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Department of Mechanical and Nuclear Engineering
Dong-Seong Sohn

Professor / UNIST

INFUEL

Welcome to Innovative Nuclear FUEL (INFUEL)

이 곳은 원자력 발전소에 사용하는 핵연료 및 핵재료에 관한 폭 넓은 연구가 이루어지는 연구실입니다. 상용로인 경수로에서부터 연구로 및 4세대 원자로인 고속로, 용융로까지 폭 넓은 연구가 이루어지고 있습니다.

This is a laboratory working for the research and development of nuclear fuels and materials. Research area includes Pressurized Water Reactor (PWR), Research Reactor (RR), and GEN-Ⅳ Reactors such as Fast and Molten Salt Reactors.

Infuel 단체

 

professor

DONG-SEONG SOHN [Professor, UNIST]

dssohn(1)

Department of Mechanical and Nuclear Engineering

Office: Engineering Bldg. 5 (Building 112), Rm.

Tel: +82-52-217-2938          Fax: +82-52-217-3008

E-mail: dssohn@unist.ac.kr

Curriculum Vitae

2010~Present: Professor, UNIST

1976~2010 KAERI, Senior Research Engineer(General Manager)

1986~1987 Siemens KWU

1984: Ph. D. Nuclear materials, Massachusetts Institute of Technology

1977~1978 La Junta de Energia Nuclear

1977: M. S. Materials science, Korea Advanced Institute of Science and Technology

1974: B. S. Nuclear Engineering, Seoul National University

 

members

Graduate Students

 Combined Master’s-Ph.D program

김미진

Name: Mi-Jin Kim, 김 미 진

E-mail:  mjkim3689@unist.ac.kr

Major research:

• Critical analysis for spent fuel cask

 

 Alumni

 Combined Master’s-Ph.D program

정관윤 사진   Dr. Gwan Yoon Jeong, 정 관 윤 (February 2014 – February 2018)

E-mail: huckel1123@unist.ac.kr

Thesis: Irradiation Performance Modeling and PRIME Code Development for U-Mo Dispersion Fuel for Research Reactors

After graduation: Postdoctoral Researcher in UNIST

Download CV

반명함판사진

Dr. Tae Won Cho, 조 태 원 (August 2013 – August 2018)

E-mail: twcho@kaeri.re.kr

Thesis: Measurements and Modeling of Thermal Conductivity of U-Mo/Al Dispersion Fuel for Research Reactor

After graduation: Postdoctoral Researcher in KAERI

Download CV

KakaoTalk_20180313_234537800   Dr. Cheol Min Lee, 이 철 민 (February 2014 – August 2018)

E-mail: cmlee@kaeri.re.kr

Thesis: Enhanced Accident Performance of Zirconium Alloy Cladding Tube by High-Temperature Preformed Oxide and Analysis of Preformed Oxide Microstructures

After graduation: Postdoctoral Researcher in KAERI

Download CV

김지현

Dr. Ji Hyeon Kim, 김 지 현 (August 2013 – February 2019)

E-mail: sangdu87@naver.com

Thesis: Investigation of ZrN Non-Reactively Sputtered Diffusion Barrier Coating for U-Mo Dispersion Fuel

After graduation: Postdoctoral Researcher in KIMS

 

Master’s Program

백제균

Je Kyun Baek, 백 제 균 (February 2015 – February 2017)

E-mail:  artoss12@unist.ac.kr

Thesis: High Temperature Corrosion Test of a Zirconium alloy

After graduation: Ph.D course in KAIST

조병진

Byoung-Jin Cho, 조 병 진 (February 2013 – February 2017)

E-mail:  cho1078@nate.com

Thesis: Modeling of the Thermal Conductivity of U-Mo/Al Dispersion Fuel

After graduation: Researcher in KAERI

이희재

Hee-Jae Lee, 이 희 재 (February 2015 – August 2017)

E-mail:  hjlee21@unist.ac.kr

Thesis: Effect of Gd-alloyed Neutron Absorber on Thermal Performance of a Spent Fuel Cask

After graduation: Researcher in JAEA

updated 2019-08-28

research

INFUEL is a laboratory working for nuclear fuel cycle, nuclear fuel performance…

연구실설명1

publications

List of the Selected Journal Publications (* denotes corresponding author)
 Click the title to follow the paper.

