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Park, Sang Yoon, Kim, Jun Hwan, Lee, Myoung Ho, Jeong, Yong Hwan (2008) Effects of the microstructure and alloying elements on the iodine-induced stress-corrosion cracking behavior of nuclear fuel claddings. Journal of Nuclear Materials, 376 (1). 98-107 doi:10.1016/j.jnucmat.2008.01.024

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Reference TypeJournal (article/letter/editorial)
TitleEffects of the microstructure and alloying elements on the iodine-induced stress-corrosion cracking behavior of nuclear fuel claddings
JournalJournal of Nuclear Materials
AuthorsPark, Sang YoonAuthor
Kim, Jun HwanAuthor
Lee, Myoung HoAuthor
Jeong, Yong HwanAuthor
Year2008 (May)Volume376
Issue1
PublisherElsevier BV
DOIdoi:10.1016/j.jnucmat.2008.01.024Search in ResearchGate
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Mindat Ref. ID4159543Long-form Identifiermindat:1:5:4159543:5
GUID0
Full ReferencePark, Sang Yoon, Kim, Jun Hwan, Lee, Myoung Ho, Jeong, Yong Hwan (2008) Effects of the microstructure and alloying elements on the iodine-induced stress-corrosion cracking behavior of nuclear fuel claddings. Journal of Nuclear Materials, 376 (1). 98-107 doi:10.1016/j.jnucmat.2008.01.024
Plain TextPark, Sang Yoon, Kim, Jun Hwan, Lee, Myoung Ho, Jeong, Yong Hwan (2008) Effects of the microstructure and alloying elements on the iodine-induced stress-corrosion cracking behavior of nuclear fuel claddings. Journal of Nuclear Materials, 376 (1). 98-107 doi:10.1016/j.jnucmat.2008.01.024
In(2008, May) Journal of Nuclear Materials Vol. 376 (1) Elsevier BV

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Park, Sang Yoon, Kim, Jun Hwan, Lee, Myoung Ho, Jeong, Yong Hwan (2008) Stress-corrosion crack initiation and propagation behavior of Zircaloy-4 cladding under an iodine environment. Journal of Nuclear Materials, 372 (2). 293-303 doi:10.1016/j.jnucmat.2007.03.258
Kim, Hyun Gil, Park, Sang Yoon, Lee, Myung Ho, Jeong, Yong Hwan, Kim, Sun Doo (2008) Corrosion and microstructural characteristics of Zr–Nb alloys with different Nb contents. Journal of Nuclear Materials, 373 (1). 429-432 doi:10.1016/j.jnucmat.2007.05.035
Kim, Jun Hwan, Lee, Myoung Ho, Choi, Byoung Kwon, Jeong, Yong Hwan (2007) Failure behavior of Zircaloy-4 cladding after oxidation and water quench. Journal of Nuclear Materials, 362 (1). 36-45 doi:10.1016/j.jnucmat.2006.10.026
Park, Sang Yoon, Kim, Jun Hwan, Choi, Byung Kwon, Jeong, Yong Hwan (2007) Crack initiation and propagation behavior of zirconium cladding under an environment of iodine-induced stress corrosion. Metals and Materials International, 13. 155-163 doi:10.1007/bf03027567
Kim, Jun Hwan, Lee, Myoung Ho, Jeong, Yong Hwan, Lim, Jae Gwan (2008) Behavior of zirconium fuel cladding under fast pressurization rates. Nuclear Engineering and Design, 238 (6). 1441-1447 doi:10.1016/j.nucengdes.2007.10.020
Lee, Myung Ho, Kim, Jun Hwan, Park, Sang Yoon, Choi, Byoung Kwon, Jeong, Yong Hwan (2009) The circumferential tensile properties of zirconium alloy fuel claddings under a simulated high burn-up environment. Metals and Materials International, 15. 539-546 doi:10.1007/s12540-009-0539-0
Kim, Jun Hwan, Lee, Myoung Ho, Choi, Byoung Kwon, Jeong, Yong Hwan (2007) Effect of the hydrogen contents on the circumferential mechanical properties of zirconium alloy claddings. Journal of Alloys and Compounds, 431. 155-161 doi:10.1016/j.jallcom.2006.05.074
Kim, Jun Hwan, Lee, Myoung Ho, Choi, Byoung Kwon, Jeong, Yong Hwan (2005) Embrittlement behavior of zircaloy-4 cladding during oxidation and water quench. Nuclear Engineering and Design, 235 (1). 67-75 doi:10.1016/j.nucengdes.2004.08.030
KIM, Jun Hwan, LEE, Myoung Ho, CHOI, Byoung Kwon, JEONG, Yong Hwan (2007) Deformation Behavior of Zircaloy-4 Cladding under Cyclic Pressurization. Journal of Nuclear Science and Technology, 44. 1275-1280 doi:10.1080/18811248.2007.9711371
Kim, Jun Hwan, Lee, Myoung Ho, Choi, Byoung Kwon, Jeong, Yong Hwan (2006) Effects of oxide and hydrogen on the circumferential mechanical properties of Zircaloy-4 cladding. Nuclear Engineering and Design, 236 (18). 1867-1873 doi:10.1016/j.nucengdes.2006.02.010
Jeong, Yong Hwan, Kim, Hyun Gil, Kim, Dae Jung, Choi, Byung Kwon, Kim, Jun Hwan (2003) Influence of Nb concentration in the α-matrix on the corrosion behavior of Zr–xNb binary alloys. Journal of Nuclear Materials, 323 (1). 72-80 doi:10.1016/j.jnucmat.2003.08.031
 
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