ANSYS, Mechanical test, Fatigue, Fracture mechanics

Name - *

JOSH KYUIN SHIN

Phone: 703-***-**** *305 Cofer Rd., APT G

***********@*****.*** / *****@***.*** Richmond, VA 23224 https://www.linkedin.com/in/kyuin-shin-ph-d-07266680/ https://www.researchgate.net/profile/Kyu-In-Shin

EDUCATION

Virginia Commonwealth University Richmond, VA

Ph.D Student, Mechanical and Nuclear Engineering 08/2022 – Present Chungbuk National University Cheongju, Chungbuk, Korea Ph.D, Safety Engineering 03/1997 – 02/2003

Dissertation: “Fracture Mechanics Analysis of Tubes Damaged by Corrosion and Wear” Committee: ByoungGon Lee (Chair), JaeHak Park, KookSam Jung, KeeBong Yoon, DooHeon Kim

Chungbuk National University Cheongju, Chungbuk, Korea MS, Safety Engineering 03/1995 – 02/1997

Thesis: “Comparison of Elevated Temperature Fracture Toughness Behavior between New and Aged 1Cr-0.5Mo Steel Weldments”

Advisor: KeeBong Yoon and JaeHak Park

Chungbuk National University Cheongju, Chungbuk, Korea BS, Industrial Safety Engineering 03/1987 – 08/1994 Advisor: JaeHak Park

HONORS AND AWARDS

College of Engineering Graduate Assistantship 2022-2024 Virginia Commonwealth University

Paul & Helen Lenchuck Engineering Student Scholarship 2022 NCMA Foundation Board of Trustees has awarded

The Award of the Honor of the Researcher 2018

Marquis WHO’s WHO has awarded

The Award of the Excellent Journal Article 2014

Korea Nuclear Society has awarded

RESEARCH EXPERIENCE

VCU (Virginia Commonwealth University) Richmond, VA Position: Teaching and Research Assistant and PhD student 08/2022 – Present

Ph. D student with research activity related to the thermo-electrical device.

Assist Professors in keeping track of student’s attendance and assignments. Name - 2

NCMA (National Concrete Masonry Association) Sterling, VA Position: Lab Technician 12/2021 – 07/2022

Measure and test CMU (concrete masonry units), SRW (segmental Retaining wall), Pavers etc. according to ASTM-C standards.

SWISS Port IAD (International Airport of Dulles), VA Position: DG (dangerous goods) Specialist and Customer Agent 09/2020 – 12/2021

Checking the special measures and the handling of dangerous goods. VCU (Virginia Commonwealth University) Richmond, VA Position: Teaching and Research Assistant 08/2018 – 12/2019

Assisted Professors in keeping track of student’s attendance and assignments.

Perform FE analysis of the nanoindentation (ZrB2 ceramic, etc.).

K. Shin, S. Vargas-Giraldo, J. Rojas, C.E. Castano, “Advanced method to measure mechanical properties of zirconium diboride at different microscale depths from surface,” International Computing in the Atmospheric Sciences (iCAS) symposium, 2019.

DaVita Inc. Silver Spring, MD

Position: Specialized Bio-Med. Technician 11/2017 – 08/2018

Repair/maintenance of dialysis equipment and dialysis water treatment systems. CHSA (Corea Health & Safety Association) Seoul, Korea Position: Advisory Commissioner 02/2016 – 02/2017

Evaluation of wall thinning elbow for Structural integrity based on strength reduction factor in plastic instability analysis.

Ungburm Jang, Kyuin Shin, Sungho Lee, Changhee Kuan, “The Structure Integrity Assessment of the Wall Thinned Elbow Considering In/Out-Plane Bending,” Journal of the Korea Society of Disaster Information, Vol.12, No.1, pp. 01 – 09, 2016.

Safety investigation to identify and eliminate incidents/ hazards in Laboratory/ Industry. Jentech Technology Dejeon, Korea

Position: Senior Researcher (Team Manager) 08/2014 – 09/2015

Fracture toughness (JIC, J-R) analysis and Creep relaxation analysis, and compared with the experimental data in Gr91, Mod. Gr91, and

SUS 316L materials.