  • Research Reactor Fuel/Material Field : 
  1. Ji-Hyeon Kim, Gwan Yoon Jeong, S.H. Kim, Y.J. Jeong, Dong-Seong Sohn*, “Dependence of thickness, morphology, and crystallographic properties of Mo and ZrN coatings on U-Mo substrate size“, J. Nucl. Mater. 512 (2018) 156-168.
  2. Ji-Hyeon Kim, Gwan Yoon Jeong, S.H. Kim, Y.J. Jeong, Dong-Seong Sohn*, “Effect of coating thickness and annealing temperature on ZrN coating failure of U-Mo particles under heat treatment“, J. Nucl. Mater. 507 (2018) 347-359.
  3. Gwan Yoon Jeong, Yeon Soo Kim, Y.J. Jeong, J.M. Park, Dong-Seong Sohn*, “Development of PRIME for irradiation performance analysis of U-Mo/Al dispersion fuel“, J. Nucl. Mater. 502 (2018) 331-348.
  4. Tae Won Cho, Yeon Soo Kim, Dong-Seong Sohn*, “Thermophysical properties of sintered aluminum-silicon“,  J. Alloys Compd. 479 (2018) 1028-1035.
  5. Tae Won Cho, Yeon Soo Kim, Dong-Seong Sohn*, et al., “Thermophysical properties of heattreated U-7Mo/Al“, J. Nucl. Mater. 501 (2018) 31-44.
  6. Tae Won Cho, Yeon Soo Kim, Dong-Seong Sohn*, et al., “Thermal properties of U-7Mo/Al dispersion fuel“, J. Nucl. Mater. 496, (2017) 274-285.
  7. Gwan Yoon Jeong, Yeon Soo Kim, L.M. Jamison, A.B. Robinson, K.H. Lee, Dong-Seong Sonh*, “Effect of stress evolution on microstructural behavior in U-Mo/Al dispersion fuel“, J. Nucl. Mater. 487 (2017) 265.
  8.  Yeon Soo Kim, Gwan Yoon Jeong, Dong-Seong Sohn, L.M. Jamison, “Pore growth in U-Mo/Al dispersion fuel“, J. Nucl. Mater. 478 (2016) 275.
  9.  Yeon Soo Kim, Byoung Jin Cho, Dong-Seong Sohn*, J.M. Park, “Thermal Conductivity Modeling of U-Mo/Al Dispersion Fuel“, J. Nucl. Mater.  466 (2015) 576.
  10.  Gwan Yoon Jeong, Dong-Seong Sohn*, Yeon Soo Kim, “Mechanical analysis of UMo/Al dispersion fuel“, J. Nucl. Mater. 466 (2015) 509.
  11.  Tae Won Cho, Dong-Seong Sohn*, Yeon Soo Kim, “Thermal conductivity of U–Mo/Al dispersion fuel: effects of particle shape and size, stereography, and heat generation“, J. Nucl. Sci. Technol. 52(10) (2015) 1328.

 

