Zobrazeno 1 - 10
of 48
pro vyhledávání: '"Kyung Doo Kim"'
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 11, Pp 4322-4328 (2022)
The two-fluid model is widely used to describe two-phase flows in complex systems such as nuclear reactors. Although the two-phase flow was successfully simulated, the standard two-fluid model suffers from an ill-posed nature. There are several remed
Externí odkaz:
https://doaj.org/article/7c40d8fb2858424f8a7025e96b432ac9
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 6, Pp 1504-1513 (2019)
Recently, ocean nuclear reactors have received attention due to enhanced safety features. The movable and transportable characteristics distinguish ocean nuclear reactors from land-based nuclear reactors. Therefore, for safety/design analysis of the
Externí odkaz:
https://doaj.org/article/583dd615e289419ab973655bbf8ad4d3
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 3, Pp 379-388 (2018)
Models for the rate of atomization and deposition of droplets for stratified and annular flow in horizontal pipes are presented. The entrained fraction is the result of a balance between the rate of atomization of the liquid layer that is in contact
Externí odkaz:
https://doaj.org/article/2aa4fbddddf34f8eb0f522c26d0b7568
Publikováno v:
Nuclear Engineering and Technology, Vol 47, Iss 4, Pp 416-423 (2015)
It had been disputed how to apply wall drag to the dispersed phase in the framework of the conventional two-fluid model for two-phase flows. Recently, Kim et al. [1] introduced the volume-averaged momentum equation based on the equation of a solid/fl
Externí odkaz:
https://doaj.org/article/f3da7bb5a55d432d8f91a3394283706b
Publikováno v:
Nuclear Engineering and Technology, Vol 46, Iss 5, Pp 619-632 (2014)
The Best Estimate Plus Uncertainty (BEPU) method has been widely used to evaluate the uncertainty of a best-estimate thermal hydraulic system code against a figure of merit. This uncertainty is typically evaluated based on the physical model's uncert
Externí odkaz:
https://doaj.org/article/2778452bbb43408c890fe821baa06959
Publikováno v:
Nuclear Engineering and Technology, Vol 46, Iss 5, Pp 719-724 (2014)
During the development process of a thermal-hydraulic system code, a non-regression test (NRT) must be performed repeatedly in order to prevent software regression. The NRT process, however, is time-consuming and labor-intensive. Thus, automation of
Externí odkaz:
https://doaj.org/article/ae28860ed67241c486bf673b8cf6f9c7
Autor:
Nguyen Huu Tiep, Kyung-Doo Kim, Hae-Yong Jeong, Nguyen Xuan-Mung, Van-Khanh Hoang, Nguyen Ngoc Anh, Mai The Vu
Publikováno v:
Applied Sciences, Vol 14, Iss 1, p 324 (2023)
The reflooding phase, a crucial recovery process after a loss of coolant accident (LOCA) in reactors, involves cooling overheated fuel rods with subcooled water. Its complex nature, notably in its flow regime and heat transfer, makes prediction chall
Externí odkaz:
https://doaj.org/article/30065c8e219b48adb9dbbb55311bd641
Publikováno v:
SSRN Electronic Journal.
Publikováno v:
Annals of Nuclear Energy. 133:122-128
The flow regime for two-phase flow plays an important role in nuclear safety analysis, because different physical models for two-phase flow are used depending on the flow regime. This paper deals with the flow regime criteria for horizontal stratific
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 6, Pp 1504-1513 (2019)
Recently, ocean nuclear reactors have received attention due to enhanced safety features. The movable and transportable characteristics distinguish ocean nuclear reactors from land-based nuclear reactors. Therefore, for safety/design analysis of the