
Soo Yong Park
Seok Won Hwang
Paul McMinn
Chan-Young Paik
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Best-estimate analysis for a MSGTR accident of CANDU-6 plants using the MAAP-ISAAC code
2020
Nuclear Engineering and Design
Chul-Kyu Lim
Sang-Koo Han
Sook-Kwan Kim
Dong Sik Jin
Bong Jin Ko
Yong Ho Hong
Kwang-Il Ahn
Soo Yong Park
Seok Won Hwang
Paul McMinn
Chan-Young Paik
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Improvement of local air coolers model in ISAAC
2004
See Darl Kim
Dong Ha Kim
Soo Yong Park
Chan-Young Paik
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