  • Light Water Reactor Fuel/Material Field :
  1. Cheol Min Lee*, G. Kim, Y.-S. Han, Y.-K. Mok, Dong-Seong Sohn, “Short communication on “self-crack-healing behavior of oxide formed on a zirconium alloy cladding tube“”, J. Nucl. Mater. 526 (2019) 151749.
  2. Cheol Min Lee, Y.-S. Han, Y.-K. Mok, Dong-Seong Sohn*, “Study of mechanism of oxidation resistance enhancement induced by preformed oxide on zirconium alloys“, Corros. Sci. 158 (2019) 108105.
  3. Gwan Yoon Jeong*, Tae Won Cho, Dong-Seong Sohn, “Performance analysis of UO2 fuel rod for low-power research reactor application“, Ann. Nucl. Energy 129 (2019) 233-239.
  4. Cheol Min Lee, Hee-Jae Lee, H.-G. Kim, Y.-K. Mok, Dong-Seong Sohn*, “Effect of pre-oxidation temperature on the ductility of a zirconium alloy cladding under simulated accident conditions“, J. Nucl. Mater. 515 (2019) 80-90.
  5. Cheol Min Lee, H.Y. Jeong, A. Yoon, Y.-K. Mok, Dong-Seong Sohn*, “Microstructural analysis of preformed oxides on a zirconium alloy before and after subsequent oxidation at 1000–1200 °C“, Corros. Sci. 139 (2018) 410-420.
  6. Cheol Min Lee, H.Y. Jeong, A. Yoon, Y.-K. Mok, Dong-Seong Sohn*, “Microstructural characteristics and effects of 800–1200°C preformed oxides on high-temperature steam oxidation of a zirconium alloy cladding“, J. Alloys Compd. 753 (2018) 119-129.
  7. Cheol Min Lee, Dong-Seong Sohn*, “Enhanced high-temperature oxidation resistance of a zirconium alloy cladding by high-temperature preformed oxide on the cladding“, Corros. Sci. 131 (2018) 116-125.
  8. Cheol Min Lee, Y.-K. Mok, Dong-Seong Sohn*, “High-temperature steam oxidation and oxide crack effects of Zr-1Nb-1Sn-0.1Fe fuel cladding“, J. Nucl. Mater. 496 (2017) 343-352.
  9. Gwan Yoon Jeong, Yang Yong Sik, Dong-Seong Sohn*, “Gas releases and rod internal pressure of BN-added UO2 fuel“, J. Nucl. Sci. Technol. 52(10) (2015) 1208.
  10.  Lee Byung-Ho, Y.H. Koo, J.Y. Oh, J.-S. Cheon, Y.-W. Tahk, Dong-Seong Sohn*,” Fuel performance code COSMO for analysis of LWR UO2 and MOX fuel“, Nucl. Eng. Technol. 43(6) (2011) 499.
  11.  H.S. Kim, C.Y. Joung, B.H. Lee, S.H. Kim, Dong-Seong Sohn*, “Characteristics of GdxMyOz (M=Ti, Zr, Al) as a burnable absorber”, J. Nucl. Mater. 372 (2008) 340.
  12. J.S. Cheon, Y.H. Koo, B.H. Lee, J.Y. Oh, Dong-Seong Sohn*, “An extension of the two-zone method for evaluating a fission gas release under an irradiation-induced resolution flux”, J. Nucl. Mater. 373 (2008), 280.
  13. B.H. Lee, Y.H. Koo, J.Y. Oh, Dong Seong Sohn*,“Zircaloy-4 cladding corrosion model covering a wide range of PWR experiences”,  J. Nucl. Mater.  378 (2008) 127.
  14. J.Y. Oh, Y.H. Koo, J.S. Cheon, B.H. Lee, Dong-Seong Sohn*, “Molecular Dynamics Simulation of the Pressure-Volume-Temperature Data of Xenon for a Nuclear Fuel”, J. Nucl. Mater. 372 (2008) 89.
  15.  C.Y. Joung, S.C. Lee, S.H. Kim, H.S. Kim, Dong-Seong Sohn*, “Fabrication method for UO2 pellets with large grains or a single grain by sintering in air”,  J. Nucl. Mater. 375 (2008) 209.
  16. T.K. Kim, C.T. Lee, Deong-Seong Sohn*, “Sintering behavior of U-80at％Zr powder compacts in a vacuum environment”,  J. Nucl. Mater. 372 (2008) 394.

 

  • Fast Reactor Fuel/Material Field :
  1.  Yeon Soo Kim,  Tae Won Cho, Dong-Seong Sohn, “Thermal conductivities of actinides (U, Pu, Np, Cm, Am) and uranium-alloys (U-Zr, U-Pu-Zr and U-Pu-TRU-Zr)“, J. Nucl. Mater. 445 (2014) 272.

