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Browsing by Author : Oh, Jae-Yong

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An extension of the two-zone method for evaluating a fission gas release under an irradiation-induced resolution flux File

Cheon, Jin-Sik , Koo, Yang-Hyun , Lee, Byung-Ho , Oh, Jae-Yong , Sohn, Dong-Seong

Article Issue Date2008-02 View199
FUEL PERFORMANCE CODE COSMOS FOR ANALYSIS OF LWR UO2 AND MOX FUEL File File

Lee, Byung-Ho , Koo, Yang-Hyun , Oh, Jae-Yong , Cheon, Jin-Sik , Tahk, Young-Wook , Sohn, Dong-Seong

Article Issue Date2011-12 View130
IRRADIATION TEST OF MOX FUEL RODS FABRICATED BY ATTRITION-MILLING AND ANALYSIS OF IN-PILE DATA WITH COSMOS CODE

Lee, Byung-Ho , Koo, Yang-Hyun , Kim, Han-Soo , Oh, Jae-Yong , Lee, Young-Woo , Sohn, Dong-Seong , Wiesenack, Wolfgang

Article Issue Date2010-10 View186
Molecular dynamics simulation of the pressure-volume-temperature data of xenon for a nuclear fuel File

Oh, Jae-Yong , Koo, Yang-Hyun , Cheon, Jin-Sik , Lee, Byung-Ho , Sohn, Dong-Seong

Article Issue Date2008-01 View89
Zircaloy-4 cladding corrosion model covering a wide range of PWR experiences File

Lee, Byung-Ho , Koo, Yang-Hyun , Oh, Jae-Yong , Sohn, Dong-Seong

Article Issue Date2008-08 View115
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