Zobrazeno 1 - 10
of 35
pro vyhledávání: '"MOON SUNG CHO"'
Autor:
Kyung Chai Jeong, Moon Sung Cho
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 1, Pp 175-181 (2016)
This study investigates the dispersibility of carbon in carbon contained ammonium diuranate (C-ADU) gel particles and the characteristics of C-ADU gel liquid droplets produced by the vibrating nozzle and integrated aging–washing–drying equipment.
Externí odkaz:
https://doaj.org/article/298916aa99514bc0ad21d55f698b1103
Publikováno v:
Nuclear Engineering and Technology, Vol 47, Iss 5, Pp 608-616 (2015)
The migration of silver (Ag) in silicon carbide (SiC) and 110mAg through SiC of irradiated tri-structural isotropic (TRISO) fuel has been studied for the past three to four decades. However, there is no satisfactory explanation for the transport mech
Externí odkaz:
https://doaj.org/article/87764b38759a43099a232fa6ad9409c5
Autor:
BONG GOO KIM, SUNG JAE PARK, SUNG TAEK HONG, BYUNG CHUL LEE, KYUNG-CHAI JEONG, YEON-KU KIM, WOONG KI KIM, YOUNG WOO LEE, MOON SUNG CHO, YONG WAN KIM
Publikováno v:
Nuclear Engineering and Technology, Vol 45, Iss 7, Pp 941-950 (2013)
The Korean Nuclear-Hydrogen Technology Development (NHTD) Plan will be performing irradiation testing of coated particle fuel at HANARO to support the development of VHTR in Korea. This testing will be carried out to demonstrate and qualify TRISO-coa
Externí odkaz:
https://doaj.org/article/25eb1c21680943a295d1b7f2c14fa1d9
Autor:
Kyung Chai Jeong, Moon Sung Cho
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 2, p 595 (2016)
Externí odkaz:
https://doaj.org/article/3ec7d950d3bb47ce8c6d803a196e401f
Publikováno v:
Nuclear Engineering and Design. 329:34-45
The first irradiation testing of TRISO-coated particle fuel to demonstrate and qualify its use in a VHTR was finished at the beginning of 2014 in HANARO, Korea. A PIE (post-irradiation examination) of the irradiated TRISO-coated particle fuel was the
Publikováno v:
Journal of Nuclear Materials. 499:383-393
This study investigated the anisotropic microstructural, mechanical, and thermal properties of fabricated graphite matrix prismatic compacts for High Temperature Gas Cooled Reactor (HTGR) fuel. When the observed alignment of graphite grains and the c
Publikováno v:
Journal of Korean Powder Metallurgy Institute. 23:384-390
Microstructure evolution of a ZrC coating layer in TRISO particles during high-temperature annealing
Autor:
Ji-Yeon Park, Myeong Jin Ko, Young Bum Chun, Hyeon-Geun Lee, Daejong Kim, Moon-Sung Cho, Weon-Ju Kim
Publikováno v:
Journal of Nuclear Materials. 479:93-99
The influence of high-temperature annealing on the microstructure of zirconium carbide (ZrC) was investigated in relation to its application as a coating layer of a nuclear fuel in a very high temperature gas cooled reactor. ZrC was deposited as a co
Publikováno v:
Nuclear Engineering and Technology, Vol 47, Iss 5, Pp 608-616 (2015)
The migration of silver (Ag) in silicon carbide (SiC) and 110mAg through SiC of irradiated tri-structural isotropic (TRISO) fuel has been studied for the past three to four decades. However, there is no satisfactory explanation for the transport mech
Publikováno v:
Journal of Korean Powder Metallurgy Institute. 21:434-440
【Silicon carbide(SiC) layer is particularly important tri-isotropic (TRISO) coating layers because it acts as a miniature pressure vessel and a diffusion barrier to gaseous and metallic fission products in the TRISO coated particle. The high temper