Small But Strong Outstanding University

Professor’s Profile

Namgung, Ihn

  • Major : Mechanical Engineering
  • Professor Professor
  • Office : Room 413, Main Bldg
  • Phone : +82-52-712-7314
  • Email : inamgung@kings.ac.kr

Educational Background

Ph.D., Mechanical Engineering, Univ. of Florida(1989.12)
M.S., Mechanical Engineering, Ajou Univ.(1983.2)
B.S., Mechanical Engineering, Ajou Univ.(1981.2)

Professional Experience

Professor, KINGS (2012.3~current)
Former Dean of Academic Affairs (2019.4~2020.1)
Former Head of Dept. of NPP Eng.(2013.7~2015.2)
Member, Ulsan City 3D printing promotion and development committee (2021.2-current)
Member, Member Ulsan Information Industry Promotion Agency 3D Printing Forum (2019.12.18-current)
Member, Member Ulsan Technopark 3D printing center - management committee (2019.11.27-current)
Member, Saeul Regional Nuclear Safety Council (2013.11-2019.11)
Director, Research Center TUV Korea (2009.1-2011.8)
Director, Daejon Intelligent Robot Center (Taejeon Techno Park) (2003.1-2008.12)
Team Leader, KEPCO E&C (1997.1-2002.12) (due to government reorganization of KAERI)
Senior Researcher, KAERI (1990.6-1996.12) (senior researcher)

Research

3D Design and Virtual Reality Simulation of Nuclear Mechanical System

• Developed PWR600 reactor system conceptual design for smaller power requirement of developing nations that included
  - PWR600 sub-system such as reactor and reactor internals 3D model that can be viewed and inspected by user in virtual environment and produced realistic animations
  - Other PWR600 sub-system and components that are developed for 3D models includes Fuel Assembly,
  - Steam Generator, CEDM (Control Element Drive Mechanism) and Reactor Coolant System virtual reality model for emmersive experience of the system
• Research interest includes
  - Advanced reactor design for higher seismic capability and
  - Innovative CEDM design than current design for lighter weight,
  - Improved reactor internals configuration change for greater severe accident margin,
  - 3D virtual model of any mechanical system including NPP system using CATIA and Composer that user can control view and manipulate easily for emmersive experience, etc.

 

 

[Research Samples]
PWR600 RCS 3D Model - picture  ☞
PWR600 Reactor Assembly - animation  ☞
Reactor Vessel Virtual Reality Model - picture  ☞
PWR600 RCS - animation  ☞
Fuel Rod Assembly - animation  ☞
Fuel Assembly - video  ☞
RV bottom head inspection - method-1 - video  ☞
RV bottom head inspection - method-2 - video  ☞
CEDM model - 3D VR simulation - animation  ☞
CEA Withdrawal - CEA Drive Motor Assmebly 3D VR simulation - animation  ☞
CEA Insertion - CEA Drive Motor Assmebly 3D VR simulation - animation  ☞

Advanced Physic Simulation of Nuclear Mechanical System

• Developed 3D FEM model of reactor, nuclear fuel, and other major equipment for system integrity assessments that includes
  - Reduced 3D fuel assembly dynamic model development based on shell and beam elements
  - CEDM nozzle welding residual stress analysis,
  - CEA drop CFD analysis,
  - Steam Generator tube-sheet optimization analysis,
  - Fuel Assembly 3D dynamic modelling and modal analysis,
  - Severe accident analysis of reactor core, etc.
• Research interests include
  - Most up-to-date analysis software and computer technology for physics based analysis
  - Develop 3D reduced core and RCS dynamic model
  - Advanced simulation and optimization of associated design innovation such as CEDM and internals, and SMR, etc.

