Nuclear System Engineering
Prof. Hyun-Sik PARK (박현식, 朴炫植)
Office: Room. #311, 1st Building (A3), KAERI, Yuseong, Daejeon
Tel: +82-42-868-8615
2000 ~ present Senior/Principal Researcher, KAERI
2010 ~ present Professor, Nuclear System Engineering, UST
- Thermal-hydraulic integral effect tests and analysis for advanced reactors of SMART (small modular reactor) and APR1400 (large conventional reactor)
- Experiment and analysis on passive safety systems of PCCS (Passive Containment Cooling System), PRHRS (Passive Residual Heat Removal System), and PSIS (Passive Safety Injection System) including CMT (Core Makeup Tank) and SIT (Safety Injection Tank)
- Design, analysis, and validation of advanced nuclear system including SMRs (Small Modular Reactors) and its related passive safety systems and components such as helical coil SG and printed circuit SG
- Fundamental researches on thermal-hydraulics phenomena of Loss-of-Coolant Accident (LOCA), natural circulation, condensation and two-phase critical flow, etc.
1991 B.S. Nuclear Engineering, Seoul National University
1994 M.S. Nuclear Engineering, KAIST
1999 Ph.D. Nuclear Engineering, KAIST (Reactor Thermal-hydraulics, Advisor: Prof. H.C. NO)
1999.9 ~ 1999.12 Post-Doc, Thermal-Hydraulics Safety Research Division, KAERI
2005.2 ~ 2006.1 Visiting Assistant Professor, Nuclear Engineering, Purdue University
2019.7 ~ 2021.8 Head, Reactor System Safety Research Division, KAERI
(On-going)
SMART SDCA CPRSS Validation Tests for SMART SDCA, ‘19~23
Validation Plan for Elementary Technology Development of Innovative SMR, ‘21~23
Thermal-hydraulic Validation Tests for Multi-purpose SMR Development, ‘19~23
Development and Verification of Key Technologies for Safety Enhancement of an Advanced SMR, ‘23~24
(Completed)
Multi-field Integrated Safety Improvement and Development of High Fidelity Safety Analysis Technology (NRF), ‘20~21
Technology Validation on Passive Safety Features of an Integral-PWR type SMR (IAEA CPR I32010, No.21098), ‘18~21
Validation Tests for SMART Reactor System Development (NRF), ‘16~18
Validation Tests for SMART Passive Safety System (NRF), ‘12~15
Thermal-Hydraulic Experimental Test for SMART Technology Validation Project (SMART Consortium), ‘09~11
Google Scholar: https://scholar.google.com/citations?user=CbBMGDMAAAAJ&hl=ko
Technical Papers: Total 86 journal papers including 71 SCI papers and approximately 300 conference papers
Intellectual Properties: approximately 70 patents and programs
Technical Reports: approximately 180 technical reports
(International Journal) published during last 7 years
Hyun-Sik Park, Hwang Bae, Sung-Uk Ryu, Byong-Guk Jeon, Jin-Hwa Yang, Sung-Jae Yi, and Young-Jong Chung, "Thermal-Hydraulic Research Supporting the Development of SMART," Nuclear Technology, Vol.209, pp.1617-1635, 2023.
Byong-Guk Jeon, Hyun-Sik Park, et al., “Experimental and analytical investigation on SMART passive safety systems for three 2-inch SBLOCA tests using SMART-ITL," Annals of Nuclear Energy, Vol. 188, No.109835, 2023.
Jin-Hwa Yang, Tae-Hwan Ahn, Hwang Bae and Hyun-Sik Park, “Investigation of condensation with non-condensable gas in natural circulation loop for passive safety system," Nuclear Engineering and Technology, Vol. 55, pp. 1125-1139, 2023.
Seong Dae Park, Hyun-Sik Park, et al., “Numerical study on the thermal-hydraulic behavior in the ultimate heat sink of passive residual heat removal system in the SMART," Nuclear Engineering and Design, Vol. 399, No. 111997, 2022.
Min Gi Kim, Hyun-Sik Park, et al., “Development of a special thermal-hydraulic component model for the core makeup tank," Nuclear Engineering and Technology, Vol. 54, pp. 1890-1901, 2022.
Byong-Guk Jeon, Hyun-Sik Park, et al., “Investigation of two-phase natural circulation with the SMART-ITL facility for an integral type reactor," Nuclear Engineering and Technology, Vol. 54, pp. 826-833, 2022.
Hwang Bae, Hyun-Sik Park, et al., “Experimental investigation and validation of TASS/SMR-S code for single-phase and two-phase natural circulation tests with SMART-ITL facility," Nuclear Engineering and Technology, Nuclear Engineering and Technology, Vol. 54, pp. 554-564, 2022.
Hwang Bae, Hyun-Sik Park, et al., “Evaluation of thermal-hydraulic characteristics for reactor coolant system and helically coiled steam generator based on the performance tests with SMART-ITL," Nuclear Engineering and Design, Vol. 382, No.111392, 2021.
Jin-Hwa Yang, Hwang Bae, Sung-Uk Ryu, Byong-Guk Jeon, Sung-Jae Yi, and Hyun-Sik Park, “Comparison of Two Different Sized Small Break LOCAs on the Passive Safety Injection Line using SMART-ITL Data," Nuclear Technology, Vol. 206, 1421-1435, September 2020.
Eunkoo Yun, Byong-Guk Jeon, and Hyun-Sik Park*, “Experimental study on a single-phase natural circulation loop and its steady-state solution," Applied Thermal Engineering, Vol. 173, No.115190, 2020. (*corresponding)
Young-Jong Chung, Gyu-Hwan Bae, Byong-Guk Jeon, and Hyun-Sik Park, “Validation with the MARS and TASS/SMR codes based on experimental results of a pressurizer safety valve line break at the SMART-ITL facility," Annals of Nuclear Energy, Vol. 141, No.107344, 2020.
