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Featured researches published by Tae Hyun Chun.


Nuclear Engineering and Technology | 2008

HIGH BURNUP FUEL TECHNOLOGY IN KOREA

Kun Woo Song; Yong Hwan Jeong; Keon Sik Kim; Je Geon Bang; Tae Hyun Chun; Hyung Kyu Kim; Kee Nam Song

High burn-up fuel technology has been developed through a national R&D program, which covers key technology areas such as claddings, UO2 pellets, spacer grids, performance code, and fuel assembly tests. New cladding alloys were developed through alloy designs, tube fabrication, out-of-pile test and in-reactor test. The new Zr-Nb tubes are found to be much better in their corrosion resistance and creep strength than the Zircaloy-4 tube, owing to an optimized composition and heat treatment of the new Zr-Nb alloys. A new fabrication technology for large grain UO2 pellets was developed using various uranium oxide seeds and a micro-doping of Al. The uranium oxide seeds, which were added to UO2 powder, were prepared by oxidizing and heat-treating scrap UO2 pellets. A UO2 pellet containing tungsten channels was fabricated for a thermal conductivity enhancement. For the fuel performance analysis, new high burnup models were developed and implemented in a code. This code was verified by an international database and our own database. The developed spacer grid has two features of contoured contact spring and hybrid mixing vanes. Mechanical and hydraulic tests showed that the spacer grid is superior in its rod- supporting, wear resistance and CHF performance. Finally, fuel assembly test technology was also developed. Facilities for mechanical and thermal hydraulic tests were constructed and are now in operation. Several achievements are to be utilized soon by the Korea Nuclear Fuel and thereby contribute to the economy and safety of PWR fuel in Korea


Journal of Nuclear Science and Technology | 2009

Evaluation of a Dual-Cooled Annular Fuel Heat Split and Temperature Distribution

Yong Sik Yang; Chang Hwan Shin; Tae Hyun Chun; Kun Woo Song

The heat flux and fuel temperature of an annular fuel rod was analyzed using a newly developed program, DUO_THERM. The dual-cooled annular fuel rod has both inner and outer coolant channels. The heat fluxes to inner and outer claddings can change during irradiation because of the variation in the gap conductances of the inner and outer sides. The heat flux is a very important design factor affecting fuel integrity and safety. However, in an annular fuel design, the prediction of heat flux is very complicated because it is closely connected with size changes of two gaps, which are different from each other during irradiation. A burnup increase and power change can cause pellet and cladding radial deformation and eventually change the gap width. Because an annular fuel has two gaps at both sides and their heat resistances are very large, an imbalance of the gap width can lead to heat flux asymmetry. Therefore, a pellet and cladding dimensional change including densification, swelling, creep, and thermal expansion must be considered in the calculation of heat flux and temperature. By using the DUO_THERM program, the changes in heat flux and temperature during an operation were evaluated with respect to a reference design of an annular fuel. The results of the evaluation showed that the heat flux of an annular fuel was greatly affected by the inner and outer gap conductance changes. The heat flux of the inner cladding was maximum at zero burnup, but that of the outer cladding was maximum at the burnup of the outer gap closing. In addition, the maximum fuel temperature location was changed by gap conductance asymmetry.


Key Engineering Materials | 2006

Development of a Bi-Axial Acceleration-Detecting Device for a Tube

Dong Seok Oh; Young Ho Lee; Chang Hwan Shin; Tae Hyun Chun; Hyung Kyu Kim; Kye Bock Lee

A new device for measuring an acceleration in a fuel rod has been developed. The primary purpose is to apply it to the experiments for a nuclear fuel fretting, which is caused by a fuel rod and grid interaction due to a flow-induced vibration of the rods. A bi-axial accelerationdetecting device of a cylindrical shape for an insertion into a cladding tube is designed. Two unimorph piezoelectric accelerometers of small size and for special use in a high temperature condition were attached to the housing’s inner wall of the mounting device, which were oriented perpendicularly with each other to accommodate the acceleration signal during a fretting. Verification is carried out by a displacement and a frequency response analysis. The verification results of the bi-axial acceleration-detecting device showed a good response for the amplitude and bi-directional trace. This paper mainly presents the detailed design of the bi-axial accelerationdetecting device which is developed by using the design optimization of a cylindrical type and applying it to the lower and upper plugs to sustain the device in the tube wall. The verification is carried out by a displacement analysis and a frequency response analysis. An elaboration of the development procedure, calibration method and results are also given in this paper.


Archive | 1998

Grid with nozzle-type coolant deflecting channels for use in nuclear reactor fuel assemblies

Heung Seok Kang; Kee Nam Song; Kyung Ho Yoon; Youn Ho Jung; Tae Hyun Chun; Dong Seok Oh; Wang Kee In; Je Geon Bang


Archive | 1998

Spacer grid with H-spring for fuel rods for use in nuclear reactor fuel assemblies

Kyung Ho Yoon; Heung Seok Kang; Hyung Kyu Kim; Kee Nam Song; Youn Ho Jung; Tae Hyun Chun; Dong Seok Oh; Wang Kee In


Archive | 2002

LIPS-TYPE MULTI-PURPOSED NUCLEAR FUEL ASSEMBLY SPACER GRID

Dae Ho Kim; Kee Nam Song; Tae Hyun Chun; Kyung Ho Yoon; Dong Seok Oh; Heung Seok Kang; Youn Ho Jung; Hyung Kyu Kim; Wang Kee In; Chang-Hwan Shin; Gyung-Jin Park


Archive | 2001

Spacer grid for nuclear reactor fuel assemblies with grid springs maintaining conformal contact with fuel rods and enlarged elastic range

Kyung Ho Yoon; Heung Seok Kang; Hyung Kyu Kim; Kee Nam Song; Youn Ho Jung; Tae Hyun Chun; Dong Seok Oh; Wang Kee In; Gyung-Jin Park


Archive | 2003

SIDE-SLOTTED NOZZLE TYPE DOUBLE SHEET SPACER GRID FOR NUCLEAR FUEL ASSEMBLIES

Heung Seok Kang; Kyung Ho Yoon; Hyung Kyu Kim; Kee Nam Song; Yeon Ho Jung; Tae Hyun Chun; Dong Seok Oh; Wang Kee In


Archive | 2007

Annular nuclear fuel rod controllable in heat fluxes of inner and outer tubes

Kun Woo Song; Tae Hyun Chun; Yong Sik Yang; Je Geon Bang; Dong Seok Oh


Archive | 2009

INTERMEDIATE END PLUG ASSEMBLY FOR SEGMENTED FUEL ROD AND SEGMENTED FUEL ROD HAVING THE SAME

Kyung Ho Yoon; Jae Yong Kim; Young Ho Lee; Kun Woo Song; Tae Hyun Chun; Dong Seok Oh; Wang Ki In; Hyung Kyu Kim; Chang Hwan Shin

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Dong Seok Oh

Korea Electric Power Corporation

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Hyung Kyu Kim

Korea Electric Power Corporation

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Kyung Ho Yoon

Korea Electric Power Corporation

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Kee Nam Song

Korea Electric Power Corporation

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Wang Kee In

Korea Electric Power Corporation

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Young Ho Lee

Sungkyunkwan University

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Heung Seok Kang

Korea Electric Power Corporation

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Je Geon Bang

Korea Electric Power Corporation

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