 

 

[Research Samples]
RV severe accident simulation - temperature profile of RV bottom head - video  ☞
RV severe accident simulation - creep deformation of RV bottom head - figure  ☞
CEDM J weld thermal analysis - video  ☞
CEDM J weld thermal- stress analysis - video  ☞
Nuclear Fuel Pellet and Clad temperature distribution for normal condition - simulation figure  ☞
Nuclear Fuel Assembly - reduced model  ☞
Modal Analysis of Fuel Assembly - animation  ☞
RV and Support Column Support 3D mesh plot - Figure  ☞
Modal Analysis of Reactor Vessel and Column Support - animation  ☞
CEDM Withdrawal - Rigid Body Dynamic Simulation - animation  ☞

Application of 3D Printing to NPP Components

• Application of 3D printing in education
  - Modeling and fabrication of scale model of reactor vessel, closure head, lower internals, upper internals, main pipes, steam generators, and SG internals using 3D printing
  - Modeling and fabrication of scale model of fuel assembly components, fuel rod
• External research project on metal 3D printing technology to develop nuclear components.
  - 3D printing development of flow control valve cage of coolant make up pump of NPP (from Ulsan TechnoPark) - currently on-going research
  - 3D printing of impeller of flow control valve of obsolete valve of NPP (from KHNP)
  - Fabrication of flow control valve body and qualification of obsolete valve in connection with KHNP project (from Ulsan city) - currently on-going research
• Research interests include
  - Development of monitoring system for metal 3D printing
  - Development of AI control algorithm for metal 3D printing
  - Development of metal power inspection system using vision and AI
  - Development of HIP (Hot Isostatic Pressing) equipment for metal 3D printer

 

 

[Research Samples]
3D printing of PWR600 RCS system reduced model overview  ☞
3D printing of PWR600 Reactor Assembly - reduced model  ☞
3D printing of PWR600 Steam Generator reduced model  ☞
3D printing of Nuclear Fuel Assembly  ☞
3D printing of Flow Control Valve Cage  ☞
3D printing of Condensor Travel Screen Pump Impeller - Protptype model  ☞
3D printing of Condensor Travel Screen Pump Impeller - 3D printing simulation (pdf)  ☞
3D printing of Condensor Travel Screen Pump Impeller - 3D printing simulation (video)  ☞

Lab Members

- AIM Lab Members ☞

- Alumni ☞

 

Lab Name : AIM Lab

AIM* is derived from Advanced simulation and Innovative design in Mechanical Eng.

       and also simultaneously stands for

       Additive-manufacturing Innovation in Metal 3D printing technology,

       Artificial Intelligence in Mechanical Eng., indicating the research direction of the lab.

 

AIM Lab Members

 

AIM Lab Members

 

 

Alumni 

Radioactive Waste and Spent Fuel Management

Introduction To the Courses

Courses

Engineering Fundamentals 
3D Design and Virtual Reality Simulation   
Advanced Physics Simulation of Nuclear Mechanical System
Application of 3D Printing to NPP Component Design and Production

 

Engineering Fundamentals

Course Overview

- This courses are intended to give student reviewing of undergraduate contents of advanced mathematics. as well as solid mechanics that were taught by prof. Ihn Namgung.
- The courses review following undergraduate subjects
   · Advanced Mathematics (Advanced Calculus, Linear Algebra, Numerical Analysis)
   · Solid Mechanics

 

Course Objective

- Give students who want to study in the fields of nuclear mechanical engineering or civil engineering area an opportunity to review fundamental subjects of these area.
- Prepare students to go on a study of the graduate level of advanced subject.

 

Students Outcomes

- Examination (mid and final)
- Recall of undergraduate fundamentals of engineering (mathematics and solid mechanics)

 

 

3D Design and Virtual Reality Simulation

Course Overview

- This courses are intended to teach student to be able to create mechanical parts, assembly and system from ideal to visualization.
- The topics treated in these course are toward nuclear reactor and primary loop of nuclear power plant, however, the skills learn from this course can be applied to create  other mechanical components or system.
- The courses that are offered in the past and presents include
   · PWR Reactor Design with Virtual Reality Simulation
   · Nuclear Reactor 3D Virtual Design and Simulation
   · Code and Standard with Applications to RV design and analysis
   · Fuel Structural Analysis and Core 3D Modeling
   · CEDM System Design and Analysis
   · APR1400 Steam Generator Conceptual Design
   · PWR 600 Reactor Internals Mechanical Design
   · Introduction to 3D CAD and FEM Analysis

 

Course Objective

- Teach students skills to create and generate from idea to visual objects using 3D CAD software (CATIA v5).
- Teach students skills to create and manipulate 3D design into animation and publishing artwork.
- Teach students fundamentals of reactor coolant pressure boundary design process according to ASME code.
- Teach students skills that are necessary for the 2nd year Project Courses.