 

  • Spent Fuel/Material Field : 
  1. Mi Jin Kim, W. Kim, D. Lee, M. LeMaire, Hee-Jae Lee, Dong Seong Sohn*, H. Kwon, “Development of integral type spent fuel pool storage rack with gadolinium and europium-containing structure materials“, Ann. Nucl. Energy 130 (2019) 107-117.
  2. G.Y. Jeong, S. Sohn, Y.H. Jeon, J. Park*, “Understanding of electrochemical behaviors of niobium in molten LiCl–KCl eutectic for pyrochemical decontamination process“, J. Nucl Mater. 524 (2019) 39-53.
  3. S. Sohn, G.Y. Jeong, S. Jeong, J. Hur, H. Ju, Y.-H. Shin, I.S. Hwang, J. Park*, “Spatial distribution of CeBi2 in Bi-Ce alloy facilitating density-based separation between actinides and lanthanides“, J. Nucl. Mater. 526 (2019) 151750.
  4. S. Sohn, G.Y. Jeong, J.Y. Park*, “Spatial distribution of HfBi in metallurgically and electrochemically formed Bi-Hf alloy“, J. Alloy. Compd. 790 (25) (2019) 772-782.
  5. Choi Yong, Baik Youl, Moon Byung-Moon, Dong-Seong Sohn*, “Application of a Dynamic-nanoindentation Method to Analyze the Local Structure of an Fe-18 at.% Gd Cast Alloy“, Nucl. Eng. Technol. 49(3) (2017) 576.
  6.  Choi Yong, Baik Youl, Moon Byung-Moon, Dong-Seong Sohn* “Corrosion and Wear Properties of Cold Rolled 0.087% Gd Lean Duplex Stainless Steels for Neutron Absorbing Material“, Nucl. Eng. Technol. 48(1) (2016) 164.
  7.  Baik Youl, Choi Yong, Moon Byung-Moon, Dong-Seong Sohn, B. Simeon, P. Alexander, “Effect of gadolinium addition on the corrosion, wear, and neutron absorbing behaviors of duplex stainless steel sheet“, Phy. Metal. Metallography, 116(11) (2015) 1135.
  8.  Choi Yong, Moon Byung-Moon, Dong-Seong Sohn, “Fabrication of Gd containing duplex stainless steel sheet for neutron absorbing structural materials“, Nucl. Eng. Technol. 45(5) (2013) 689.

 

Patents (Selected)

1. “Spent Fuel Gripper using Two oval Shape Cams”, Korean patent no. 10-2008- 0091554
2. “Method for manufacturing nuclear fuel rod and billetof used thereof”, Korean patent no. 10-2003-0020272
3. “Method for manufacturing UO2 pellet by adding Gd2O3”, Korean patent no. 10-2003-0026831
4. “Method and Furnace for Sintering of U-Zr PowderCompacts in a Low-vacuum Environment”, Korean patent no. 10-2006-0091676
5. “Zirconia added neutron absorbing pellets and theirfabrication methods “, Korean patent no. 10-2006-0081708
6. “Method for manufacturing UO2 sintered body havingcoarse grain or single crystal “, Korean patent no. 10-2005-0099539
7. “DYNAMIC MILL” , Korean patent no. 10-2002-0043461
8. “DYNAMIC MILL ” Japanese patent no. 14261938

education

Undergraduate course

1. Introduction to Nuclear Fuel Cycle Engineering (핵주기공학 개론)

2. Introduction to Nuclear Fuel Engineering (핵연료공학개론)

3. Nuclear engineering Design and Lab 1 (원자력공학 설계프로젝트1)

Graduate course

1. Nuclear Fuel Design & Performance Analysis (핵연료설계 및 성능분석)

NEWS

 

2015.03.08 UBC 논평: 월성원전 수명연장에 대해

Dong-Seong Sohn

dssohn@unist.ac.kr