• Journal of Adhesion and Interface
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• v.20 no.3
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• pp.110-115
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• 2019

Graphene oxide has been gathering interests as a way to exfoliate graphene. Since the oxidation group of graphene oxide can hydrogen bond with various functional groups, tremendous efforts have been actively conducted to apply various applications. However, graphene oxide alone cannot substantially possess the mechanical properties required for the practical application. Therefore, in this study, polydopamine, which is a bio-mimetic mussel protein-inspired material, was combined with graphene oxide to form a large-area composite membrane at the liquid-gas interface. In addition, the morphology of the polydopamine-graphene oxide composite thin film was also controlled to obtain a composite membrane having a nano-wrinkle structure. It can be expected to be used in the next generation seawater desalination membranes or carbon composites because it can form mechanically superior and sophisticated nanostructures.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.74-79
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• 1997

$UO_2$ 및 $UO_2$-3.23wt%CeO$_2$가 128$0^{\circ}C$에서 소결되면 밀도는 각각 93%T.D., 91.2%T.D.이었으나, Li$_2$O가 0.lwt%씩 첨가된 경우에는 소결밀도가 95.5%T.D., 95.1%T.D.로 증가하였다. 소결온도가 증가함에 따라서 $UO_2$ 및 $UO_2$-3.23wt%CeO$_2$의 소결밀도는 현저하게 증가되는 반면에, Li$_2$O가 첨가된 경우에는 저온에서도 이미 치밀화가 많이 일어났기 때문에 소결밀도의 증가폭이 완만하였다. Li$_2$O가 첨가된 분말에서는 소결온도가 더 높아지면, 결정립성장이 주로 일어나게 되어 168$0^{\circ}C$에서 소결되었을 때, $UO_2$와 $UO_2$-0.1wt%Li$_2$O의 결정립크기가 각각 8.7$\mu\textrm{m}$, 120$\mu\textrm{m}$ 이고, $UO_2$-3.23wt%CeO$_2$와 $UO_2$-3.23wt%CeO$_2$-0.lwt%Li$_2$O는 각각 10.9$\mu\textrm{m}$, 34$\mu\textrm{m}$ 이었다. $UO_2$와 $UO_2$-3.23wt%CeO$_2$ 그리고, 두 조성에 Li$_2$O가 각각 첨가된 경우, Ar-4vol.%H$_2$ 분위기보다 H$_2$분위기에서 소결했을 때 밀도가 더 높았다. 그러나, 결정립은 $UO_2$와 $UO_2$-Li$_2$O의 경우, 수소분위기에서 소결했을 때, (U,Ce)O$_2$와 (U,Ce)O$_2$-Li$_2$O에서는 Ar-4vol.%H$_2$분위기에서 소결했을 때 더욱 성장하였다.

• Proceedings of the KSME Conference
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• 2007.05b
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• pp.2244-2249
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• 2007

A directly heated $SO_3$ decomposer for the sulfur-iodine and hybrid-sulfur processes has been introduced and analyzed by using a computational fluid dynamics code(CFD) with the CFX 5.7.1. The use of a directly heated decomposition reactor in conjunction with a VHTR allows higher decomposition reactor operating temperature. However, the thermochemical and hybrid hydrogen production processes accompanied with the high temperature and strongly corrosive operating conditions basically have material problems. In order to resolve these problems, we carried out the development of a structural material and equipment design technologies. The results show that the maximum temperature of the structural material (RA330) could be maintained at 800$^{\circ}C$ or less. Also, it can be seen that the mean temperature of the reaction region packed with catalysts in the $SO_3$ decomposition reactor could satisfy the temperature condition of around 850 $^{\circ}C$ which is the target temperature in this study.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.7 no.2
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• pp.1-6
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• 2011

PHE(Process Heat Exchanger) is a key component required to transfer heat energy of $950^{\circ}C$ generated in a VHTR(Very High Temperature Reactor) to the chemical reaction that yields a large quantity of hydrogen. Korea Atomic Energy Research Institute established a small-scale gas loop for the performance test of components, which are used in the VHTR, and they manufactured a PHE prototype made of Hastelloy-X to be tested in the small-scale gas loop. Results from the elastic structural analysis on the PHE prototype were reported in the previous article. In order to investigate the macroscopic structural characteristics and behavior of the PHE prototype under the test condition of the small-scale gas loop far more in detail, elastic-plastic high-temperature structural-analysis of the PHE prototype was carried out in this study.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.33 no.10
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• pp.1108-1118
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• 2009

