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1

Multi-physics steady-state analysis of OECD/NEA modular high temperature gas-cooled reactor MHTGR-350

Lemaire, Matthieu, Lee, Hyunsuk, Tak, Nam-il, Lee, Hyun Chul, Lee, Deokjung

Journal:

Journal of Nuclear Science and Technology

Year:

2017

Language:

english

File:

PDF, 1.66 MB

english, 2017

2

Investigation on turbulent heat transfer to lead–bismuth eutectic flows in circular tubes for nuclear applications

Xu Cheng, Nam-il Tak

Journal:

Nuclear Engineering and Design

Year:

2006

Language:

english

File:

PDF, 483 KB

english, 2006

3

A combined procedure of RSM and LHS for uncertainty analyses in source term quantifications using MAAP3.0B code

Moon-Hyun Chun, Seok-Jung Han, Nam-Il Tak

Journal:

Annals of Nuclear Energy

Year:

1996

Language:

english

File:

PDF, 952 KB

english, 1996

4

CFD analysis of the HYPER spallation target

Chungho Cho, Nam-il Tak, Jae-Hyuk Choi, Yong-Bum Lee

Journal:

Annals of Nuclear Energy

Year:

2008

Language:

english

File:

PDF, 1.37 MB

english, 2008

5

Numerical investigation of a heat transfer within the prismatic fuel assembly of a very high temperature reactor

Nam-il Tak, Min-Hwan Kim, Won Jae Lee

Journal:

Annals of Nuclear Energy

Year:

2008

Language:

english

File:

PDF, 1.56 MB

english, 2008

6

Development of a computer code to estimate the fuel rod failure using primary coolant activities of operating PWRS

Moon-Hyun Chun, Nam-Il Tak, Sang-Kyu Lee

Journal:

Annals of Nuclear Energy

Year:

1998

Language:

english

File:

PDF, 637 KB

english, 1998

7

Effect of Growth Interruption in Migration Enhanced Epitaxy on InAs/GaAs Quantum Dots

Ryu, Sung-Pil, Cho, Nam-Ki, Lim, Ju-Young, Rim, A-Ram, Choi, Won-Jun, Song, Jin-Dong, Lee, Jung-Il, Lee, Yong-Tak

Journal:

Japanese Journal of Applied Physics

Year:

2009

Language:

english

File:

PDF, 309 KB

english, 2009

8

VALIDATION OF NUMERICAL METHODS TO CALCULATE BYPASS FLOW IN A PRISMATIC GAS-COOLED REACTOR CORE

TAK, NAM-IL, KIM, MIN-HWAN, LIM, HONG-SIK, NOH, JAE MAN, DRZEWIECKI, TIMOTHY J., SEKER, VOLKAN, DOWNAR, THOMAS J., KELLY, JOSEPH

Journal:

Nuclear Engineering and Technology

Year:

2013

Language:

english

File:

PDF, 5.64 MB

english, 2013

9

Tritium Transport and Distribution in a High-Temperature Gas-Cooled Reactor

Lee, Sung Nam, Tak, Nam-Il

Journal:

Fusion Science & Technology

Year:

2020

Language:

english

File:

PDF, 1.56 MB

english, 2020

10

Thermal-fluid assessment of the design options for reactor vessel cooling in a prismatic core VHTR

Min-Hwan Kim, Nam-il Tak, Hong-Sik Lim

Journal:

Annals of Nuclear Energy

Year:

2010

Language:

english

File:

PDF, 1.98 MB

english, 2010

11

Thermal hydraulic test with 6 MPa nitrogen gas loop for developing the Korean He cooled test blanket

Dong Won Lee, Young Dug Bae, Suk Kwon Kim, Bong Guen Hong, Chan Su Kim, Sung Deok Hong, Nam Il Tak, In Cheol Bang

Journal:

Fusion Engineering and Design

Year:

2010

Language:

english

File:

PDF, 1020 KB

english, 2010

12

Thermo-fluid investigation on a double-side-cooled annular fuel for the prismatic very high temperature gas-cooled reactor

Nam-Il Tak, Yonghee Kim, Jae-Hyuk Choi, Won Jae Lee

Journal:

Nuclear Engineering and Design

Year:

2008

Language:

english

File:

PDF, 1.25 MB

english, 2008

13

Numerical prediction of the fission product plate-out for a VHTR application

Jun Soo Yoo, Nam-il Tak, Hong-Sik Lim, Ji-Han Chun

Journal:

Annals of Nuclear Energy

Year:

2010

Language:

english

File:

PDF, 1.05 MB

english, 2010

14

Sensitivity study on depressurized LOFC accidents with failure of RCCS in a modular gas-cooled reactor

Seyun Kim, Nam-Il Tak, Hong-Sik Lim, Sang-Jun Ha

Journal:

Annals of Nuclear Energy

Year:

2010

Language:

english

File:

PDF, 1.19 MB

english, 2010

15

Computational fluid dynamics analysis of spallation target for experimental accelerator-driven transmutation system

Nam-il Tak, Hans-Joachim Neitzel, Xu Cheng

Journal:

Nuclear Engineering and Design

Year:

2005

Language:

english

File:

PDF, 622 KB

english, 2005

16

Thermal hydraulic investigations on lead-bismuth cooled fuel assemblies with ducts

Nam-Il Tak, Tae Y. Song, Chang-Hyun Kim

Journal:

Progress in Nuclear Energy

Year:

2004

Language:

english

File:

PDF, 563 KB

english, 2004

17

An uncertainty importance measure using a distance metric for the change in a cumulative distribution function

Moon-Hyun Chun, Seok-Jung Han, Nam-IL Tak

Journal:

Reliability Engineering & System Safety

Year:

2000

Language:

english

File:

PDF, 213 KB

english, 2000

18

Thermo-mechanical analysis of the prismatic fuel assembly of VHTR in normal operational condition

Ji-Ho Kang, Nam-il Tak, Min-Hwan Kim

Journal:

Annals of Nuclear Energy

Year:

2012

Language:

english

File:

PDF, 2.92 MB

english, 2012

19

Anti-inflammatory effect of fucoxanthin derivatives isolated from Sargassum siliquastrum in lipopolysaccharide-stimulated RAW 264.7 macrophage

Soo-Jin Heo, Weon-Jong Yoon, Kil-Nam Kim, Chulhong Oh, Young-Ung Choi, Kon-Tak Yoon, Do-Hyung Kang, Zhong-Ji Qian, Il-Whan Choi, Won-Kyo Jung

Journal:

Food and Chemical Toxicology

Year:

2012

Language:

english

File:

PDF, 457 KB

english, 2012

20

Urine output is associated with prognosis in patients with acute kidney injury requiring continuous renal replacement therapy

Oh, Hyung Jung, Shin, Dong Ho, Lee, Mi Jung, Ko, Kwang Il, Kim, Chan Ho, Koo, Hyang Mo, Doh, Fa Mee, Kwon, Young Eun, Kim, Yung Ly, Nam, Ki Heon, Park, Kyoung Sook, An, Seong Yeong, Park, Jung Tak, Ha

Journal:

Journal of Critical Care

Year:

2013

Language:

english

File:

PDF, 531 KB

english, 2013

21

Numerical and experimental investigation on labyrinth seal mechanism for bypass flow reduction in prismatic VHTR core

Yoon, Su-Jong, Lee, Jeong-Hun, Lee, Sang-Moon, Tak, Nam-il, Kim, Min-Hwan, Kim, Kwang-Yong, Park, Goon-Cherl

Journal:

Nuclear Engineering and Design

Year:

2013

Language:

english

File:

PDF, 3.35 MB

english, 2013

22

Thermal analysis of prismatic gas-cooled reactor core under coolant channel blockage accidents

