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Dive into the research topics where Chansun Shin is active.

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Featured researches published by Chansun Shin.


Journal of Electron Microscopy | 2010

Fabrication of a TEM sample of ion-irradiated material using focused ion beam microprocessing and low-energy Ar ion milling

Hyung-Ha Jin; Chansun Shin; Junhyun Kwon

Cross-section-view TEM samples of ion-irradiated material are successfully fabricated using a focused ion beam (FIB) system and low-energy Ar ion milling. Ga ion-induced damages in FIB processing are reduced remarkably by the means of low-energy Ar ion milling. There are optimized ion milling conditions for the reduction and removal of the secondary artifacts such as defects and ripples. Incident angles and accelerated voltages are especially more important factors on the preservation of a clean surface far from secondary defects and surface roughing due to Ga and Ar ion bombardment.


Nuclear Engineering and Technology | 2009

MULTISCALE MODELING OF RADIATION EFFECTS ON MATERIALS: PRESSURE VESSEL EMBRITTLEMENT

Junhyun Kwon; Gyeong-Geun Lee; Chansun Shin

Radiation effects on materials are inherently multiscale phenomena in view of the fact that various processes spanning a broad range of time and length scales are involved. A multiscale modeling approach to embrittlement of pressure vessel steels is presented here. The approach includes an investigation of the mechanisms of defect accumulation, microstructure evolution and the corresponding effects on mechanical properties. An understanding of these phenomena is required to predict the behavior of structural materials under irradiation. We used molecular dynamics (MD) simulations at an atomic scale to study the evolution of high-energy displacement cascade reactions. The MD simulations yield quantitative information on primary damage. Using a database of displacement cascades generated by the MD simulations, we can estimate the accumulation of defects over diffusional length and time scales by applying kinetic Monte Carlo simulations. The evolution of the local microstructure under irradiation is responsible for changes in the physical and mechanical properties of materials. Mechanical property changes in irradiated materials are modeled by dislocation dynamics simulations, which simulate a collective motion of dislocations that interact with the defects. In this paper, we present a multiscale modeling methodology that describes reactor pressure vessel embrittlement in a light water reactor environment.


Journal of Composite Materials | 2018

Microstructures and high-temperature tensile properties of mechanically alloyed and spark plasma-sintered 304SS-CNT composites:

Hyo-haeng Cho; Sangyeob Lim; Hyung-Ha Jin; Junhyun Kwon; Soon-Jik Hong; Chansun Shin

We fabricated and investigated a 304 stainless steel and carbon nanotube (304SS-CNT) composite with an aim to study its microstructures and high-temperature tensile properties. 304SS powders were mixed with carbon nanotubes using ball milling and consolidated using the spark plasma sintering technique. Tensile specimens made from the consolidated samples of 304SS-CNT were tested in a temperature range from 299 K (26℃) to 773 K (500℃). An induction coil was used for high-temperature tensile tests. The yield strength and the work hardening of the 304SS-CNT sample were found to be higher than those of a sample fabricated from 304SS without carbon nanotubes for all tested temperatures. Microstructure analysis carried out using optical microscopy, scanning electron microscopy, and transmission electron microscopy showed that the 304SS-CNT sample has a microstructure significantly different from the 304SS sample, e.g. reduced grain size and many small cuboidal particles. Composition analysis using energy-dispersive spectroscopy revealed that the cuboidal particles are chromium carbides, and the chromium content is reduced in the 304SS-CNT matrix. Retained carbon nanotubes could not be observed; it is thought that the carbon nanotubes may decompose, induce the reduced grain size and chromium carbides.


Journal of Nuclear Materials | 2014

Development and testing of microcompression for post irradiation characterization of ODS steels

Chansun Shin; Sangyeob Lim; Hyung-Ha Jin; P. Hosemann; Junhyun Kwon


Journal of the American Ceramic Society | 2012

Mechanical Properties and Deformation of Cubic Silicon Carbide Micropillars in Compression at Room Temperature

Chansun Shin; Hyung-Ha Jin; Weon-Ju Kim; Ji-Yeon Park


Journal of Nuclear Materials | 2009

Evaluation of the depth-dependent yield strength of a nanoindented ion-irradiated Fe–Cr model alloy by using a finite element modeling

Chansun Shin; Hyung-Ha Jin; Maan-Won Kim


Nuclear Instruments & Methods in Physics Research Section B-beam Interactions With Materials and Atoms | 2008

Irradiation induced dislocation loop and its influence on the hardening behavior of Fe–Cr alloys by an Fe ion irradiation

Hyung-Ha Jin; Chansun Shin; Do Hyun Kim; Kyu Hwan Oh; Jun Hyun Kwon


Materials Science and Engineering A-structural Materials Properties Microstructure and Processing | 2015

Specimen size effects on the weakening of a bulk metastable austenitic alloy

Chansun Shin; Sangyeob Lim; Hyung-Ha Jin; P. Hosemann; Junhyun Kwon


Materials Letters | 2012

Modified preparation technique of TEM sample for various TEM analyses of structural materials

Hyung-Ha Jin; Hae-Dong Cho; Sang-chul Kwon; Chansun Shin; Junhyun Kwon


Materials Science and Engineering A-structural Materials Properties Microstructure and Processing | 2016

Investigation of specimen size effects by in-situ microcompression of equal channel angular pressed copper

C. Howard; D. Frazer; A. Lupinacci; S. Parker; Ruslan Z. Valiev; Chansun Shin; B. William Choi; P. Hosemann

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Junhyun Kwon

Pennsylvania State University

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Junhyun Kwon

Pennsylvania State University

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P. Hosemann

University of California

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Kyu Hwan Oh

Seoul National University

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