A Very High Temperature Gas Cooled Reactor (VHTR) has been selected as a high energy heat source of the order of $950^{\circ}C$ for nuclear hydrogen generation, which can produce hydrogen from water or natural gas. A primary hot gas duct (HGD) as a coaxial double-tube type cross vessel is a key component connecting a reactor pressure vessel and an intermediate heat exchanger in the VHTR. In this study, a structural sizing methodology for the primary HGD of the VHTR is suggested in order to modulate a flow-induced vibration (FIV). And as an example, a structural sizing of the horizontal HGD with a coaxial double-tube structure was carried out using the suggested method. These activities include a decision of the geometric dimensions, a selection of the material, and an evaluation of the strength of the coaxial double-tube type cross vessel components. Also in order to compare the FIV characteristics of the proposed design cases, a fluid-structure interaction (FSI) analysis was carried out using the ADINA code.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.8 no.1
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• pp.33-38
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• 2012

A PHE (Process Heat Exchanger) in a nuclear hydrogen system is a key component required to transfer heat energy of $950^{\circ}C$ generated in a VHTR (Very High Temperature Reactor) to a chemical reaction that yields a large quantity of hydrogen. Korea Atomic Energy Research Institute has established a small-scale gas loop for the performance test on VHTR components and recently has manufactured a medium-scale PHE prototype made of Hastelloy-X. A performance test on the PHE prototype is scheduled in the gas loop. In this study, high-temperature structural analysis modeling, and macroscopic thermal and structural analysis of the medium-scale PHE prototype by imposing the established displacement boundary constraints in the previous research were carried out under the gas loop test condition. The results obtained in this study will be compared with performance test results.

• Nuclear Engineering and Technology
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• v.21 no.4
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• pp.332-340
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• 1989

Destructive examination of 14$\times$14 PWR fuel burned for 3 cycles are carried out to investigate the in-reactor fuel performance. The results obtained are as follows; 1) Grain growth is not occured at the fuel center. 2) Fuel density is decreased as the turnup increase, the density is down to 94.4% TD at burnup of 36,000 MWD/MTU. 3) Average thickness of oxide layer on cladding is less than 10 $\mu$m in the lower and middle section, while it is rapidly increased above 20 $\mu$m in the upper section. 4) The rate of hydride production in the cladding is large in the upper section than lower section and is related to the production of oxide on the cladding

• Journal of the Korean Society of Marine Environment & Safety
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• v.5 no.1
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• pp.47-58
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• 1999

Polycyclic aromatic hydrocarbons (PAHs) are ubiquitous contaminants in coastal marine environment. PAHs enter estuarine and nearshore marine environment via several routes such as combustion of fossil fuels, domestic and industrial effluents and oil spills. In August of 1997, sediment and mussels (Mytilus edulis) were collected at 6 sites near Kori nuclear power plant in order to analyze the PAH content by HPLC with uv/vis detection. The concentrations of 15 PAH in sediment ranged from < 1 to 5,900 ppb ( mean 173.5$\pm$99.7 ppb), and in mussels, from < 0.5 to 4,125 ppb (mean 105$\pm$60.5 ppb). Compared with other studies world over, the concentrations of carcinogenic PAHs were relatively low in both sediment and mussels from the intertidal zone of Kori. This study presents preliminary data for the PAH levels in sediment and mussels from the intertidal zone of Kori, and the data will hopefully be utilized for the assessment of oil pollution in the Southeast East Sea, Korea (especially for the PAHs).

• Nuclear Engineering and Technology
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• v.20 no.4
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• pp.246-252
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• 1988

Experiments on the hydrogen gas breakdown for plasma initiation in the KAERIT tokamak are described. The influence of the applied loop voltage, toroidal magnetic field, gas filling pressure, error magnetic field, and preionization is studied. It is concluded that the magnitude of the error field is the most important factor for successful discharge initiation. The gas breakdown voltage becomes minumum when the external compensating field most effectively corrects the net error field. Even though preionization effect is not prominent, it is exhibited more easily in the case of worse confinement. Discharge initiation conditions experimentally determined are compared with those calcuated from a theoretical model. Some other unknown physical processes maintain the operation range somewhat narrower than predicted by the present theoretical model. However, this model is adequate for the breakdown phase of tokamaks.

• Nuclear Engineering and Technology
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• v.4 no.1
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• pp.39-45
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• 1972

In neutron shielding, the scattering effect is equally important as the attenuations in shielding materials. In the present study, the scattered dose equivalent was measured using a Rem counter for water, paraffin, borated paraffin, ordinary and heavy concrete, lead, iron, and tissue equivalent material in three different angles: 45$^{\circ}$, 90$^{\circ}$, and 135$^{\circ}$, respectively. The measurements were performed for the neutron, having the energies of 0.5, 1, 2, 5, and 18 MeV, which are produced from the Van do Graaff accelerator. The scattered dose equivalent ratios were increased with increasing the thickness of scattering materials and saturated at a certain thickness although they were different from one to other materials under study. The ratios were large for lead and iron while they were small for the hydrogen containing materials such as water and paraffin etc.