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Dive into the research topics where Cheol Nam is active.

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Featured researches published by Cheol Nam.


Journal of Nuclear Materials | 2002

Creep strength of Zircaloy-4 cladding depending on applied stress and annealing temperature

Cheol Nam; Byoung-Kwon Choi; Myung Ho Lee; Yong-Hwan Jeong

Abstract Tube creep tests were conducted on low tin Zircaloy-4 cladding with variations given in final annealing temperatures of 769–893 K, test temperatures of 613–673 K and applied hoop stresses of 90–195 MPa. The enhanced creep rates of low tin Zircaloy-4 by a factor of 2 compared with standard Zicaloy-4 were observed mainly due to reduced tin content. It was found that the creep parameters had a considerable stress dependency, that is, the activation energy and stress exponent decreased with stress increment. The plausible contribution of Coble creep to low-temperature-annealed Zircaloys at a lower stress range is discussed based on the determined creep parameters, microstructure and texture to explain the observed stress dependency.


Acta Materialia | 2007

Tetragonal phase stability in ZrO2 film formed on zirconium alloys and its effects on corrosion resistance

W. Qin; Cheol Nam; Hualong Li; Jerzy A. Szpunar


Journal of Nuclear Materials | 2004

Analysis on volume fraction and crystal orientation relationship of monoclinic and tetragonal oxide grown on Zr–2.5Nb alloy

Jianlong Lin; Hualong Li; Cheol Nam; Jerzy A. Szpunar


Journal of Alloys and Compounds | 2007

Effects of local stress on the stability of tetragonal phase in ZrO2 film

W. Qin; Cheol Nam; Hualong Li; Jerzy A. Szpunar


Archive | 2002

Method for manufacturing zirconium-based alloys containing niobium for use in nuclear fuel rod cladding

Yong Hwan Jeong; Jong Hyuk Baek; Byoung Kwon Choi; Sang Yoon Park; Myung Ho Lee; Cheol Nam; Jeong Yong Park; Youn Ho Jung


Journal of Nuclear Materials | 2006

Effects of tube fabrication variables on the oxidation of experimental Zr–2.5Nb tubes

Cheol Nam; Jianlong Lin; Hualong Li; Jerzy A. Szpunar; R.A. Holt


Archive | 2001

Zirconium alloy having excellent corrosion resistance and mechanical properties and method for preparing nuclear fuel cladding tube by zirconium alloy

Yong Hwan Jeong; Jong Hyuk Baek; Byoung Kwon Choi; Myung Ho Lee; Sang Yoon Park; Cheol Nam; Youn Ho Jung


Archive | 2001

Zirconium alloy having excellent corrosion resistance and mechanical properties for nuclear fuel cladding tube

Yong Hwan Jeong; Jong Hyuk Baek; Byoung Kwon Choi; Myung Ho Lee; Sang Yoon Park; Cheol Nam; Youn Ho Jung


Archive | 2000

Niobiuim-containing zirconium alloy suitable for nuclear fuel cladding

Jong Hyuk Baek; Byoung Kwon Choi; Yong Hwan Jeong; Youn Ho Jung; Kyeong Ho Kim; Myung Ho Lee; Cheol Nam; Sang Yoon Park; ケオン ホ キム; ヨン ホ ジュン; ヤン ホァン ジョン; ビョン クォン チョイ; チェオル ナン; ジョン・ヒュク・バエク; サン ユン パク; ミュン ホ リ


Archive | 2002

Verfahren zur Herstellung von Niobium enthaltenden Zirkoniumlegierungen für die Verwendung in Kernreaktorbrennstabhüllen A process for the production of niobium-containing zirconium alloys for use in nuclear fuel rod claddings

Yong Hwan Jeong; Jong Hyuk Baek; Byoung Kwon Choi; Sang Yoon Park; Myung Ho Lee; Cheol Nam; Jeong Yong Park; Youn Ho Jung

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Jong Hyuk Baek

Korea Electric Power Corporation

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Jerzy A. Szpunar

University of Saskatchewan

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W. Qin

University of Saskatchewan

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