Zobrazeno 1 - 10
of 70
pro vyhledávání: '"SE-MYONG CHANG"'
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 4, Pp 1008-1016 (2019)
In the SG (steam generator) of PWR (pressurized water reactor) for a nuclear plant, hundreds of U-shaped tubes are used for the heat exchanger system. They interact with primary pressurized cooling water flow, generating flow-induced vibration in the
Externí odkaz:
https://doaj.org/article/c6d7273ceb324140905d0e0783e2fde2
Publikováno v:
Entropy, Vol 22, Iss 3, p 358 (2020)
This research focused on the correlations associated with the physics of natural convection in circular fin-tube models. The limiting conditions are defined by two conditions. The lower limit ( D o / D → 1, s/D = finite value) corresponds to a hori
Externí odkaz:
https://doaj.org/article/ec406c34fe6a4f6aa48f6236bd2b40a4
Publikováno v:
Entropy, Vol 22, Iss 3, p 363 (2020)
In this research, unsteady three-dimensional incompressible Navier−Stokes equations are solved to simulate experiments with the Boussinesq approximation and validate the proposed numerical model for the design of a circular fin-tube heat exchanger.
Externí odkaz:
https://doaj.org/article/1481531024534aa3b75180f765385f75
Publikováno v:
Applied Sciences, Vol 10, Iss 4, p 1228 (2020)
In the manufacturing process of hard-board poly-urethane foams, the uniformity is a very important issue for the raw compound of the liquid poly-urethane system flow for the quality control of such products. One of the universal methods to generate m
Externí odkaz:
https://doaj.org/article/d08dc8b3f958481dabb699273c3a2aa1
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2018 (2018)
The LOCA (loss of coolant accident) is a kind of severe accident in the operation of PHWR (pressurized heavy water reactor) as well as other nuclear facilities, and possible cause of LOCA can be counted on the ballooning of pressure tube (PT) contact
Externí odkaz:
https://doaj.org/article/213f3f6ba4de4c85b92790a345b4b61f
Autor:
Hyoung Tae Kim, Se-Myong Chang
Publikováno v:
Nuclear Engineering and Technology, Vol 47, Iss 3, Pp 284-292 (2015)
A numerical calculation with the commercial computational fluid dynamics code CFX-14.0 was conducted for a test facility simulating the Canadian deuterium uranium moderator thermal–hydraulics. Two kinds of moderator thermal–hydraulic tests at Ste
Externí odkaz:
https://doaj.org/article/d83fa52c33954d9aaf1a06a01bc3e85b
Publikováno v:
Nuclear Engineering and Technology, Vol 46, Iss 5, Pp 633-640 (2014)
In this research, the surface roughness affecting the pressure drop in a pipe used as the steam generator of a PWR was studied. Based on the CFD (Computational Fluid Dynamics) technique using a commercial code named ANSYS-FLUENT, a straight pipe was
Externí odkaz:
https://doaj.org/article/1a2aa22ec0ad41a2a73a13e74c633d81
Publikováno v:
Energies, Vol 12, Iss 21, p 4122 (2019)
In the design of wind energy farms, the loss of power should be seriously considered for the second wind turbine located inside the wake region of the first one. The rotation of the first wind-front rotor generates a high-vorticity wake with turbulen
Externí odkaz:
https://doaj.org/article/59b975bfd11c408b97dfdf580b8c6be8
Publikováno v:
Energies, Vol 12, Iss 2, p 330 (2019)
Three-dimensional moderator flow in the calandria tank of CANDU-6 pressurized heavy water reactor (PHWR) is computed with Open Field Operation and Manipulation (OpenFOAM), an open-source computational fluid dynamics (CFD) code. In this study, numeric
Externí odkaz:
https://doaj.org/article/d00cc08319be457182f7a112444d1370
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2016 (2016)
The moderator system of CANDU, a prototype of PHWR (pressurized heavy-water reactor), has been modeled in multidimension for the computation based on CFD (computational fluid dynamics) technique. Three CFD codes are tested in modeled hydrothermal sys
Externí odkaz:
https://doaj.org/article/7c6c05781be743a19be7d3a14c8c3682