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1

SPIE Proceedings [SPIE Fourth International Conference on Experimental Mechanics - Singapore, Singapore (Wednesday 18 November 2009)] Fourth International Conference on Experimental Mechanics - A measurement of a control rod drop using an LVDT

Choi, Myoung-Hwan, Kim, Ji-Ho, Huh, Hyung, Yu, Je-Yong, Sohn, Dong-Seong, Quan, Chenggen, Qian, Kemao, Asundi, Anand K., Chau, Fook S.

Year:

2010

Language:

english

File:

PDF, 3.99 MB

english, 2010

2

A comparative analysis of UO2 and MOX fuel behavior under reactivity initiated accident

Yang-Hyun Koo, Dong-Seong Sohn, Boris Volkov

Journal:

Annals of Nuclear Energy

Year:

1997

Language:

english

File:

PDF, 542 KB

english, 1997

3

Release of unstable fission products from defective fuel rods to the coolant of a PWR

Koo Yang-Hyun, Sohn Dong-Seong, Yoon Young-Ku

Journal:

Journal of Nuclear Materials

Year:

1994

Language:

english

File:

PDF, 1.09 MB

english, 1994

4

Pore growth in sintered UO2

Song Kun Woo, Young Woo Lee, Myung Seung Yang, Sohn Dong-Seong, Kang Young Hwan

Journal:

Journal of Nuclear Materials

Year:

1994

Language:

english

File:

PDF, 1.13 MB

english, 1994

5

Modeling of creep behavior of Zircaloy-4 by considering metallurgical effect

Byung-Ho Lee, Yang-Hyun Koo, Jin-Sik Cheon, Dong-Seong Sohn

Journal:

Annals of Nuclear Energy

Year:

2002

Language:

english

File:

PDF, 183 KB

english, 2002

6

Modeling and parametric studies of the effect of inhomogeneity on fission gas release in LWR MOX fuel

Yang-Hyun Koo, Byung-Ho Lee, Jin-Sik Cheon, Dong-Seong Sohn

Journal:

Annals of Nuclear Energy

Year:

2002

Language:

english

File:

PDF, 266 KB

english, 2002

7

Cosmos: A computer code to analyze LWR UO2 and MOX fuel up to high burnup

Yang-Hyun Koo, Byung-Ho Lee, Dong-Seong Sohn

Journal:

Annals of Nuclear Energy

Year:

1999

Language:

english

File:

PDF, 985 KB

english, 1999

8

Statistical failure analysis of metallic U-10zr/HT9 fast reactor fuel pin by considering the weibull distribution and cumulative damage fraction

Cheol Nam, Woan Hwang, Dong-Seong Sohn

Journal:

Annals of Nuclear Energy

Year:

1998

Language:

english

File:

PDF, 785 KB

english, 1998

9

Effects of sintering processes on the duplex grain structure of UO2

Kun Woo Song, Dong-Seong Sohn, Woong Kil Choo

Journal:

Journal of Nuclear Materials

Year:

1993

Language:

english

File:

PDF, 1.22 MB

english, 1993

10

An analysis method for the fuel rod gap inventory of unstable fission products during steady-state operation

Koo Yang-Hyun, Sohn Dong-Seong, Yoon Young-Ku

Journal:

Journal of Nuclear Materials

Year:

1994

Language:

english

File:

PDF, 2.04 MB

english, 1994

11

Thermal conductivities of actinides (U, Pu, Np, Cm, Am) and uranium-alloys (U–Zr, U–Pu–Zr and U–Pu–TRU–Zr)

Kim, Yeon Soo, Cho, Tae Won, Sohn, Dong-Seong

Journal:

Journal of Nuclear Materials

Year:

2014

Language:

english

File:

PDF, 935 KB

english, 2014

12

Microstructural characteristics and different effects of 800–1200 °C preformed oxides on high-temperature steam oxidation of a zirconium alloy cladding

Lee, Cheol Min, Jeong, Hu Yeong, Yoon, Aram, Mok, Yong-Kyoon, Sohn, Dong-Seong

Journal:

Journal of Alloys and Compounds

Year:

2018

Language:

english

File:

PDF, 10.17 MB

english, 2018

13

Behavior of unirradiated Zr based uranium metal fuel under reactivity initiated accident conditions

Yang-Hyun Koo, Chong-Tak Lee, Je-Yong Oh, Dong-Seong Sohn, M. Baryshnikov, A. Chechurov, B. Margulis

