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Hur, Do Haeng, Lee, Deok Hyun, Choi, Myung Sik, Song, Myung Ho, Han, Jung Ho (2008) Root causes of intergranular attack in an operating nuclear steam generator tube. Journal of Nuclear Materials, 375 (3). 382-387 doi:10.1016/j.jnucmat.2008.01.017

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Reference TypeJournal (article/letter/editorial)
TitleRoot causes of intergranular attack in an operating nuclear steam generator tube
JournalJournal of Nuclear Materials
AuthorsHur, Do HaengAuthor
Lee, Deok HyunAuthor
Choi, Myung SikAuthor
Song, Myung HoAuthor
Han, Jung HoAuthor
Year2008 (April)Volume375
Issue3
PublisherElsevier BV
DOIdoi:10.1016/j.jnucmat.2008.01.017Search in ResearchGate
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Mindat Ref. ID4159527Long-form Identifiermindat:1:5:4159527:7
GUID0
Full ReferenceHur, Do Haeng, Lee, Deok Hyun, Choi, Myung Sik, Song, Myung Ho, Han, Jung Ho (2008) Root causes of intergranular attack in an operating nuclear steam generator tube. Journal of Nuclear Materials, 375 (3). 382-387 doi:10.1016/j.jnucmat.2008.01.017
Plain TextHur, Do Haeng, Lee, Deok Hyun, Choi, Myung Sik, Song, Myung Ho, Han, Jung Ho (2008) Root causes of intergranular attack in an operating nuclear steam generator tube. Journal of Nuclear Materials, 375 (3). 382-387 doi:10.1016/j.jnucmat.2008.01.017
In(2008, April) Journal of Nuclear Materials Vol. 375 (3) Elsevier BV

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Hur, Do Haeng, Choi, Myung Sik, Lee, Deok Hyun, Song, Myung Ho, Kim, Seon Jin, Han, Jung Ho (2004) Effect of shot peening on primary water stress corrosion cracking of Alloy 600 steam generator tubes in an operating PWR plant. Nuclear Engineering and Design, 227 (2). 155-160 doi:10.1016/j.nucengdes.2003.09.002
Hur, Do Haeng, Choi, Myung Sik, Lee, Deok Hyun, Han, Jung Ho, Shim, Hee Sang (2013) Corrosion inhibition of steam generator tubesheet by Alloy 690 cladding in secondary side environments. Journal of Nuclear Materials, 442 (1). 326-329 doi:10.1016/j.jnucmat.2013.09.023
Lee, Deok Hyun, Choi, Myung Sik, Hur, Do Haeng, Han, Jung Ho, Song, Myung Ho, Lee, Un Chul (2006) A New Eddy Current 3-D Profilometry for a Quantitative Measurement of Geometric Anomaly in Steam Generator Tubes of Nuclear Power Plants. Key Engineering Materials, 321. 426-429 doi:10.4028/www.scientific.net/kem.321-323.426
Kim, Gyung Guk, Kim, Ji Hui, Lee, Kwon Yeong, Kim, Seon Jin, Lee, Deok Hyun, Hur, Do Haeng, Choi, Myung Sik, Han, Jung Ho (2005) Sliding Wear Behavior of Steam Generator Tube Materials in Nuclear Power Plants. Materials Science Forum, 486. 137-140 doi:10.4028/www.scientific.net/msf.486-487.137
Lee, Deok Hyun, Choi, Myung Sik, Hur, Do Haeng, Han, Jung Ho, Lee, Un Chul (2004) Development of an ECT Technique for Discriminating between a Through-Wall/Non Through-Wall Crack in a Steam Generator Tube. Key Engineering Materials, 270. 600-605 doi:10.4028/www.scientific.net/kem.270-273.600
Hur, Do Haeng, Choi, Myung Sik, Lee, Deok Hyun, Kim, Seon Jin, Han, Jung Ho (2010) A case study on detection and sizing of defects in steam generator tubes using eddy current testing. Nuclear Engineering and Design, 240 (1). 204-208 doi:10.1016/j.nucengdes.2009.10.006
Song, Sung Jin, Kim, Chang Hwan, Lee, Deok Hyun, Choi, Myung Sik, Hur, Do Haeng, Han, Jung Ho (2005) An Automated System for Detection of Through-Wall Cracks in Racks in Steam Generator Tubes. Key Engineering Materials, 297. 2071-2076 doi:10.4028/www.scientific.net/kem.297-300.2071
Kim, Gyung Guk, Noh, Seung Dae, Park, Gi Sung, Kim, Seon Jin, Lee, Deok Hyun, Hur, Do Haeng, Choi, Myung Sik, Han, Jung Ho (2006) Sliding Wear Behaviors of Steam Generator Tubes in Various Environments. Materials Science Forum, 510. 566-569 doi:10.4028/www.scientific.net/msf.510-511.566
Shim, Hee-Sang, Choi, Myung Sik, Lee, Deok Hyun, Hur, Do Haeng (2016) A prediction method for the general corrosion behavior of Alloy 690 steam generator tube using eddy current testing. Nuclear Engineering and Design, 297. 26-31 doi:10.1016/j.nucengdes.2015.11.015
Hur, Do Haeng, Choi, Myung Sik, Kim, Uh Chul, Han, Jung Ho (2003) Magnetite dissolution and corrosion behavior in high temperature EDTA solvents. Nuclear Engineering and Design, 220 (1). 11-16 doi:10.1016/s0029-5493(02)00252-2
Jeon, Soon-Hyeok, Hong, Seokmin, Kwon, Hyuk-Chul, Hur, Do Haeng (2018) Characteristics of steam generator tube deposits in an operating pressurized water reactor. Journal of Nuclear Materials, 507. 371-380 doi:10.1016/j.jnucmat.2018.05.001
 
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