Lee, Sung Nam, Tak, Nam-il, Kim, Min Hwan, Noh, Jae Man

Journal:

Annals of Nuclear Energy

Year:

2014

Language:

english

File:

PDF, 4.13 MB

english, 2014

23

Bijections among combinatorial models for shifted Littlewood–Richardson coefficients

Choi, Seung-Il, Nam, Sun-Young, Oh, Young-Tak

Journal:

Journal of Combinatorial Theory, Series A

Year:

2014

Language:

english

File:

PDF, 527 KB

english, 2014

24

Effect of Modified Growth Method on the Structural and Optical Properties of InAs/GaAs Quantum Dots for Controlling Density

Ryu, Sung-Pil, Cho, Nam-Ki, Lim, Ju-Young, Lee, Hye-Jin, Choi, Won-Jun, Song, Jin-Dong, Lee, Jung-Il, Lee, Yong-Tak

Journal:

Japanese Journal of Applied Physics

Year:

2009

Language:

english

File:

PDF, 453 KB

english, 2009

25

Ultra-mechanically stable and transparent conductive electrodes using transferred grid of Ag nanowires on flexible substrate

Jang, Hyejin, Kim, Dongjae, Tak, Hyowon, Nam, Jaewook, Kim, Tae-il

Journal:

Current Applied Physics

Year:

2016

Language:

english

File:

PDF, 1.44 MB

english, 2016

26

CAPP/GAMMA+ code system for coupled neutronics and thermo-fluid simulation of a prismatic VHTR core

Tak, Nam-il, Lee, Hyun Chul, Lim, Hong Sik, Han, Tae Young

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 5.26 MB

english, 2016

27

Study on Influence of Turbulence Model Selection on Prediction of Flow Distribution and Hot Spot Fuel Temperature in Prismatic HTGR Cores

Kim, Min-Hwan, Tak, Nam-il, Noh, Jae-Man

Journal:

Engineering Applications of Computational Fluid Mechanics

Year:

2014

Language:

english

File:

PDF, 1.65 MB

english, 2014

28

DEVELOPMENT OF A CORE THERMO-FLUID ANALYSIS CODE FOR PRISMATIC GAS COOLED REACTORS

TAK, NAM-IL, LEE, SUNG NAM, KIM, MIN-HWAN, LIM, HONG SIK, NOH, JAE MAN

Journal:

Nuclear Engineering and Technology

Year:

2014

Language:

english

File:

PDF, 6.86 MB

english, 2014

29

Fuel temperature prediction using a variable bypass gap size in the prismatic VHTR

Lee, Sung Nam, Tak, Nam-il, Kim, Min Hwan

Journal:

Nuclear Engineering and Design

Year:

2016

Language:

english

File:

PDF, 7.55 MB

english, 2016

30

[ASME 14th International Conference on Nuclear Engineering - Miami, Florida, USA (July 17–20, 2006)] Volume 4: Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition - Three-Dimensional CFD Analysis on Gas Flow in Corrugated Wall Channel

Tak, Nam-il, Lee, Won-Jae, Jang, Jonghwa

Year:

2006

Language:

english

File:

PDF, 451 KB

english, 2006

31

Analytical Study on the Effective Thermal Conductivity of VHTR Fuel Block Geometry with Multiple Cylindrical Holes

Shin, Dong-Ho, Yoon, Su-Jong, Tak, Nam-Il, Park, Goon-Cherl, Cho, Hyoung-Kyu

Journal:

Nuclear Technology

Year:

2015

Language:

english

File:

PDF, 2.79 MB

english, 2015

32

A Practical Method for Whole-Core Thermal Analysis of a Prismatic Gas-Cooled Reactor

Tak, Nam-Il, Kim, Min-Hwan, Lim, Hong Sik, Noh, Jae Man

Journal:

Nuclear Technology

Year:

2012

Language:

english

File:

PDF, 1.57 MB

english, 2012

33

[ASME ASME/JSME 2011 8th Thermal Engineering Joint Conference - Honolulu, Hawaii, USA (March 13–17, 2011)] ASME/JSME 2011 8th Thermal Engineering Joint Conference - CFD Analysis on the Influence of Coolant Distribution Blocks on the Core Hot Spot Temperature in a Prismatic Very High Temperature Reactor

Kim, Min-Hwan, Tak, Nam-il, Noh, Jae Man, Park, Goon-Cherl

Year:

2011

Language:

english

File:

PDF, 790 KB

english, 2011

34

Design and control of a linearity-enhanced SMA actuator

Son, Hyung-Min, Tak, Chul-Gon, Kang, Seok-Won, Kim, Jae-Il, Nam, Tae-Hyun, Lee, Yun-Jung

Journal:

Physica Scripta

Year:

2010

File:

PDF, 1.03 MB

2010

35

Design and control of a linearity-enhanced SMA actuator

Son, Hyung-Min, Tak, Chul-Gon, Kang, Seok-Won, Kim, Jae-Il, Nam, Tae-Hyun, Lee, Yun-Jung

Journal:

Physica Scripta

Year:

2010

Language:

english

File:

PDF, 1.03 MB

english, 2010

36

Treatment of Tibial Shaft Fracture with Butterfly Fragment using Interlocking Intramedullary Nailing

Yoo, Chong Il, Suh, Jeung Tak, Nam, Tae Wook

Journal:

Journal of the Korean Fracture Society

Year:

1999

Language:

english

File:

PDF, 274 KB

english, 1999

37

Water-jacket reactor cavity cooling system concept to mitigate severe accident consequence of high temperature gas-cooled reactor

Lim, Hong Sik, Tak, Nam-il, Lee, Sung Nam, Jo, Chang Keun

Journal:

Nuclear Engineering and Design

Year:

2018

Language:

english

File:

PDF, 3.23 MB

english, 2018

38

Ilizarov External Fixation for Severe Open Tibial Shaft fractures in Adults

Suh, Jeung Tak, Nam, Tae Wook, Yoo, Chong Il

Journal:

Journal of the Korean Fracture Society

Year:

1999

File:

PDF, 1.18 MB

1999

39

Surgical Treatment and Prognostic Factor for Metastatic Bone Tumor

Kim, Jeung-Il, Yoo, Chong-Il, Suh, Jeung-Tak, Suh, Kuen-Tak, Kim, Hui-Taek, Moon, Nam-Hoon

Journal:

The Journal of the Korean Orthopaedic Association

Year:

2008

Language:

english

File:

PDF, 465 KB

english, 2008

40

Investigations of Hydraulic Behavior in Spallation Target Configurations

Cheng, Xu, Batta, Abdalla, Tak, Nam-Il

Journal:

Nuclear Technology

Year:

2006

Language:

english

File:

PDF, 1.08 MB

english, 2006

41

Benchmark calculations for verification of thermo-fluid analysis codes using simplified model of the OECD/NEA MHTGR-350 core design

Lee, Sung Nam, Tak, Nam-il, Lim, Hong-Sik, Jo, Chang Keun, Seker, Volkan, Downar, Thomas J.

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 4.33 MB

2020

42

Time-dependent neutron diffusion analysis using finite element method for a block-type VHTR core design

Yuk, Seungsu, Cho, Jin Young, Jo, Chang Keun, Tak, Nam-il, Lim, Hong Sik

Journal:

Nuclear Engineering and Design

Year:

2020

File:

PDF, 1.10 MB

2020

43

POSCA: A computer code for fission product plateout and circulating coolant activities within the primary circuit of a high temperature gas-cooled reactor

Tak, Nam-il, Lee, Jeong-Hun, Lee, Sung Nam, Jo, Chang Keun

Journal:

Nuclear Engineering and Technology

Year:

2020

File:

PDF, 2.33 MB

2020