The CDR (concept design report) of HCCR

TBM (helium-cooled ceramic reflector test

blanket module) for ITER (international

thermo-nuclear experimental reactor) project

ITER Report, “HCCR-TBS Conceptual Design

Description,” QQ2R5R (2015).

Structure Integrity Assessment considering

Load Combination

ITER Report, “HCCR-TBS CD Structural Integrity Report,” QQLY7N (2015).

The Modal and Spectra Response Analysis for the Seismic Events

ITER Report, “HCCR TBS CD Seismic Analysis Report for TBM-set,” QQFTHR (2015).

Material Specification:

ITER Report, “HCCR-TBS Material Data Summary for the Design and Analysis of CDR,” QABFQ5 (2015).

Electromagnetic Stress Analysis

KAERI (Korea Atomic Energy Research Institute) Dejeon, Korea Name - 3

Position: Post-Doc Fellow 04/2012 – 04/2014

The structure design of a Korean HCCR TBM component based on ASME Sec. III, RCC- MR(x)

Kyu In Shin, Dong Won Lee, “First Wall Design of ITER Test Blanket Module (TBM) based on RCC-MR Code,” Journal of the Korean Society of Safety 27(6), 2012.

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

“Structural Components Design and Analysis of Side Wall in a Korean HCCR TBM for ITER,” Fusion Engineering and Design, 89, 1068-1073, 2014.

Kyu In Shin, Dong Won Lee, Eo Hwak Lee, Suk-Kwon Kim, Jae Sung Yoon, Seungyon Cho, “Design and performance analysis of structural components for a Korean He Cooled Ceramic Reflector TBM in ITER,” Fusion Engineering and Design, 88, 1866-1871, 2013.

Thermal-structural contact analysis between sub- modules in TBM

Kyu In Shin, Dong Won Lee, Hyung Gon Jin, Eo Hwak Lee, Suk-Kwon Kim, Jae Sung Yoon, Mu-Young Ahn and Seungyon Cho, “Contact Stress Evaluation Based on Thermal-Structural Analysis in KO HCCR TBM Sub-Modules for ITER,” IEEE Transactions on Plasma Science, 42(6), 1807-1810, 2014.

Strength Evaluation of HAZ in TIG (tungsten inlet arc) and EB (electron beam) welded material at room and high (550

o

C) temperatures for

weld fabrication

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

“Strength Evaluation of a Single Layer Passed TIG Weld Joint in ARAA (Korean RAFM Steel) by Small Punch Test for HCCR TBM in ITER,” Fusion Science and Technology, 66, 200-207, 2014.

Documentation of QA (quality assurance) for Weld fabrication (EB and TIG weld) from Standard Weld test procedure, and Establishment of PWHT (post weld heat treatment) condition based on ASME Sec. III, RCC-MR(x), and ISO. EN.

High Heat Load Fatigue Analysis of Be/Cu/SS

Mock-Ups for ITER Blanket First Wall

KAERI Technical Report, “High Heat Load Fatigue Analysis of Be/Cu/SS Mock-Ups for ITER Blanket Module,” 2012.

Fatigue life assessment of the neutral beam system Korea University

Seoul, Korea

Position: Research Professor 10/2008 – 03/2011

Burst pressure analysis for a tube with L- and U-type combination through-wall cracks.

Kyu In Shin, Kee Bong Yoon, and Jai Hak Park, “Experimental and numerical study on the burst pressure of steam generator tubes with L- and U-type through-wall combination cracks,” Journal of Mechanical Science and Technology, 27 (8) 1-6, 2013.

Limit load analysis for the forged T-pipe.

Evaluation of the allowable local thickness of pipes based on ASME/ANSI B31.1, and ASME Code Case N-597

FE analysis of Hyper & Reactor section pipe considering a flange and a cone-ring based on ASME Sec. VIII and Hitachi requirement codes.

Name - 4

Energy Safety Research Institute, Chung-Ang University Seoul, Korea Position: Post-Doc Fellow 03/2008 – 09/2008

Evaluation of thermal stress, and 2

nd

creep analysis considered the operating history (time vs. pressure and time vs. temperature) in boiler header.

