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Oh, Jae Yong
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1

Proposal for the list of potential radionuclides of interes..:

Seo, Hyung-Woo ; Oh, Jae Yong ; Shin, Weon Gyu
Nuclear Engineering and Technology.  53 (2021)  1 - p. 234-243 , 2021
Link: https://doi.org/10.1016/..
 
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2

Calculation approach to building DCGLs of waste treatment f..:

Seo, Hyung-Woo ; Oh, Jae Yong ; Yu, Ji-Hwan.
Annals of Nuclear Energy.  153 (2021)  - p. 108009 , 2021
Link: https://doi.org/10.1016/..
 
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3

Redox behaviors of Fe(II/III) and U(IV/VI) studied in synth..:

Lee, Jun-Yeop ; Oh, Jae Yong ; Putri, Kirana Yuniati..
Journal of Radioanalytical and Nuclear Chemistry.  312 (2017)  2 - p. 221-231 , 2017
Link: https://doi.org/10.1007/..
 
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4

A method for fabricating a micro-structured surface of poly..:

Ma, Yong-Won ; Oh, Jae Yong ; Ahn, Seokyoung.
Journal of the Korean Physical Society.  69 (2016)  3 - p. 386-389 , 2016
Link: https://doi.org/10.3938/..
 
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5

Applicability of CeO2 as a surrogate for PuO2 in a MOX fuel..:

Kim, Han Soo ; Joung, Chang Yong ; Lee, Byung Ho...
Journal of Nuclear Materials.  378 (2008)  1 - p. 98-104 , 2008
Link: https://doi.org/10.1016/..
 
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6

Establishment of the design stress intensity value for the ..:

Kim, Hyun-Jung ; Tahk, Young-Wook ; Jun, Hyunwoo...
Nuclear Engineering and Technology.  53 (2021)  3 - p. 911-919 , 2021
Link: https://doi.org/10.1016/..
 
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7

Drop behaviors of a plate-type fuel assembly used in resear..:

Kim, Hyun-Jung ; Yim, Jeong-Sik ; Tahk, Young-Wook..
Progress in Nuclear Energy.  113 (2019)  - p. 255-262 , 2019
Link: https://doi.org/10.1016/..
 
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8

Modeling a failure criterion for U–Mo/Al dispersion fuel:

Oh, Jae-Yong ; Kim, Yeon Soo ; Tahk, Young-Wook...
Journal of Nuclear Materials.  473 (2016)  - p. 68-74 , 2016
Link: https://doi.org/10.1016/..
 
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9

Experimental study on micro-porous patterning using UV puls..:

Park, Chan ; Shin, Bo-Sung ; Kang, Moon-Suk...
International Journal of Precision Engineering and Manufacturing.  16 (2015)  7 - p. 1385-1390 , 2015
Link: https://doi.org/10.1007/..
 
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10

DROP IMPACT ANALYSIS OF PLATE-TYPE FUEL ASSEMBLY IN RESEARC..:

KIM, HYUN-JUNG ; YIM, JEONG-SIK ; LEE, BYUNG-HO..
Nuclear Engineering and Technology.  46 (2014)  4 - p. 529-540 , 2014
Link: https://doi.org/10.5516/..
 
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11

FUEL PERFORMANCE CODE COSMOS FOR ANALYSIS OF LWR UO2AND MOX..:

Lee, Byung-Ho ; Koo, Yang-Hyun ; Oh, Jae-Yong...
Nuclear Engineering and Technology.  43 (2011)  6 - p. 499-508 , 2011
Link: https://doi.org/10.5516/..
 
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12

Evaluation of the effective thermal conductivity of UO2 fue..:

Oh, Jae-Yong ; Koo, Yang-Hyun ; Lee, Byung-Ho.
Journal of Nuclear Materials.  414 (2011)  2 - p. 320-323 , 2011
Link: https://doi.org/10.1016/..
 
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13

Irradiation Test of MOX Fuel Rods Fabricated by Attrition-M..:

Lee, Byung-Ho ; Koo, Yang-Hyun ; Kim, Han-Soo...
Nuclear Technology.  172 (2010)  3 - p. 246-254 , 2010
Link: https://doi.org/10.13182..
 
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14

Artificial neural network modeling for fission gas release ..:

Koo, Yang-Hyun ; Oh, Jae-Yong ; Lee, Byung-Ho..
Journal of Nuclear Materials.  405 (2010)  1 - p. 33-43 , 2010
Link: https://doi.org/10.1016/..
 
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15

CERAMOGRAPHY ANALYSIS OF MOX FUEL RODS AFTER AN IRRADIATION..:

Kim, Han-Soo ; Jong, Chang-Yong ; Lee, Byung-Ho..
Nuclear Engineering and Technology.  42 (2010)  5 - p. 576-581 , 2010
Link: https://doi.org/10.5516/..
 
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