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Featured researches published by Kyong-bo Eom.


Nuclear Engineering and Technology | 2011

MECHANICAL AND IRRADIATION PROPERTIES OF ZIRCONIUM ALLOYS IRRADIATED IN HANARO

Oh-Hyun Kwon; Kyong-bo Eom; Jae-Ik Kim; Jung-Min Suh; Kyeong-Lak Jeon

These experimental studies are carried out to build a database for analyzing fuel performance in nuclear power plants. In particular, this study focuses on the mechanical and irradiation properties of three kinds of zirconium alloy (Alloy A, Alloy B and Alloy C) irradiated in the HANARO (High-flux Advanced Neutron Application Reactor), one of the leading multipurpose research reactors in the world. Yield strength and ultimate tensile strength were measured to determine the mechanical properties before and after irradiation, while irradiation growth was measured for the irradiation properties. The samples for irradiation testing are classified by texture. For the irradiation condition, all samples were wrapped into the capsule (07M-13N) and irradiated in the HANARO for about 100 days (E > 1.0 MeV, 1.1 x 10 21 n/cm²). These tests and results indicate that the mechanical properties of zirconium alloys are similar whether unirradiated or irradiated. Alloy B has shown the highest yield strength and tensile strength properties compared to other alloys in irradiated condition. Even though each of the zirconium alloys has a different alloying content, this content does not seem to affect the mechanical properties under an unirradiated condition and low fluence. And all the alloys have shown the tendency to increase in yield strength and ultimate tensile strength. Transverse specimens of each of the zirconium alloys have a slightly lower irradiation growth tendency than longitudinal specimens. However, for clear analysis of texture effects, further testing under higher irradiation conditions is needed.


ASME 2009 Pressure Vessels and Piping Conference | 2009

Analysis of Spacer Grid Spring Load-Deflection Characteristic for PWR Fuel Assembly

Kyong-bo Eom; Joon-kyoo Park; Kyoung-joo Kim; Jung-Min Suh; Kyeong-Lak Jeon

Spacer grid springs support fuel rods so that the rods keep the position laterally and axially in pressurized water reactor fuel assemblies. The spring load-deflection characteristic, i.e. spring force and stiffness, is needed to evaluate the rod support conditions in the case of fuel assembly manufacturing, shipping and handling. In general, the load-deflection characteristic of grid spring is obtained by mechanical test, but it takes long time to get the new designed grid specimen because the grid manufacturing process comprises strip material manufacturing, stamping die and punch preparation, heat treatment and welding, etc. Therefore the analytic method such as finite element method (FEM) is tried to predict the nonlinear load-deflection characteristic of new designed grid. The spring characteristic mechanical test is simulated with unit cell model and analyzed by FEM tool. Comparing the results between test and analysis shows that more details are needed in the modeling because the boundary conditions of the spring are very complicated and the spring material thickness is changed by the stamping process. The analysis of modified model including expanded cells and thickness changed springs is performed. Using the analytic method of the work to obtain the load-deflection characteristic of spacer grid spring is expected to be useful in the prediction of the characteristic of new designed grids.Copyright


Archive | 2010

DEBRIS FILTERING BOTTOM SPACER GRID WITH LOUVERS FOR PREVENTING UPLIFT OF FUEL RODS

Joon-kyoo Park; Kyong-bo Eom; Kyu-Tae Kim; Jung-Min Suh; Nam-Gyu Park; Jin-Sun Kim; Dong-geun Ha; Kyoung-joo Kim; Jin-seok Lee; Seong-Ki Lee; Kyeong-Lak Jeon


Archive | 2008

Anti-fretting Wear Spacer Grid With Canoe-Shaped Spring

Kyong-bo Eom; Kyu-Tae Kim; Jung-Min Suh; Shin-ho Lee; Nam-Gyu Park; Joon-kyoo Park; Jin-Sun Kim; Il-kyu Kim; Seong-Ki Lee; Joon-hyung Choi


Archive | 2012

Support grillwork with rowboat-shaped spring for preventing frottage of fuel rod

Shin-ho Lee; Seong-Ki Lee; Joon-hyung Choi; Kyu-Tae Kim; Il-kyu Kim; Nam-Gyu Park; Jin-Sun Kim; Jung-Min Suh; Joon-kyoo Park; Kyong-bo Eom


Archive | 2008

Top nozzle for nuclear fuel assembly

Joon-kyoo Park; Joon-hyung Choi; Kyu-Tae Kim; Jung-Min Suh; Shin-ho Lee; Nam-Gyu Park; Kyong-bo Eom; Jin-Sun Kim; Jin-seok Lee; Seong-Ki Lee


Archive | 2008

Top Nozzle Having On-Off Type Of Hold-Down Spring In Nuclear Fuel Assembly

Joon-kyoo Park; Joon-hyung Choi; Kyu-Tae Kim; Jung-Min Suh; Shin-ho Lee; Nam-Gyu Park; Kyong-bo Eom; Jin-Sun Kim; Jin-seok Lee; Seong-Ki Lee


Archive | 2008

Joining Structure Between Top Nozzle and Guide Thimbles In Nuclear Fuel Assembly

Nam-Gyu Park; Kyu-Tae Kim; Jung-Min Suh; Shin-ho Lee; Kyong-bo Eom; Joon-kyoo Park; Jin-Sun Kim; Gyu-cheol Shin; Seong-Ki Lee; Il-kyu Kim; Ki-sung Choi; Kyeong-Lak Jeon


Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory | 2018

Finite Element Analysis for Fuel Assembly Structural Behavior

Youngik Yoo; Kyoung-Hong Kim; Kyong-bo Eom; Seong-Ki Lee; Jongsung Yoo


Archive | 2016

STRUCTURE OF TOP NOZZLE FOR NUCLEAR FUEL ASSEMBLY

Nam-Gyu Park; Kyu-Tae Kim; Jung-Min Suh; Shin-ho Lee; Kyong-bo Eom; Joon-kyoo Park; Jin-Sun Kim; Gyu-cheol Shin; Seong-Ki Lee; Ii-kyu Kim; Ki-sung Choi; Kyeong-Lak Jeon

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Jung-Min Suh

Korea Electric Power Corporation

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Joon-kyoo Park

Korea Electric Power Corporation

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Jin-Sun Kim

Korea Electric Power Corporation

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Kyu-Tae Kim

Pohang University of Science and Technology

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Nam-Gyu Park

Korea Electric Power Corporation

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Seong-Ki Lee

Korea Electric Power Corporation

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Shin-ho Lee

Korea Electric Power Corporation

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Kyeong-Lak Jeon

Korea Electric Power Corporation

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Il-kyu Kim

Korea Electric Power Corporation

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Ki-sung Choi

Korea Electric Power Corporation

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