 

Students Outcomes

- Term Projects
- Skillful use of 3D design software (CATIA)
- Skillful use of 3D animation software (Composer)

 

 

Advanced Physics Simulation of Nuclear Mechanical System

Course Overview

- This courses are intended to teach student to be able to assess and analyze soundness of reactor coolant pressure boundary components and systems.
- The courses teach the theory of pressure vessel, fundamentals of structural analysis, fracture mechanics and ASME codes.
- The courses are designed to give students hands-on-practice of analysis using ANSYS general purpose FEM analysis software. The course covers FEM modeling technique, structural analysis, dynamic analysis, thermal analysis, CFD analysis, rigid dynamic analysis as well as 3D printing simulation.
- Some of the courses offered in the past and presents include
   · Design and Analysis of Pressure Vessels,
   · Reactor Mechanical System Analysis
   · Introduction to 3D CAD and FEM Analysis
   · Design and Analysis of Nuclear Piping
   · Severe Accident Modeling and Analysis of Reactor Structure
   · Fatigue and Fracture Mechanics of Nuclear Mechanical System
   · Fuel Seismic Analysis Modeling and Analysis
   · Fuel Structural Analysis and Core 3D Modeling

 

Course Objective

- Teach students theory related to the fundamentals of reactor coolant pressure boundary such as theory of pressure vessel, theory of fracture mechanics and ASME codes
- Teach students skills to be able to develop FEM model of mechanical component and systems and carry out structural analysis, thermal analysis, and other associated analysis.
- Teach students knowledge on analysis methodology of ASME code that are required by regulatory body.
- Teach students skills that are necessary for the 2nd year Project Courses.

 

Students Outcomes

- Term Projects
- Ability to develop FEM model of given component or system
- Ability to properly set boundary condition and external loadings to the model.
- Ability to digest analysis results

 

 

Application of 3D Printing to NPP Component Design and Production

Course Overview

- This courses are intended to teach student 3D printing technology.
- The courses teach 3D design for additive manufacturing.
- The courses are designed to give students hands-on-practice of 3D design of reactor components and 3D printing simulation using CATIA and ANSYS. 3D printing simulation requires completely different approach than usual structural analysis due to tight coupling of heat tansfer and thermal contraction in the process.
- Some of the courses offered in the past and present include
   · 3D Printing Technology
   · 3D Printing Simulation and Prototyping of Nuclear Components
   · CEDM System Design and Analysis
   · APR1400 Steam Generator Conceptual Design
   · PWR Reactor Design with Virtual Reality Simulation
   · PWR RCS Design with Virtual Reality Simulation

 

Course Objective

- Teach students skills to do 3D design of reactor components or system and create stl file, then check defact of stl file.
- Teach students skills to to develop 3D printing simulation model of the design in ANSYS Additive Suite.
- Teach students knowledge on design compensation of design that minimize thermal distorsion.
- Teach students how to use 3D printing machin (educational 3D printer).

 

Students Outcomes

- Term Projects.
- 3D printing product of the projects.
- Ability to develop 3D model of given component or system for 3D printing.
- Ability to properly carry out 3D printing simulation and design compensation.
- Ability to produce 3D printing part of the design.

 

-

Publications, Projects and Awards

Categories

- Journal Publications
- Conference Publications
- Books
- Workbook
- Patents

 

Journal Publications

 

[23]Wycliffe Kiprotich KIPTISIA, Ihn Namgung, "Analysis of residual stresses on the expansion transition zone of steam generator tubes of APR1400", Journal of Pressure Vessel Technology, (ASME), 2019, Nov.1 (on-line), https://asmedigitalcollection.asme.org/pressurevesseltech/article-abstract/doi/10.1115/1.4045392/1067336/Analysis-of-Residual-Stresses-On-the-Expanding?redirectedFrom=fulltext

 

[22]Collins Juma, Ihn Namgung, "FEM Estimation and Comparison of Material Properties of Thin Spherical Perforated Plate and Thin Perforated Flat Plate", Int. J. Eng. Research and Tech., Volume 12, Number 9 (2019), pp. 1533-1540.

