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Featured researches published by Jae-Ho Yang.


Nuclear Technology | 2014

KAERI’s Development of LWR Accident-Tolerant Fuel

Yang-Hyun Koo; Jae-Ho Yang; Jeong-Yong Park; Keon-Sik Kim; Hyung-Il Kim; Dong-Joo Kim; Yang-Il Jung; Kun-Woo Song

Abstract The Fukushima accident has had a tremendous impact on Japan and the rest of the world in the areas of public health, economy, and nuclear energy policy. Thus, international consensus has been reached that inherent tolerance of nuclear fuel to severe accidents needs to be increased significantly to prevent accidents or to mitigate their consequences. In this respect, several countries have started to develop accident-tolerant fuel (ATF) that can tolerate loss of active cooling for a considerably longer time period than current fuels, while maintaining or improving performance during normal operations and operational transients and also enhancing fuel safety for beyond-design-basis events. The Korea Atomic Energy Research Institute is also developing ATF: surface-coated Zr cladding and metal-ceramic hybrid cladding for the purpose of suppressing hydrogen generation during severe accidents, and microcell UO2 pellets to enhance the retention of highly radioactive and corrosive fission products such as Cs and I, where all UO2 grains are enveloped by thin cell walls that act as chemical traps or physical barriers for the movement of fission products. When the screening of developing fuel materials has been performed through various out-of-pile tests, irradiation tests of the selected materials will be carried out in a research reactor to demonstrate their enhanced accident tolerance.


Nuclear Technology | 2017

On the Minimum Thickness of FeCrAl Cladding for Accident-Tolerant Fuel

Hyung-Kyu Kim; Hyung-Il Kim; Jae-Ho Yang; Yang-Hyun Koo

Abstract The thickness of iron-based accident-tolerant fuel (ATF) cladding is discussed in this technical note because its thickness tends to be reduced from conventional zirconium alloy cladding. Structural stability may be lost if the thickness cannot withstand external pressure. Thus, the minimum allowable thickness of the ATF cladding is studied here from the viewpoint of preventing a cladding collapse. The elastic buckling theory is used to obtain the minimum thickness. The uncertainties of the mechanical properties and dimension tolerances are taken into consideration. The ovality of the cladding is also incorporated. An example calculation is carried out for APMT cladding. It is evaluated that the minimum thickness is 0.45 mm when the safety factor against the buckling is set as 2.0 and 1% of the cladding radius is accommodated for the ovality. A reference guideline of the minimum thickness depending on the mechanical property variation is suggested.


Nuclear Engineering and Technology | 2016

Development Status of Accident-tolerant Fuel for Light Water Reactors in Korea

Hyung-Il Kim; Jae-Ho Yang; Weon-Ju Kim; Yang-Hyun Koo


Thermochimica Acta | 2006

The linear thermal expansion and the thermal diffusivity measurements for near-stoichiometric (U, Ce)O2 solid solutions

Dong-Joo Kim; Yongsoo Kim; Si-Hyung Kim; Jong-Heon Kim; Jae-Ho Yang; Young-Woo Lee; Han-Soo Kim


Materials & Design | 2017

Strengthening of Zircaloy-4 using Y2O3 particles by a laser-beam-induced surface treatment process

Yang-Il Jung; Hyung-Il Kim; Il-Hyun Kim; Sun-Han Kim; Jung-Hwan Park; Dong-Jun Park; Jae-Ho Yang; Yang-Hyun Koo


Archive | 2010

Method for Preparing Sintered Annular Nuclear Fuel Pellet

Young-Woo Rhee; Dong-Joo Kim; Kun-Woo Song; Jong-Hun Kim; Keon-Sik Kim; Jae-Ho Yang; Ki-Won Kang; Chill Sun Ryu


Archive | 2013

URANIUM DIOXIDE NUCLEAR FUEL PELLET HAVING CERAMIC MICROCELLS AND FABRICATING METHOD THEREOF

Keon-Sik Kim; Yang-Hyun Koo; Jong-Hun Kim; JangSoo Oh; Young Woo Rhee; Dong-Joo Kim; Jae-Ho Yang


Applied Surface Science | 2018

Surface treatment to form a dispersed Y2O3 layer on Zircaloy-4 tubes

Yang-Il Jung; Hyung-Il Kim; Hwan-Uk Guim; Yoon-Soo Lim; Jung-Hwan Park; Dong-Jun Park; Jae-Ho Yang


Archive | 2011

METHOD OF CONTROLLING SOLUBILITY OF ADDITIVES AT AND NEAR GRAIN BOUNDARIES, AND METHOD OF MANUFACTURING SINTERED NUCLEAR FUEL PELLET HAVING LARGE GRAIN SIZE USING THE SAME

Jae-Ho Yang; Keon-Sik Kim; Kun-Woo Song; Jong-Hun Kim; Young-Woo Rhee; Dong-Joo Kim; Chill-Sun Ryu


Archive | 2010

Method for Fabricating Sintered Annular Nuclear Fuel Pellet Through Rod-Inserted Sintering

Young-Woo Rhee; Dong-Joo Kim; Jong-Hun Kim; Jae-Ho Yang; Ki-Won Kang; Chill Sun Ryu; Keon-Sik Kim; Kun-Woo Song

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Keon-Sik Kim

Korea Electric Power Corporation

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Hyung-Il Kim

Pusan National University

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Jong-Hun Kim

Korea Electric Power Corporation

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Kun-Woo Song

Korea Electric Power Corporation

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Dong-Jun Park

Gyeongsang National University

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Ki-Won Kang

Korea Electric Power Corporation

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