Journal:

Nuclear Engineering and Design

Year:

2008

Language:

english

File:

PDF, 1.40 MB

english, 2008

14

Fabrication method and thermal conductivity assessment of molybdenum-precipitated uranium dioxide pellets

Si-Hyung Kim, Chang-Young Joung, Han-Soo Kim, Young-Woo Lee, Ho-Jin Ryu, Dong-Seong Sohn, Dong-Joo Kim

Journal:

Journal of Nuclear Materials

Year:

2006

Language:

english

File:

PDF, 981 KB

english, 2006

15

A two-zone method with an enhanced accuracy for a numerical solution of the diffusion equation

Jin-Sik Cheon, Yang-Hyun Koo, Byung-Ho Lee, Je-Yong Oh, Dong-Seong Sohn

Journal:

Journal of Nuclear Materials

Year:

2006

Language:

english

File:

PDF, 1.39 MB

english, 2006

16

Measurement of the specific heat of Zr–40 wt%U metallic fuel

Byung-Ho Lee, Jin-Sik Cheon, Yang-Hyun Koo, Je-Yong Oh, Jeong-Sik Yim, Dong-Seong Sohn, M. Baryshnikov, A. Gaiduchenko

Journal:

Journal of Nuclear Materials

Year:

2007

Language:

english

File:

PDF, 841 KB

english, 2007

17

Molecular dynamics simulation of the pressure–volume–temperature data of xenon for a nuclear fuel

Jae-Yong Oh, Yang-Hyun Koo, Jin-Sik Cheon, Byung-Ho Lee, Dong-Seong Sohn

Journal:

Journal of Nuclear Materials

Year:

2008

Language:

english

File:

PDF, 150 KB

english, 2008

18

Sintering behavior of U–80 at.%Zr powder compacts in a vacuum environment

Tae-Kyu Kim, Chong-Tak Lee, Dong-Seong Sohn

Journal:

Journal of Nuclear Materials

Year:

2008

Language:

english

File:

PDF, 1.19 MB

english, 2008

19

An extension of the two-zone method for evaluating a fission gas release under an irradiation-induced resolution flux

Jin-Sik Cheon, Yang-Hyun Koo, Byung-Ho Lee, Jae-Yong Oh, Dong-Seong Sohn

Journal:

Journal of Nuclear Materials

Year:

2008

Language:

english

File:

PDF, 669 KB

english, 2008

20

Evaluation of a pellet-clad mechanical interaction in mixed oxide fuels during power transients by using axisymmetric finite element modeling

Jin-Sik Cheon, Byung-Ho Lee, Yang-Hyun Koo, Je-Yong Oh, Dong-Seong Sohn

Journal:

Nuclear Engineering and Design

Year:

2004

Language:

english

File:

PDF, 304 KB

english, 2004

21

Measurement of the thermal properties of gadolinium and dysprosium titanate

Byung-Ho Lee, Han-Soo Kim, Sang-Hyun Lee, Dong-Seong Sohn

Journal:

Thermochimica Acta

Year:

2007

Language:

english

File:

PDF, 550 KB

english, 2007

22

Analysis of fission gas release and gaseous swelling in UO2 fuel under the effect of external restraint

Yang-Hyun Koo, Byung-Ho Lee, Dong-Seong Sohn

Journal:

Journal of Nuclear Materials

Year:

2000

Language:

english

File:

PDF, 311 KB

english, 2000

23

Pore pressure and swelling in the rim region of LWR high burnup UO2 fuel

Yang-Hyun Koo, Byung-Ho Lee, Jin-Sik Cheon, Dong-Seong Sohn

Journal:

Journal of Nuclear Materials

Year:

2001

Language:

english

File:

PDF, 211 KB

english, 2001

24

Characterization of U–Nb–Zr dispersion fuel prepared by centrifugal atomization process

Jong-Man Park, Ki-Hwan Kim, Dong-Seong Sohn, Chang-Kyu Kim, Gerard L. Hofman

Journal:

Journal of Nuclear Materials

Year:

1999

Language:

english

File:

PDF, 958 KB

english, 1999

25

Thermal stability of co-extruded U–Zr/Zr–Nb alloys

Chong-Tak Lee, Jong-Hyuk Park, Tae-Kyu Kim, Ui-Jong Lee, Bong-Sang Lee, Dong-Seong Sohn

Journal:

Journal of Nuclear Materials

Year:

2008

Language:

english

File:

PDF, 1.18 MB

english, 2008

26

Zircaloy-4 cladding corrosion model covering a wide range of PWR experiences

Byung-Ho Lee, Yang-Hyun Koo, Jae-Yong Oh, Dong-Seong Sohn

Journal:

Journal of Nuclear Materials

Year:

2008

Language:

english

File:

PDF, 257 KB

english, 2008

27

Three-dimensional simulation of threshold porosity for fission gas release in the rim region of LWR UO2 fuel

Yang-Hyun Koo, Je-Yong Oh, Byung-Ho Lee, Dong-Seong Sohn

Journal:

Journal of Nuclear Materials

Year:

2003

Language:

english

File:

PDF, 222 KB

english, 2003

28

Thermal expansion of near stoichiometric (U,Er)O2 solid solutions

Si-Hyung Kim, Han-Soo Kim, Young-Woo Lee, Dong-Seong Sohn, Dong-Soo Suhr

Journal:

Materials Letters

Year:

2006

Language:

english

File:

PDF, 257 KB

english, 2006

29

Variation of the lattice parameter and thermal expansion coefficient of (U,Dy)O2 as a function of DyO1.5 content

Si-Hyung Kim, Han-Soo Kim, Young-Woo Lee, Dong-Seong Sohn, Dong-Soo Suhr

Journal:

Journal of Alloys and Compounds

Year:

2006

Language:

english

File:

PDF, 207 KB

english, 2006

30

Rim Characteristics and Their Effects on the Thermal Conductivity in High Burnup UO 2 Fuel

LEE, Byung-Ho, KOO, Yang-Hyun, SOHN, Dong-Seong

Journal:

Journal of Nuclear Science and Technology

Year:

2001

Language:

english

File:

PDF, 1.17 MB

english, 2001

31

Resintering Behavior in Oxidativdy Sintered UO 2 and UO 2 -5wt%CeO 2 Pellet

Kim, Si-Hyung, Joung, Chang-Young, Kim, Han-Soo, Na, Sang-Ho, Lee, Young-Woo, Sohn, Dong-Seong

Journal:

Journal of Nuclear Science and Technology

Year:

2002

Language:

english

File:

PDF, 1.88 MB

english, 2002

32

Sintering of U 3 O 8 -CeO 2 Powder Mixture and Its Microstructure Evolution in Different Atmospheres

Lee, Young-Woo, Joung, Chang Young, Kim, Si Hyung, Na, Sang Ho, Sohn, Dong-Seong

Journal:

Journal of Nuclear Science and Technology

Year:

2002

Language:

english

File:

PDF, 1.85 MB

english, 2002

33

A Unified Thermal Conductivity Model of LWR MOX Fuel Considering Its Microstructural Characteristics

Lee, Byung-Ho, Koo, Yang-Hyun, Cheon, Jin-Sik, Oh, Je-Yong, Sohn, Dong-Seong

Journal:

Journal of Nuclear Science and Technology

Year:

2002

Language:

english

File:

PDF, 2.38 MB

english, 2002

34

Thermal conductivity of U–Mo/Al dispersion fuel: effects of particle shape and size, stereography, and heat generation

Cho, Tae Won, Sohn, Dong-Seong, Kim, Yeon Soo

Journal:

Journal of Nuclear Science and Technology

Year:

2015

Language:

english

File:

PDF, 805 KB

english, 2015

35

FABRICATION OF GD CONTAINING DUPLEX STAINLESS STEEL SHEET FOR NEUTRON ABSORBING STRUCTURAL MATERIALS

CHOI, YONG, MOON, BYUNG M., SOHN, DONG-SEONG

Journal:

Nuclear Engineering and Technology

Year:

2013

Language:

english

File:

PDF, 1.53 MB

english, 2013

36

Gas releases and rod internal pressure of BN-added UO 2 fuel

Jeong, Gwan Yoon, Yang, Yong Sik, Sohn, Dong-Seong

Journal:

Journal of Nuclear Science and Technology

Year:

2015

Language:

english

File:

PDF, 687 KB

english, 2015

37

Mechanical analysis of UMo/Al dispersion fuel

Jeong, Gwan Yoon, Kim, Yeon Soo, Sohn, Dong-Seong

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 6.01 MB

english, 2015

38

Corrosion and Wear Properties of Cold Rolled 0.087% Gd Lean Duplex Stainless Steels for Neutron Absorbing Material