 

[21]Francis Chanzu Kevore, Ihn Namgung, "ASME Code Stress Evaluation of Manway Nozzle for PWR Steam Generator", Int. J. Eng. Research and Tech., Volume 12, Number 9 (2019), pp. 1556-1561.

 

[20]Mai Quy Sang, Ihn Namgung, "Steam Generator Overall Heat Transfer Area Estimation for PWR NPP", Int. J. Eng. Research and Tech., Volume 12, Number 9 (2019), pp. 1601-1609.

 

[19]Joswhite Ondabu Maragia, Ihn Namgung, "Assessments and Comparisons of PWR Reactor PT Limits per Deterministic and Risk Informed by ASME Code Rules", Int. J. Eng. Research and Tech., Volume 12, Number 9 (2019), pp. 1468-1478.

 

[18]Joswhite Ondabu Maragia, Ihn Namgung, "Comparative Study of P-T Limit Curves between 1998 ASME and 2017 ASME Code Applied to Typical OPR1000 Reactors", Transactions of KPVP, Vol.15 , No.02, pp1-8, (2019.12) 2017 ASME Code Applied to Typical OPR1000 Reactors

 

[17]Collins JUMA, Ihn NAMGUNG, "Assessment of Equivalent Elastic Modulus of Perforated Spherical Plates", Transactions of KPVP, Vol.15, No.01, (2019.6)

 

[16]Wycliffe Kiprotich KIPTISIA, Ihn NAMGUNG, "Evaluation of APR1400 SG Tube to Tube-sheet Joints Residual Stresses", Transactions of KPVP, Vol.14, No.02, (2018.12)

 

[15]Fahmi Alfa Muslimu, Ihn Namgung, "CFD Modelling and Analysis of CEDM CEA SCRAM Drop Simulation", Transactions of KPVP, Vol.14 , No.02, (2018.12)

 

[14]Mutegi Peter Mutembei, Ihn Namgung, "Design Verification of APR1400 Reactor Vessel Through Re-engineering Approach", Journal of KOSSE. Vol. 13, No. 1 pp. 15-23. (2017. 6)

 

[13]Nguyen Anh Tung, Ihn Namgung, "Design Re-engineering of the Lower Support Structure of the APR1400 Reactor Internals", Journal of KOSSE., Vol. 13, No. 1 pp. 25-31., (2017. 6)

 

[12]Sang-Jun Park, Mutegi Peter Mutembei, Ihn Namgung, "Systems Engineering Approach to the Heat Transfer Analysis of PLUS 7 Fuel Rod Using ANSYS FEM Code", Journal of KOSSE. Vol. 13, No. 1 pp. 33-39., (2017. 6)

 

[11]Khaled Atya Ahmed Abdallah, Ihn Namgung, "Virtual reality development and simulation of BMI nozzle inspection system for use during regular refueling outage of APR1400 family of reactors", Annals of Nuclear Energy, Vol. 116, pp.235–256., (2018)

 

[10]Anh Tung Nguyen, IhnNamgung, "INVESTIGATION OF APR1400 REACTOR VESSEL SUPPORT", Int. J. Engineering and Innovative Tech., Vol 6, Issue 4, Oct. (2016)

 

[9]Anh Tung Nguyen, Ihn Namgung, "Structural assessments of plate type support system for APR1400 reactor", Nuclear Engineering and Design, Vol. 314, pp.256-270, (2017)

 

[8]Ihn Namgung, Nguyen Hoang Giang, "Investigation of Burst Pressures in PWR Primary Pressure Boundary Components", Nuclear Engineering and Technology, Vol.48, pp.236~245, (2016)

 

[7]Hyo-Nam Kim, Ihn Namgung, "Two-Dimensional Axisymmetric Thermostructural Analysis of APR1400 Reactor Vessel Lower Head for Full-Core Meltdown Accident", Nuclear Technology, Vol.195, pp.15~28, July, (2016)

