| 201903 | Acoustic analysis on the dynamic motion of vapor-liquid interface for the identification of boiling regime and critical heat flux | Seo, Seok Bin; Bang, In Cheol | ARTICLE | 39 |
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| 201812 | Effect of thermal activity on critical heat flux enhancement in downward-hemispherical surface using graphene oxide coating | Lee, Min Ho; Heo, Hyo; Bang, In Cheol | ARTICLE | 57 |
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| 201810 | Spent nuclear fuel with a hybrid heat pipe for electricity generation and thermal management | Kim, In Guk; Bang, In Cheol | ARTICLE | 16 |
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| 201807 | Natural convection heat transfer characteristics of molten salt with internal heat generation | Jeong, Yeong Shin; Seo, Seok Bin; Bang, In Cheol | ARTICLE | 206 |
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| 201806 | Study on flow characteristics of high-Pr heat transfer fluid near the wall in a rectangular natural circulation loop | Shin, Yukyung; Seo, Seok Bin; Bang, In Cheol | ARTICLE | 116 |
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| 201805 | Effects of hole patterns on surface temperature distributions in pool boiling | Seo, Han; Lim, Yeongjin; Shin, Heungjoo, et al | ARTICLE | 468 |
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| 201804 | Thermal-hydraulic phenomena inside hybrid heat pipe-control rod for passive heat removal | Kim, Kyung Mo; Bang, In Cheol | ARTICLE | 352 |
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| 201804 | Thermal-hydraulic analysis of a 7-pin sodium fast reactor fuel bundle with a new pattern of helical wire wrap spacer | Park, Seong Dae; Seo, Han; Jeong, Yeong Shin, et al | ARTICLE | 233 |
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| 201803 | Chromia coating with nanofluid deposition and sputtering for accident tolerance, CHF enhancement | Son, Gyu Min; Kim, Kyung Mo; Bang, In Cheol | ARTICLE | 227 |
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| 201801 | Analysis of hydrogen and dust explosion after vacuum vessel rupture: Preliminary safety analysis of Korean fusion demonstration reactor using MELCOR | Moon. Sung Bo; Lim, Soo Min; Bang, In Cheol | ARTICLE | 234 |
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| 201712 | Numerical analysis on spatial universality of similarity technique inside molten salt reactor system | Seo, Seok Bin; Shin, Yukyung; Bang, In Cheol | ARTICLE | 457 |
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| 201712 | Risk mitigation strategy by Passive IN-core Cooling system for advanced nuclear reactors | Seo, Seok Bin; Kim, In Guk; Kim, Kyung Mo, et al | ARTICLE | 283 |
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| 201710 | Flow visualization and heat transfer performance of annular thermosyphon heat pipe | Kim, In Guk; Kim, Kyung Mo; Jeong, Yeong Shin, et al | ARTICLE | 561 |
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| 201707 | Hydraulic control rod drive mechanism concept for passive in-core cooling system (PINCs) in fully passive advanced nuclear power plant | Kim, In Guk; Bang, In Cheol | ARTICLE | 305 |
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| 201702 | Risk-reduction of passive decay heat removal system by using gallium-water for UCFR and SMR | Seo, Seok Bin; Kim, In Guk; Bang, In Cheol | ARTICLE | 470 |
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| 201702 | Heat transfer characteristics and operation limit of pressurized hybrid heat pipe for small modular reactors | Kim, Kyung Mo; Bang, In Cheol | ARTICLE | 364 |
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| 201612 | Development of passive in-core cooling system for nuclear safety using hybrid heat pipe | Kim, Kyung Mo; Jeong, Yeong Shin; Kim, In Guk, et al | ARTICLE | 255 |
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| 201610 | Hydrodynamic cavitation characteristics of an orifice system and its effects on CRUD-like SiC deposition | Kim, Seong Man; Bang, In Cheol | ARTICLE | 582 |
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| 201609 | Visual Study of Ex-Pin Phenomena for SFR with Metal Fuel Under Initial Phase of Severe Accidents by using Simulants | Heo, Hyo; Park, Seong Dae; Jerng, Dong Wook, et al | ARTICLE | 384 |
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| 201608 | High performance all-carbon composite transparent electrodes containing uniform carbon nanotube networks | Yun, Hyung Duk; Kwak, Jinsung; Kim, Se-Yang, et al | ARTICLE | 772 |
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