Choi, Yong, Baik, Youl, Moon, Byung-Moon, Sohn, Dong-Seong

Journal:

Nuclear Engineering and Technology

Year:

2016

Language:

english

File:

PDF, 1.41 MB

english, 2016

39

Thermal conductivity modeling of U-Mo/Al dispersion fuel

Kim, Yeon Soo, Cho, Byoung Jin, Sohn, Dong-Seong, Park, Jong Man

Journal:

Journal of Nuclear Materials

Year:

2015

Language:

english

File:

PDF, 875 KB

english, 2015

40

Application of a Dynamic-nanoindentation Method to Analyze the Local Structure of an Fe-18 at.% Gd Cast Alloy

Choi, Yong, Baik, Youl, Moon, Byung M., Sohn, Dong-Seong

Journal:

Nuclear Engineering and Technology

Year:

2016

Language:

english

File:

PDF, 1.12 MB

english, 2016

41

Effect of stress evolution on microstructural behavior in U-Mo/Al dispersion fuel

Jeong, G.Y., Kim, Yeon Soo, Jamison, L.M., Robinson, A.B., Lee, K.H., Sohn, Dong-Seong

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 3.20 MB

english, 2017

42

Thermal properties of U-7Mo/Al dispersion fuel

Cho, Tae Won, Kim, Yeon Soo, Park, Jong Man, Lee, Kyu Hong, Kim, Sunghwan, Lee, Chong-Tak, Yang, Jae Ho, Oh, Jang Soo, Won, Ju-Jin, Sohn, Dong-Seong

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 8.83 MB

english, 2017

43

High-temperature steam oxidation and oxide crack effects of Zr-1Nb-1Sn-0.1Fe fuel cladding

Lee, Cheol Min, Mok, Yong-Kyoon, Sohn, Dong-Seong

Journal:

Journal of Nuclear Materials

Year:

2017

Language:

english

File:

PDF, 4.15 MB

english, 2017

44

Enhanced high-temperature oxidation resistance of a zirconium alloy cladding by high-temperature preformed oxide on the cladding

Lee, Cheol Min, Sohn, Dong-Seong

Journal:

Corrosion Science

Year:

2017

Language:

english

File:

PDF, 1.40 MB

english, 2017

45

Irradiation Test of MOX Fuel Rods Fabricated by Attrition-Milling and Analysis of In-Pile Data with COSMOS Code

Lee, Byung-Ho, Koo, Yang-Hyun, Kim, Han-Soo, Oh, Jae-Yong, Lee, Young-Woo, Sohn, Dong-Seong, Wiesenack, Wolfgang

Journal:

Nuclear Technology

Year:

2010

Language:

english

File:

PDF, 1.16 MB

english, 2010

46

Modeling of the Rim Effect on Thermal Behavior of High-Burnup UO 2 Fuel

Lee, Byung-Ho, Koo, Yang-Hyun, Sohn, Dong-Seong

Journal:

Nuclear Technology

Year:

1999

Language:

english

File:

PDF, 434 KB

english, 1999

47

Thermophysical properties of heat-treated U-7Mo/Al dispersion fuel

Cho, Tae Won, Kim, Yeon Soo, Park, Jong Man, Lee, Kyu Hong, Kim, Sunghwan, Lee, Chong Tak, Yang, Jae Ho, Oh, Jang Soo, Sohn, Dong-Seong

Journal:

Journal of Nuclear Materials

Year:

2018

Language:

english

File:

PDF, 2.17 MB

english, 2018

48

Improvement of Fuel Performance Code COSMOS with Recent In-Pile Data for MOX and UO 2 Fuels

Lee, Byung-Ho, Koo, Yang-Hyun, Oh, Je-Yong, Cheon, Jin-Sik, Sohn, Dong-Seong

Journal:

Nuclear Technology

Year:

2007

Language:

english

File:

PDF, 873 KB

english, 2007

49

Thermophysical properties of sintered aluminum-silicon

Cho, Tae Won, Kim, Yeon Soo, Sohn, Dong-Seong

Journal:

Journal of Alloys and Compounds

Year:

2018

Language:

english

File:

PDF, 2.76 MB

english, 2018

50

Yield Stress Determination by the Massachusetts Institute of Technology Miniaturized Disk Bend Test

Sohn, Dong-Seong, Kohse, Gordon E., Parks, David M., Harling, Otto K.

Journal:

Nuclear Technology

Year:

1990

Language:

english

File:

PDF, 724 KB

english, 1990