 

[6]Ihn Namgung, Nguyen Dang Van, "Assessment of Profile Change and Acceptance Criteria of Cold-worked Elbow of ICI Guide Tubes", IJERT, Vol. 4 Issue 10, Oct. (2015)

 

[5]Ihn Namgung, Nguyen Dang Dinh, "Comparison of P-T Limit Curves of OPR-1000 and VVER-1000 RPV based on ASME Code Rule", IJERT, Vol. 4 Issue 09, Sep. (2015)

 

[4]Ihn Namgung, Hyun-Jin Lee, "Computational Fluid Dynamic Analysis Modeling of IVR-ERVC of APR1400 Reactor", IJERT, Vol. 4 Issue 10, Oct. (2015)

 

[3]Khaled Atya Ahmed Abdallah, Ihn Namgung, Patricia Alves Franca De Mesquita, Salwa Al -doais, "SE Approach for the Development of Internal Inspection and Maintenance Methodology of PWR RCS Primary Pipe", IJERT, Vol. 4, Issue 05, May, (2015)

 

[2]Khaled Atya Ahmed Abdallah, Ihn Namgung, "Systems Engineering Method to Develop Multiple BMI Nozzle Inspection System for APR1400", Journal of KOSSE., Vol. 12, No. 1 pp. 27-42, (2016. 6)

 

[1]Khaled Atya Ahmed Abdallah, Ihn Namgung, "Sensitivity study of APR-1400 steam generator primary head stay cylinder and tube sheet thickness", Annals of Nuclear Energy, Vol.92, pp.8~15, (2016)

 

 

Conference Publications

 

Conference Publications

 

Books

1. Ihn Namgung (2016), Introduction to APR1400 Reactor Coolant System Mechanical Design and Analysis, KINGS, ISBN(978-89-969080-6-7)
2. Ihn Namgung (2015), Conceptual Design of PWR600 Reactor Pressure Vessel, KINGS, ISBN(978-89-969080-5-0)
3. Ihn Namgung (2015), Conceptual Design of PWR600 Reactor Internals Mechanical Design, KINGS, ISBN(978-89-969080-4-3)
4. Ihn Namgung (2015), Conceptual Design of PWR600 Steam Generator Mechanical Design, KINGS, ISBN(978-89-969080-3-6)

 

Workbook

1. Ihn Namgung (2020), ANSYS Workbook, rev.2
2. Ihn Namgung (2020), CATIA V5 Workbook, rev.1
3. Ihn Namgung (2021), CATIA Composer Workbook, rev.1

 

Patents

1. 남궁인 (2012.02.03), 방사성폐기물 밀봉처리방법, 한국, 10-1115118
2. 남궁인 (2017.09.04), 가압경수형 원자로의 노심 상부설치 노내계측기 안네관 장치 및 그 고정장치, 한국, 10-1776866
3. 남궁인 (2017.09.29), 가압경수형 원자로의 이중 튜브뱅크를 갖은 노심 상부연결 노내계측기 안내관 장치, 한국, 10-1785322

Projects

- External Projects
- KINGS Projects Reports

External Projects

 

1. 금속 3D 프린팅 산업 활성화 사업, 2020.6.1. ~ 2022.5.31, 울산광역시
2. 4차 산업혁명 시대의 금속 3D 프린팅 기술을 이용한 원전부품 제조공급 기반기술 개발, 2020.4.1. ~ 2022.3.31, 한국수력원자력
3. 금속3D 프린팅을 활용한 원자력부품 시작품 제작 및 품질 검증 사업, 2019.5.1. ~ 2020.2.29, 울산테크노파크
4. 중소형로 상부탑재형 노내계측계통 (TM-ICI) 배치 기술자문, 2014.4.1. ~ 2014.9.30, 한국전력기술
5. 상부탑재형 노내계측계통 개발과제 기술자문, 2013.10.4. ~ 2013.11.30, 한국전력기술

 

KINGS Projects Reports

KINGS Projects Reports

 