Yeon-Sik Kim, Hyun-Sik Park, et al., “Investigation of CMT Behavior between the ATLAS and SMART-ITL Tests," Annals of Nuclear Energy, Vol. 135, pp. 1-10, 2019.
Yeon-Sik Kim, Hyun-Sik Park, et al., “Overall thermal-hydraulic behavior in an SBO test using HSIT in the ATLAS facility," Annals of Nuclear Energy, Vol. 130, pp. 250-258, 2019.
46. Hwang Bae, Hyun-Sik Park, et al., “Core makeup tank injection characteristics during different test scenarios using SMART-ITL facility," Annals of Nuclear Energy, Vol. 126, pp. 10-19, 2019. (Review Paper)
Tram Thanh Tram, Byoung Jae Kim, Hyun-Sik Park, “Study on bubble and liquid velocities in an area-varying horizontal channel," Annals of Nuclear Energy, Vol. 118, pp. 170-177, 2018.
Yeon-Sik Kim, Hyun-Sik Park, et al., “Investigation of thermal hydraulic behavior of SBLOCA tests in SMART-ITL facility," Annals of Nuclear Energy, Vol. 113, pp. 25-36, 2018.
Hyun-Sik Park, Tae-Soon Kwon, Sang-Ki Moon, Seok Cho, Dong-Jin Euh, and Sung-Jae Yi, "Contribution of Thermal-Hydraulic Validation Tests to the Standard Design Approval of SMART," Nuclear Engineering and Technology, Vol.49, No.7, pp.1537-1546, 2017.
Hyun-Sik Park, Byong-Guk Jeon, Hwang Bae, Yong-Cheol Shin & Sung-Jae Yi, "An integral effect test of a complete loss of reactor coolant system flow rate for the SMART design using the VISTA-ITL facility and its simulation with the MARS-KS code," Journal of Nuclear Science and Technology, Vol.54, No.3, pp.348-355, 2017.
Eunkoo Yun, Hwang Bae, Sung-Uk Ryu, Sung-Jae Yi, and Hyun-Sik Park, “Design review and controllability assessment of the SMART-ITL secondary system for the SMART design with experimental investigation," Annals of Nuclear Energy, Vol. 109, pp. 538-547, 2017.
Hwang Bae, Hyun-Sik Park, et al., “Comparison of three SBLOCA tests with different break locations using the SMART-ITL facility to estimate the safety of the SMART design," Nuclear Engineering and Technology, Vol. 49, pp. 968-978, 2017.
Byong-Guk Jeon, Hyun-Sik Park, et al., “Code Validation on a Passive Safety System Test with the SMART-ITL Facility," Journal of Nuclear Science and Technology, Vol. 54, No.3, pp. 322-329, 2017.
Yeon-Sik Kim, Hyun-Sik Park, et al., “Reflux condensation behavior in SBLOCA tests of ATLAS facility," Annals of Nuclear Energy, Vol. 99, pp. 227-239, 2017.
(Patents) Selected among 70 items
Sung-Jae Yi, Hyun-Sik Park, et al., Natural Circulation Cooling System by Two-Step Heat Exchange, Korean Patent, Registration No. 10-2546736, 2023.
Sung-Jae Yi, Hyun-Sik Park, et al., Syphon System for Infinite Passive Cooling, Korean Patent, Registration No. 10-2574058, 2023.
Sung-Jae Yi, Hyun-Sik Park, et al., Porous Materialization and Screen Structure for Core Meltdown Material during Severe Accident, Chinese Patent, Registration No. 201910481303.2, 2023.
Hyun-Sik Park, et al., Two-phase Quality Sensor, Korean Patent, Registration No. 10-1767415, 2017.
(2022~present) Bureau member, Working Group on Analysis and Management of Accidents (WGAMA), Committee on the Safety of Nuclear Installations (CSNI), OECD/NEA
(2023~present) Korean representative, Expert Group on Small Modular Reactors (EGSMR), Committee on the Safety of Nuclear Installations (CSNI), OECD/NEA
Keynote Lecture (Thermal-Hydraulic Research Supporting the Development of SMART) @ NURETH-19 (2022), American Nuclear Society
Introduction to Advanced Nuclear Energy Systems (UST, 2011, 2012, 2015, 2018, 2022)
Introduction to Nuclear Thermal-hydraulics (UST, 2016)
Best Paper Award @ KNS (2011, 2012, 2014), Korean Nuclear Society
Academic Award @ KNS (2012), Korean Nuclear Society
Best Achievement @ National R&D (2016), Ministry of Science and Technology
Award Certificate for Nuclear Field Promotion (2016), Ministry of Science and Technology
Best Paper Award @ ATH-22 (2022), American Nuclear Society
Student
Alumni
– Tae-Woo Kim (Sep. 2020 ~ Aug. 2023, PhD Degree)
(Thesis title) Analyses of Thermal-Hydraulic Characteristics and Sodium-Water Reaction Resistance in the Printed-Circuit Steam Generator for Small Modular Reactors
(Present) Senior Researcher, KAERI
– Ki-Seok Han (Mar. 2017 ~ Feb. 2019, MS Degree)
(Thesis title) Experimental Study on Direct Contact Condensation Characteristics with 3D Bubble Reconstruction Method
(Present) Researcher, KRIBB
– Ji-Hwan Park (Mar. 2017 ~ Feb. 2019, MS Degree)
(Thesis title) Experimental and analytical study on single-phase natural circulation phenomenon in SMART
(Present) PhD candidate, Kyungpook National University