Kyu In Shin, Kee Bong Yoon, “Thermal Stress Evaluation by Elastic-Creep Analysis during Start-up of Boiler Header,” 2008.

Tohoku University Sendai, Japan

Position: Post-Doc Fellow 03/2007 – 02/2008

Development and Evaluation of DCPD (direct current potential drop) method with adjustable four-point probes in NDE

Chung-Ang University Seoul, Korea

Position: Post-Doc Fellow 11/2004 – 03/2007

Fracture mechanical analysis from a Hydrogen attacked carbon steel pipe (ASTM A53B steel)

Joon-Won Lee, Maan-Won Kim, Kyu-In Shin, Jai-Hak Park, “Analysis Strength Characteristics Using Small Punch Test for A53B Carbon Steel Pipes Damaged by

High Temperature Hydrogen Attack, Journal of the

Korean Society of Mechanical Engineering, KSME

08MF075 01/2008

FFS (fitness-for-service) evaluation for Pressure Vessel & Pipe System according to API 579.

Limit load, and Creep analysis for the remaining life assessment of a weld region in Y-pipe

Kyu In Shin, and Kee Bong Yoon, “3-Dimentional Stress Analysis for Creep Life Assessment of Y-Piece under Inner Pressure and Bending System Load, Journal of the Korean Society of Safety, pp. 502-507, 2008.

Local Creep Rupture analysis for T-pipe using ABAQUS.

Kyu In Shin, Yun Jae Kim, and Kee Bong Yoon, “Reference Stress Based Stress Analysis for Local Creep Rupture of a T-pipe,” Journal of the Korean Society of Mechanical Engineering, Vol. 30, No. 8, 2006.

Plastic collapse analysis in elbows with the various shapes of wall thinning area based on ASME XI, ASME Code Case N-597, and ANSI/ASME B31.1 code in NPP.

Kyu In Shin, Sung Ho Lee, and Kee Bong Yoon, “Evaluation of Plastic Collapse Bending Load of Elbows with Thinning Area of Various Shapes,” Journal of the Korean Society of Safety, Vol. 23, No. 3, pp. 17-24, 2008.

Kyu In Shin and Kee Bong Yoon, “A Study on Failure Mode of Pipe Elbows with Wall Thinning,” Journal of the Korean Institute of Gas, Vol. 12, No. 2, pp. 57-62, 2008

Burst pressure analysis for SG (steam

generator) tube with T-type combination

through-wall cracks in NPP.

Kyu In Shin, Jai Hak Park and Kee Bong Yoon,

“Experimental and Analytical Study on the Burst

Pressure of Steam Generator Tubes with T-type

Combination Cracks,” Journal of the Korean

Society of Safety, Vol. 20, No. 2, pp. 38-43, 2005 KINS (Korea Institute of Nuclear Safety) Daejeon, Korea Position: Post-Doc Fellow 03/2003 – 10/2004

Structure integrity assessment of the inclined defected SG (steam generator) tube caused by fretting-wear damage in NPP.

Name - 5

Kyu In Shin, Jai Hak Park, Myung Jo Jhung, Young Hwan Choi, “The Burst Pressure Analysis of Steam Generator Tubes with Inclined Type of Wear Damage,” Journal of the Korean Society of Safety, Vol. 19, No. 2, pp. 11-15, 2004.

Accident cause analysis from SGTR (steam generator tube rupture) in NPP

Unified terminology of SGTR based on NUREG guide, the viewpoints of leakage, defect, and operator.

Chungbuk National University Cheongju, Chungbuk, Korea Position: PhD Student 03/1997 – 02/2004

FE (finite element) simulation of SCCG (stress corrosion crack growth) in steam generator tube

Kyu-In Shin, Jai Hak Park, Hong-Deok Kim and Han-Sub Chung, “Simulation of Stress Corrosion Crack Growth in Steam Generator Tubes,” Nuclear Engineering and Design, Vol. 214, pp. 91-101, 2002.

