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4 results on '"Hyung Gon Jin"'

1. Hypervapotron Mockup Experiment and Analysis for Application into the Plasma Facing Components

Author

Hyung Gon Jin, Hyun Gon Lee, Seungyon Cho, Eo Hwak Lee, Jae Sung Yoon, Suk Kwon Kim, and Dong Won Lee

Subjects
Nuclear and High Energy Physics, Materials science, Heating system, Nuclear Energy and Engineering, Mockup, Mechanical Engineering, Nuclear engineering, General Materials Science, Plasma, Beam (structure), Ion source, Neutral beam injection, Civil and Structural Engineering
Abstract

A hypervapotron mockup was fabricated and used in the Neutral Beam Injection (NBI) heating system at KAERI. During the test, especially with the JAEA ion source, which has a focused beam and a long...

Published
2015
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2. Strength Evaluation of HAZ in Electron Beam Welded ARAA by Small Punch Test for HCCR TBM in ITER

Author

Eo Hwak Lee, Hyung Gon Jin, Jae Sung Yoon, Kyu In Shin, Suk-Kwon Kim, Seungyon Cho, and Dong Won Lee

Subjects
Nuclear and High Energy Physics, Materials science, Mechanical Engineering, Nuclear engineering, chemistry.chemical_element, Reflector (antenna), Welding, Blanket, 01 natural sciences, 010305 fluids & plasmas, law.invention, Nuclear Energy and Engineering, chemistry, law, Martensite, visual_art, 0103 physical sciences, Cathode ray, visual_art.visual_art_medium, General Materials Science, Ceramic, 010306 general physics, Helium, Civil and Structural Engineering
Abstract

The Korean helium cooled ceramic reflector (HCCR) test blanket module (TBM) has been developed for ITER, and Korean reduced activation ferritic martensitic (RAFM) steel, called advanced reduced act...

Published
2015
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3. Status and Plan of the System Codes Development for ITER Test Blanket Module and Fusion Breeding Blanket in Korea

Author

Dong Won Lee, Hyung Gon Jin, Moo Hwan Kim, Goon Cherl Park, Soo Been Yum, Seungyon Cho, Hee Cheon No, and Seol Ha Kim

Subjects
Nuclear and High Energy Physics, Fusion, Liquid metal, Computer science, 020209 energy, Mechanical Engineering, 3d analysis, Nuclear engineering, 02 engineering and technology, Plan (drawing), Blanket, 01 natural sciences, Extreme temperature, 010305 fluids & plasmas, Coolant, Nuclear Energy and Engineering, 0103 physical sciences, 0202 electrical engineering, electronic engineering, information engineering, Heat transfer model, General Materials Science, Civil and Structural Engineering
Abstract

The design scheme and system codes for fusion application have been developed for the ITER Test Blanket Module (TBM) program in Korea in parallel with the breeding blanket development, which were based on the developed system codes in Gen. IV reactor development projects such as MARS (Multi-dimensional Analysis of Reactor Safety) and GAMMA (GAs Multi-component Mixture Analysis). Considering the unique and common features with both the Fusion and Gen. IV reactors, four approaches have been carried out: (1) modifying the heat transfer model and suggesting a 3D analysis for considering the one-sided heating with extreme temperature differences, (2) implementing a tritium permeation model for a simulation of its behavior and amount simulation in a fusion coolant system, (3) developing a physical properties generation model for PbLi and Li considering the liquid metal breeders in these codes, and (4) implementing the magnetohydrodynamics (MHD) model by Miyazaki et.al. To integrate these separate codes ...

Published
2013
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4. Korean Development of Advanced Thermal-Hydraulic Codes for Water Reactors and HTGRs: Space and Gamma

Author

Hyung Gon Jin, Sang Jun Ha, Kyung Doo Kim, Eo Hwak Lee, Hong Sik Lim, and Hee Cheon No

Subjects
Nuclear and High Energy Physics, 010308 nuclear & particles physics, Computer science, Nuclear engineering, 0211 other engineering and technologies, 02 engineering and technology, Condensed Matter Physics, Space (mathematics), 01 natural sciences, Thermal hydraulics, Development (topology), Nuclear Energy and Engineering, Nuclear industry, 0103 physical sciences, Code (cryptography), 021108 energy
Abstract

The Korea nuclear industry has been developing the thermal-hydraulic system analysis Safety and Performance Analysis CodE (SPACE) and the GAs Multicomponent Mixture Analysis (GAMMA) code fo...

Published
2013
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