Search Results - "Yun, Sunghwan"

P3‐147: Comparison to the rate of cognitive decline in early‐and late‐onset Alzheimer's disease by Yun, Sunghwan

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Comparison to the rate of cognitive decline in early-and late-onset Alzheimer's disease by Yun, Sunghwan

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Narrow passage assistant system for rear wheel steering semi-trailer truck by Junggun Yang, Sunghwan Yun, Kunsoo Huh

“…Semi-trailer trucks generate the articulation angle during turning situation due to structural characteristics. This angle can cause the trailer to deviate…”
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Acceleration of source convergence in Monte Carlo k-eigenvalue problems via anchoring with a p-CMFD deterministic method by Yun, Sunghwan, Cho, Nam Zin

“…The Monte Carlo method is widely used in neutron transport calculations, especially in complex geometry and continuous-energy problems. However, an extended…”
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A study on the radial expansion reactivity of a metal-fueled sodium-cooled fast reactor via a physics experiment by Yun, Sunghwan, Mikhailov, Gennadii, Kim, Sang Ji, Lim, Jae-Yong

“…•An experimental model of the radial expansion reactivity in a SFR was proposed.•The model reflects well the spectral component of the radial expansion…”
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An optimization study for shielding design of D-D and D-T neutron generators by Yun, Sunghwan, Lee, Cheol Woo, Lee, Dong Won, Kim, Sun-Ho, Jung, Bongki, Chang, Doo-Hee, Jin, Hyung Gon, Shin, Chang Wook

“…Neutron generators (NG) are being increasingly used in various industrial and research areas such as neutron activation analysis, neutron radiography, and…”
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Study on in-vessel shielding design concepts for small-size pool-type sodium-cooled fast reactors by Yun, Sunghwan, Kim, Sang Ji, Lim, Jae-Yong

“…•We study the in-vessel shielding design of sodium-cooled fast reactors (SFRs).•Axial-neutron-shielding plays an important role in the in-vessel shielding…”
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Status of HCCR TBM program for DEMO blanket by Cho, Seungyon, Ahn, Mu-Young, Chun, Young-Bum, Gwon, Hyoseong, Jin, Hyung Gon, Kim, Bum Seok, Kim, Chang-Shuk, Kim, Jong-Il, Kim, Suk-Kwon, Ku, Duck Young, Lee, Cheol Woo, Lee, Dong Won, Lee, Eo Hwak, Lee, Hyeong-Yeon, Lee, Youngmin, Park, Seong Dae, Park, Soon Chang, Park, Yi-Hyun, Shin, Chang Wook, Son, Seok-Kwon, Yoon, Jae Sung, Yun, Sunghwan

“…•The main functions and design concepts of the HCCR breeding blanket are to be verified in ITER through the HCCR Test Blanket Module (TBM) program.•R&D…”
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Validation of the axial expansion reactivity worth for a metal-fueled Sodium-cooled Fast Reactor via a physical experiment by Yun, Sunghwan, Mikhailov, Gennadii, Kim, Sang Ji, Lim, Jae-Yong

“…•In this paper, an experimental model of the fuel axial expansion reactivity in a metal-fueled SFR was proposed.•The suggested axial expansion model based on…”
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Validation of the MC2-3/TWODANT/DIF3D code system for control rod worth via BFS-75-1 and BFS-109-2A reactor physics experiments by Yun, Sunghwan, Lee, Min Jae, Kim, Sang Ji

“…•The MC2-3/TWODANT/DIF3D codes are validated using BFS-75-1/BFS-109-2A experiments.•The codes show excellent agreement with experiments in the reference…”
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Conceptual design and analysis of the HCCR breeder blanket for the K-DEMO by Yun, Sunghwan, Park, Seong Dae, Lee, Dong Won, Lee, Cheol Woo, Jin, Hyung Gon, Shin, Chang Wook, Kim, Suk-Kwon, Yoon, Jae Sung, Park, Yi-Hyun, Ahn, Mu-Young, Cho, Seungyon

“…•A conceptual HCCR breeder blanket design was suggested for 2200 MWf of the K-DEMO.•A graphite reflector resulted in 33 % reduction of the total Be multiplier…”
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Global depletion analysis of Korean helium cooled solid breeder TBM model for demo fusion reactor by Yun, Sunghwan, Cho, Nam Zin, Ahn, Mu-Young, Cho, Seungyon

“…The Korean HCSB (helium cooled solid breeder) TBM (test blanket module) is proposed with its specific compositions of lithium ceramic, beryllium and graphite…”
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Current status of design and analysis of Korean Helium-Cooled Solid Breeder Test Blanket Module by Cho, Seungyon, Ahn, Mu-Young, Kim, Duck Hoi, Lee, Eun-Seok, Yun, Sunghwan, Cho, Nam Zin, Jung, Ki Jung

“…It is known that the test of the capability of tritium self-sufficiency and the extraction of high-grade heat using tritium breeding blanket concepts is one of…”
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Depletion analysis of a solid-type blanket design for ITER by Yun, Sunghwan, Cho, Nam Zin, Ahn, Mu-Young, Cho, Seungyon

“…In the blanket design in a D-T fusion power plant, the majority of the fusion energy is obtained from neutron kinetic energy. The tritium for maintaining the…”
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Preliminary safety analysis of Korea Helium Cooled Solid Breeder Test Blanket Module by Ahn, Mu-Young, Cho, Seungyon, Kim, Duck Hoi, Lee, Eun-Seok, Kim, Hyung-Seok, Suh, Jae-Seung, Yun, Sunghwan, Cho, Nam Zin

“…ITER Test Blanket Module (TBM) which will be the act-alike module corresponding to DEMO blanket is aimed to verify the capability of tritium self-sufficiency…”
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