Zobrazeno 1 - 10
of 40
pro vyhledávání: '"Yong-Sik Yang"'
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 3, Pp 614-620 (2020)
In a previous study, delayed hydride cracking (DHC) assessment of pressurized water reactor (PWR) spent fuel during dry storage using the threshold stress intensity factor (KIH) was performed. However, there were a few limitations in the analysis of
Externí odkaz:
https://doaj.org/article/c38a1ed7d55d493d8376619d674db3d8
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 3, Pp 614-620 (2020)
In a previous study, delayed hydride cracking (DHC) assessment of pressurized water reactor (PWR) spent fuel during dry storage using the threshold stress intensity factor (KIH) was performed. However, there were a few limitations in the analysis of
Publikováno v:
Annals of Nuclear Energy. 175:109217
Publikováno v:
Nuclear Technology. 203:282-292
One of the limiting mechanisms of pressurized water reactor spent fuel cladding is creep owing to high temperature and rod internal pressure. Based on extensive studies, many countries have tentatively concluded that creep rupture is hard to occur un
Publikováno v:
Nuclear Engineering and Design. 322:324-330
One of the possible degradation mechanisms of PWR spent fuel cladding is delayed hydride cracking (DHC), which can activate within a relatively low temperature range. Due to the high crack growth rate, it is essential to prevent DHC crack growth, but
Publikováno v:
Journal of Nuclear Materials. 492:253-259
Temperature and hoop stress limits have been used to prevent the gross rupture of spent nuclear fuel during dry storage. The stress due to rod internal pressure can induce cladding degradation such as creep, hydride reorientation, and delayed hydride
Publikováno v:
Nuclear Engineering and Design. 318:61-71
In order to evaluate the PCMI (pellet-to-cladding mechanical interaction) behavior in fuel rods, a three-dimensional finite element (FE) module, termed NUFORM3D, was developed by KAERI. In the NUFORM3D module, a thermo-mechanical model considering el
Publikováno v:
Transactions of the Korean Society of Mechanical Engineers A. 40:437-447
Publikováno v:
Journal of the Korean Society for Precision Engineering. 33:279-286
To enhance the safety of nuclear reactors after the Fukushima accident, researchers are developing various types of accident tolerant fuel (ATF) to increase the coping time and reduce the generation of hydrogen by oxidation. Coated cladding, an ATF c