Evaluation of before/after shot peening effects steam generator tube based on stress intensity factor (KI)

Kyu In Shin, Jai Hak Park, Myung Jo Jhung, and Young Hwan Choi, “Fracture Mechanics Analysis of Steam Generator Tubes after Shot Peening,” Journal of the Korean Society of Mechanical Engineering, Vol. 28, No. 6, pp. 732-738, 2004.

Plastic instability analysis in flat or circumferential type of defected steam generator tube.

Kyu In Shin and Jai Hak Park, “Analysis of Burst Pressure of Damaged Tubes Using Plastic Instability Analysis,” Solid State Phenomena, Vol. 120, pp. 187-192, 2007.

Kyu In Shin and Jai Hak Park, “Analysis of Burst Pressure for Wear- Damaged Steam Generator Tubes,” Journal of the Korean Society of Safety, Vol. 18, No. 4, pp. 16-22, 2003.

Air plasma cutting surface evaluation, and fracture toughness (KIC) behavior of welded materials from Air plasma cutting.

Kyu In Shin, Hyung Gin Kim, Jai Hak Park, Sung Chung Kim,

“Mechanical Properties of Welded Materials after Plasma Cutting,” Korean Society of Precision Engineering, Vol. 16, No. 9, p. 68-74, 1999.

Kyu In Shin, Hyung Gin Kim, Jai Hak Park, Sung Chung Kim,

“Characteristics of Plasma Cut Surface,” Korean Society of Precision Engineering, pp. 1052-1066, 1999.

Construction of 2

nd

Pipe Safety Management System based

on P&IDs and ISO drawing

KEPRI Report, “Management Program for Thinned Pipe in NPP Secondary System,” KEPRI TM.00NJ12.M2001.189, 2001.

Evaluation of residual strength in MSD (multi-site damage) cracks

Structural Integrity Assessment of KS D 3507 and KS D 3631 welded carbon steel pipes KRISS (Korea Research Institute of Standard and Science) Daejeon, Korea Position: Master Course Research student 09/1994 – 12/1996

Mechanical properties test, Fracture toughness (KIC, JIC, and J-R curve) experiment, Creep rupture test, Fatigue test, Charpy impact test, and so on.

Material degradation evaluation using replica method with Optical metallography and SEM. Name - 6

Kyu In Shin, Jai-Hak Park, Kee Bong Yoon, and Hee Moo Lee,

“A Study on Elevated Temperature Fracture Behavior of Cracks in 1Ce-0.5Mo Steel Weld,” Journal of the Korean Society of Safety, Vol. 12, No. 2, p. 45-56, 1997

Performed Creep-Crack-Growth rates Experiment of 1Cr-0.5Mo steels at high temperature.

KRISS Report “Development of a General Model for Prediction Crack Growth Rates at High-Temperature (2nd year),” 1995 LECTURES

Korea University of Technology and Education Aug. 2016 – Dec. 2016

Safety in Gas Facilities, undergraduate course averaging 15 students per semester. Han Sung University Mar. 2009 – Aug. 2009

Materials Science and Engineering, undergraduate course averaging 70 students per semester.

Chung-Ang University Mar. 2006 – Aug. 2006

Fundamentals in Modern Science and Technology, undergraduate course averaging 60 students per semester.

Korea Polytechnic IV Colleges Mar. 2000 – Dec. 2000

Mechanics of Materials, and Introduction of Computation, undergraduate course averaging 40 students per semester.

LANGUAGES

English: Advanced Reading and Writing, Advanced Listener, Advanced Speaker Korean: Native Language

REFERENCES

Ph.D Karla M. Mossi, Associate Professor/ Graduate Program Director Mechanical and Nuclear Engineering, Virginia Commonwealth University Phone: +1-804-***-****

Email: *******@***.***

Ph.D Carlos Castano, Associate Professor

Mechanical and Nuclear Engineering, Virginia Commonwealth University Phone: +1-804-***-****

Email: *************@***.***

Ph.D Jai Hak Park, Professor

Dept. of Safety Engineering, Chungbuk National University, Korea Phone: +82-43-261-****

Email: ******@********.**.**

Ph.D Dong Won Lee, Principal Researcher / Division Director Korea Atomic Energy Research Institute (KAERI)

Phone: +82-42-868-****

Email: *****@*****.**.**

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