Zobrazeno 1 - 10
of 17
pro vyhledávání: '"Dong Jun Park"'
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 10, Pp 2299-2305 (2020)
Zr alloy specimens were coated with Cr–Al alloy to enhance their resistance to oxidation. The coated samples were oxidized at 1200 °C in a steam environment for 300 s and showed extremely low oxidation when compared to uncoated Zr alloy specimens.
Autor:
Jung Hwan Park, Hyung-Il Kim, Byoung-Kwon Choi, Il-Hyun Kim, Yang-Il Jung, Young-Ho Lee, Dong-Jun Park
Publikováno v:
Journal of Nuclear Materials. 523:223-230
For enhancing accident tolerance in current operating LWRs, Zr-based claddings with a protective layer, which have outstanding resistance to high-temperature oxidation, are selected as strong candidates for accident-tolerant fuel claddings. One of th
Autor:
Jae Ho Yang, Byoung Kwon Choi, Yang-Il Jung, Yang-Hyun Koo, Dong Jun Park, Hyun-Gil Kim, Jung Hwan Park
Publikováno v:
Fusion Engineering and Design. 139:81-85
In the present work, oxide dispersion is used to improve the high-temperature strength of FeCrAl alloys, which have excellent high-temperature oxidation resistance. Laser-beam scanning is introduced as a new method for manufacturing oxide-dispersion-
Autor:
Young-Ho Lee, Yang-Il Jung, Il-Hyun Kim, Hyun Gil Kim, Byung-Kwon Choi, Dong-Jun Park, Jung-Hwan Park
Publikováno v:
Journal of Nuclear Materials. 510:93-99
ATF claddings are defined as those that provide considerably increased response time in the event of a reactor accident while providing performance similar to or better than that of the commercial zirconium (Zr) cladding during normal operation. Surf
Autor:
Il-Hyun Kim, Dong-Jun Park, Jung-Hwan Park, Yang-Il Jung, Jae Ho Yang, Hyun-Gil Kim, Yang-Hyun Koo
Publikováno v:
Additive Manufacturing. 22:75-85
To increase the mechanical strength of Zircaloy-4 cladding at high temperatures, partial oxide dispersion-strengthened (ODS) treatment of the cladding tube surface was achieved by using laser processing technology. The microstructural characteristics
Publikováno v:
Journal of Nuclear Materials. 504:261-266
FeCrAl and Mo layers were cold-sprayed onto a Zr surface, with the Mo layer introduced between the FeCrAl coating and the Zr matrix preventing high-temperature interdiffusion. Microstructural characterization of the first-deposited Mo layer and the Z
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 2, Pp 218-222 (2018)
An oxide-dispersion-strengthened (ODS) layer was formed on Zircaloy-4 tubes by a laser beam scanning process to increase mechanical strength. Laser beam was used to scan the yttrium oxide (Y2O3)–coated Zircaloy-4 tube to induce the penetration of Y
Autor:
Jung Hwan Park, Hwan-Uk Guim, Yoon-Soo Lim, Jae Ho Yang, Hyung-Il Kim, Yang-Il Jung, Dong-Jun Park
Publikováno v:
Applied Surface Science. 429:272-277
Zircaloy-4 is a traditional zirconium-based alloy developed for application in nuclear fuel cladding tubes. The surfaces of Zircaloy-4 tubes were treated using a laser beam to increase their mechanical strength. Laser beam scanning of a tube coated w
Autor:
Hyun-Gil Kim, Jung-Hwan Park, Yang-Hyun Koo, Jae Ho Yang, Yang-Il Jung, Dong-Jun Park, Sun-Han Kim, Il-Hyun Kim
Publikováno v:
Materials & Design, Vol 116, Iss, Pp 325-330 (2017)
The mechanical strength of Zircaloy-4 was enhanced by surface treatment consisting of laser beam scanning of an oxide-coated Zircaloy-4 sheet. An yttrium oxide (Y2O3) coating 7–55 μm thick was applied to Zircaloy-4 sheets. Then, a laser beam was u
Autor:
Jung Hwan Park, Dong Won Lee, Seungyon Cho, Byoung-Kwon Choi, Jeong-Yong Park, Dong-Jun Park, Suk-Kwon Kim, Yang-Il Jung, Hyun-Gil Kim, Jung-Suk Lee
Publikováno v:
Fusion Engineering and Design. :448-453
Joining technology for dissimilar materials was developed for the fabrication of an ITER blanket first-wall, which consisted of Be, CuCrZr, and stainless steel (SS). The Be/CuCrZr/SS joint was fabricated using a hot isostatic pressing (HIP) method. B