Awards

1. Amy Gichuru, Ihn Namgung (July, 2020), Best Paper (Estimation of APR1400 nuclear fuel spacer grid equivalent Young's modulus for a reduced model of fuel assembly), KSME Reliability Division
2. Amy Gichuru (Mar. 2020), Scholarship (KNS Annual Scholarship of Academic Achievement), KNS
3. Khaled Atya Ahmed Abdallah (May, 2015), Scholarship (KNS annual scholarship of academic achievement), KNS
4. Nguyen Dang Van, Ihn Namgung (Nov., 2014), Best Paper (An investigation of wall thining and cross sectional geometry change of bent tube of small diameters), KNS
5. Lee Hyun-Jin, Cho Yun-Ki, Nguyen Dang Van, Nguyen Hoang Giang (Oct., 2014), 2nd Place KINGS annual project competition, KINGS
6. Kyu-Wan Kim (May, 2014), Sholarship (KNS annual scholarship of aacademic achievement), KNS
7. Nguyen Truong Quang, Ihn Namgung (May, 2014), Best Paper (Thermal Stress Investigation of Reactor Coolant System of VVER-1000 Reactor for Normal Operation Condition), Korean Nuclear Association (KNS)

Galleries

After Commencement Ceremony of Year 2019, 2020.12.15
  • 2019 test2
At Commencement Ceremony with students from the lab, 2020.01.29
  • 2019 test2
Magnolia blossom on KINGS Campus amid CORVID19 pandemic, 2020.03.18
  • 2019 test2
At KSME Spring Conference in Jeju Oriental Hotel, 2020.07.14~16
  • 2019 test2
At GanJul-Gok with graduating students, 2020.12.08
  • 2019 test2
Hiking at Mount KumJung with other faculty, 2019.06.06
  • 2019 test2
At the IAEA Head Quater in Vienna for IAEA General Conference, 2019.10.19
  • 2019 test2
Hiking at Mount GanWol with students, 2019.10.19
  • 2019 test2
Hiking at Mount GanWol with students, 2019.10.19
  • 2019 test2
During three week IAEA NPP infrastructure building training course for newcomer countries, 2018.07
  • 2019 test2
2018 KNS fall conference at SeoSu Convention Center, 2018.10.24~26
  • 2019 test2
At the PBNC conference in Vancuber Canada in 2018.09.29~10.05
  • 2019 test2
At the Commencement Ceremony, 2017.01.18
  • 2019 test2
Hiking on YongSil Trail of Mount Halla at the KSME Fall Conference , 2017.11.1~3
  • 2019 test2
Hiking with Prof. TaeRyong Kim on SungPanAk Trail of Mount Halla at the KSME Fall Conference, 2017.11.1~3
  • 2019 test2
At the Commencement Ceremony, 2016.01.20
  • 2019 test2
Hiking to Yong-Nam Alps (mount GanWol), 2016.11.4.
  • 2019 test2
On a Spring day in KINGS campus with other faculty, 2015.04.17
  • 2019 test2
At the SMiRT conference Banquet, 2015.08.08~14
  • 2019 test2
At the Commencement Ceremony of year 2013, 2014.01.22
  • 2019 test2
Snow on campus, 2014.02.12
  • 2019 test2
At the APR1400 road show in Prague, Czech Republic, 2014.06.03~07
  • 2019 test2
At the ICONE22 Conference, 2014.07.11-14
  • 2019 test2
After visiting KAERI research reactor facility in Daejon, 2014.08.05
  • 2019 test2
At the PBNC 2014 Conference, 2014.08.24-30
  • 2019 test2
At the APR1400 road show at Cairo, Egypt, 2014.11.04~06
  • 2019 test2
Faculty workshop (2013.05.03)
  • 2019 test2
With students and family after iNUSTEC conference (2013.09.30)
  • 2019 test2
Opening of KINGS and Orientation for new students (2012.02.27)
  • 2019 test2
Meeting with students before course registration (2012.02.29)
  • 2019 test2
Mount Ganwol (Young-Nam Alps) Hiking with Lab members in 2012.10.7
  • 2019 test2