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Radiological Assessment of Loss of Coolant Accident from Saeul Nuclear Power Plant KCI 등재 SCOPUS

Moses Oboo, Juyoul Kim

대한방사선방어학회 방사선방어학회지 Vol. 50 Special Issue (ISORD-11) 2025.05 pp.12-21

실험계획법을 이용한 원자력 발전소에서의 냉각제 상실사고에 대한 연구 KCI 등재후보

임영문, 이성모

대한안전경영과학회 대한안전경영과학회지 제7권 제4호 2005.10 pp.85-99

Overview of Critical Flow Test Program for the Simulation of Loss of Coolant Accident and Preliminary Analysis of Test Results

Park, C.K., Park, H.S., Yoon, Y.J., Song, C.H.

[Kisti 연계] 한국원자력학회 한국원자력학회 학술대회논문집 2005 pp.647-648

Impact of hydrogen on rupture behaviour of Zircaloy-4 nuclear fuel cladding during loss-of-coolant accident: a novel observation of failure at multiple locations

Suman, Siddharth

[Kisti 연계] 한국원자력학회 Nuclear Engineering and Technology Vol.53 No.2 2021 pp.474-483

Comparison of three small-break loss-of-coolant accident tests with different break locations using the system-integrated modular advanced reactor-integral test loop facility to estimate the safety of the smart design

Bae, Hwang, Kim, Dong Eok, Ryu, Sung-Uk, Yi, Sung-Jae, Park, Hyun-Sik

[Kisti 연계] 한국원자력학회 Nuclear Engineering and Technology Vol.49 No.5 2017 pp.968-978

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

[Kisti 연계] 한국원자력학회 한국원자력학회 학술대회논문집 2002 p.169

Effect of emergency core cooling system flow reduction on channel temperature during recirculation phase of large break loss-of-coolant accident at Wolsong unit 1

Yu, Seon Oh, Cho, Yong Jin, Kim, Sung Joong

[Kisti 연계] 한국원자력학회 Nuclear Engineering and Technology Vol.49 No.5 2017 pp.979-988

Loss of coolant accident analysis under restriction of reverse flow

Radaideh, Majdi I., Kozlowski, Tomasz, Farawila, Yousef M.

[Kisti 연계] 한국원자력학회 Nuclear Engineering and Technology Vol.51 No.6 2019 pp.1532-1539

Loss of Coolant Accident Analysis During Shutdown Operation of YGN Units 3/4

Bang, Young-Seok, Kim, Kap, Seul, Kwang-Won, Kim, Hho-Jung

[Kisti 연계] 한국원자력학회 Nuclear Engineering and Technology Vol.31 No.1 1999 pp.17-28

Scalability Analysis of Large Loss-of-Coolant-Accident at 8% Power Level for APR1400 and ATLAS

Hong, Soon-Joon, Lee, Byung-Chul, Lee, Hee-Do

[Kisti 연계] 한국원자력학회 한국원자력학회 학술대회논문집 2005 pp.448-449

Simulation of Containment Pressurization in a Large Break-Loss of Coolant Accident Using Single-Cell and Multicell Models and CONTAIN Code

Noori-Kalkhoran, Omid, Shirani, Amir Saied, Ahangari, Rohollah

[Kisti 연계] 한국원자력학회 Nuclear Engineering and Technology Vol.48 No.5 2016 pp.1140-1153

Evaluation of Analytically Scaled Model for Small Break Loss of Coolant Accident at Low Power

Song, Jin-Ho, Bae, Kyoo-Hwan

[Kisti 연계] 한국원자력학회 한국원자력학회 학술대회논문집 1999 p.177

Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor

Dehjourian, Mehdi, Sayareh, Reza, Rahgoshay, Mohammad, Jahanfarnia, Gholamreza, Shirani, Amir Saied

[Kisti 연계] 한국원자력학회 Nuclear Engineering and Technology Vol.48 No.5 2016 pp.1174-1183

Preliminary Best-estimate Analysis of APR1400 Large Loss-of-Coolant-Accident in 8% Power Level

Hong, Soon-Joon, Lee, Doo-Yong, Kim, Tae-Yoon, Lee, Hee-Do

[Kisti 연계] 한국원자력학회 한국원자력학회 학술대회논문집 2005 pp.1231-1232

Axial strength of Zircaloy-4 samples with reduced thickness after a simulated loss of coolant accident

Desquines, Jean, Taurines, Tatiana

[Kisti 연계] 한국원자력학회 Nuclear Engineering and Technology Vol.53 No.7 2021 pp.2295-2303

INTEGRAL BEHAVIOR OF THE ATLAS FACILITY FOR A 3-INCH SMALL BREAK LOSS OF COOLANT ACCIDENT

Choi, Ki-Yong, Park, Hyun-Sik, Cho, Seok, Euh, Dong-Jin, Kim, Yeon-Sik, Baek, Won-Pil

[Kisti 연계] 한국원자력학회 Nuclear Engineering and Technology Vol.40 No.3 2008 pp.199-212

3-Dimensional Analysis of the Steam-Hydrogen Behavior from a Small Break Loss of Coolant Accident in the APR1400 Containment

Kim Jongtae, Hong Seong-Wan, Kim Sang-Baik, Kim Hee-Dong, Lee Unjang, Royl P., Travis J. R.

[Kisti 연계] 한국원자력학회 Nuclear Engineering and Technology Vol.36 No.1 2004 pp.24-35

Prediction of ballooning and burst for nuclear fuel cladding with anisotropic creep modeling during Loss of Coolant Accident (LOCA)

Kim, Jinsu, Yoon, Jeong Whan, Kim, Hyochan, Lee, Sung-Uk

[Kisti 연계] 한국원자력학회 Nuclear Engineering and Technology Vol.53 No.10 2021 pp.3379-3397

FUEL BEHAVIOR UNDER LOSS-OF-COOLANT ACCIDENT SITUATIONS

CHUNG HEE M.

[Kisti 연계] 한국원자력학회 Nuclear Engineering and Technology Vol.37 No.4 2005 pp.327-362

Realistic Large Break Loss of Coolant Accident Mass and Energy Release and Containment Pressure and Temperature Analyses

Kwon, Young-Min, Song, Jin-Ho

[Kisti 연계] 한국원자력학회 Nuclear Engineering and Technology Vol.29 No.3 1997 pp.229-239