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AbstractAbstract
[en] New poly(arylene ether)s (PAEs) with both transparency and heat-resistance were prepared by a polycondensation of FBPODS, an ordered-sequence aromatic dihalide, and cardo typed aromatic diols containing fluorene and/or adamantane moiety and also non-cardo typed 1,5-naphthalene diol. The resulting polymers had their glass transition temperatures ranged from 202 to 247 .deg. C. Based on TGA data, they exhibited excellent thermal stabilities, showing 5% weight loss at 434-487 .deg. C. They had low thermal expansion coefficients of 58-59 ppm at temperature range of 50-200 .deg. C as well as good mechanical properties with moduli of 1757-2143 MPa. The optical transmittance for the PAE films was over 70% at 550 nm, except for the PAE that contains naphthalene moiety (30% at 550 nm). They also showed water uptake of about 0.68% regardless of their chemical compositions. Therefore, the newly developed PAEs show strong potential as plastic substrates for flexible devices for display, solar cell and e-paper
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21 refs, 4 figs, 3 tabs
Record Type
Journal Article
Journal
Bulletin of the Korean Chemical Society; ISSN 0253-2964; ; v. 32(9); p. 3311-3316
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AbstractAbstract
[en] In the winter of 2012, several cracks were detected in the penetration nozzles of the reactor pressure vessel closure head in a pressurized water reactor in Korea. Primary water stress corrosion cracking in the CRDM penetration nozzle is usually initiated due to a combination of a particular alloy, temperature, boric acid and weld residual stress. Garud et al. suggested an empirical equation for PWSCC initiation time based on a strain rate damage model. In this study, the authors introduce a user subroutine to apply Garud’s simplified SRDM model and XFEM to simulate PWSCC crack initiation location and growth. The suggested model includes a new algorithm to track cracks and update crack domains by simulating primary water contact conditions. A finite element model of the CRDM penetration nozzle were constructed to simulate such phenomena. Only one quarter of the nozzle were modeled because of its geometrical symmetry. In order to calculate the welding residual stress, a heat transfer analysis with a model change function followed by a thermal stress analysis were performed. Adopting the calculated welding residual stress as initial condition, the PWSCC crack initiation and propagation analysis were done for over 11 cycles of normal operating conditions. After 11 cycles of normal operation, the crack depth and length were measured and compared with the reported cracks from operating nuclear power plants in Korea. A comparison of PWSCC driving force among hoop stress, von Mises stress and maximum principal stress were investigated. Also a comparison of PWSCC dimension between two different Alloy 600 material conditions (MA, CW) were investigated.
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Source
26 refs, 9 figs, 4 tabs
Record Type
Journal Article
Journal
Journal of Mechanical Science and Technology; ISSN 1738-494X; ; v. 31(11); p. 5387-5395
Country of publication
ALLOY-NI76CR15FE8, ALLOYS, ALUMINIUM ADDITIONS, ALUMINIUM ALLOYS, CHEMICAL REACTIONS, CHROMIUM ALLOYS, CONTAINERS, CORROSION, CORROSION RESISTANT ALLOYS, DECOMPOSITION, ENRICHED URANIUM REACTORS, HEAT RESISTANT MATERIALS, HEAT RESISTING ALLOYS, INCONEL ALLOYS, IRON ALLOYS, MATERIALS, NICKEL ALLOYS, NICKEL BASE ALLOYS, NIMONIC, NUCLEAR FACILITIES, OPERATION, POWER PLANTS, POWER REACTORS, PYROLYSIS, REACTOR LIFE CYCLE, REACTORS, STRESSES, THERMAL POWER PLANTS, THERMAL REACTORS, THERMOCHEMICAL PROCESSES, TITANIUM ADDITIONS, TITANIUM ALLOYS, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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AbstractAbstract
[en] An advancement can be seen in ultra-thin coatings used for the enhancement of material durability and lifespan. Among candidate materials, copper is used in various applications, such as micro sensors, nuclear fuel waste deposition canisters, and International Thermonuclear Experimental Reactor first walls. However, it is easily susceptible to metal creep, due to its exposure to harsh environments. In this study, graphene, a promising ultra-thin material, is tested as a single-layer coating substance used to enhance the creep property of copper. For measuring creep life, the small punch creep test methodology is adopted. Results show that, remarkably, the creep lifetime of copper increases by up to 19 % with the use of the graphene coating. In testing, the heat-treated copper specimen without graphene was fractured at 45 hours, while the graphene-coated copper specimen was fractured at 55.4 hours. The finite element method also supports the experimental results obtained.
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Secondary Subject
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40 refs, 7 figs, 1 tab
Record Type
Journal Article
Journal
Journal of Mechanical Science and Technology; ISSN 1738-494X; ; v. 33(5); p. 2085-2091
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AbstractAbstract
[en] Elastic network-based normal mode analyses (EN-NMA) of four pairs of open-closed proteins (Lactoferrin, Maltodextrin-binding protein, LAO-binding protein, and Adenylate kinase) were conducted using both all-atom and coarse-grained models. The results indicated that the performance of the all-atom model was similar to that of the coarse-grained model in terms of predicting the conformational changes of backbones. Moreover, dynamic behavior was examined by studying relative atomic displacements and shapes of the dominant mode. For instance, for Maltodextrin-binding protein, the results from the all-atom model differed from those of the coarse-grained model, especially for residues that are biologically relevant. The coarse-grained model has better computational efficiency than the allatom model. However, the former may misrepresent the key dynamics of a protein related to biological functions as a consequence of excessive coarse approximation. Considering that the current power even in a high-end personal computer is sufficient to handle most of protein structures with up to 1,000 residues in a reasonable manner, which can only be used with supercomputers a few decades ago, an all-atom-based EN-NMA may deserve more attention as a reliable and powerful computational tool for protein dynamics study over the conventional coarse-graining approach.
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56 refs, 10 figs, 3 tabs
Record Type
Journal Article
Journal
Journal of Mechanical Science and Technology (Online); ISSN 1976-3824; ; v. 27(11); p. 3267-3275
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AbstractAbstract
[en] The residual stress is the key factor causing the reliability problem of thermal barrier coating (TBC). The failure of plasma spray coatings due to residual stresses is a serious and recurring problem of TBC. The difference of thermal expansion coefficient between the substrate and each coating combined with temperature evolution and temperature gradients during deposition process determine the residual stress for the whole TBC system. The magnitudes and distributions of the residual stresses are affected by deposition process and deposition characteristics. Most of FEA (finite element analysis) has been performed under the assumption that the multilayer coating system is stacked at once without considering the deposition process during plasma spraying. In this research, FEA for a coupled heat transfer and elastic-plastic thermal stress was performed to obtain the more detailed and reliable result of residual stress of the TBC system using the element activation/deactivation technique. The residual stress variation from the start of plasma spraying to cooling stage with room temperature was obtained systematically considering the deposition process. It can be used as reference data to improve the performance of TBC. In addition, the relationship between residual stress and coating conditions such as cooling rate and time is also examined thoroughly.
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Source
38 refs, 9 figs, 1 tab
Record Type
Journal Article
Journal
Journal of Mechanical Science and Technology (Online); ISSN 1976-3824; ; v. 28(6); p. 2161-2168
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AbstractAbstract
[en] New advanced materials have received more attention from many scientists and engineers because of their outstanding chemical, electrical, thermal, optical, and mechanical properties. Since the design of advanced material by experiments requires high cost and time, numerical approaches have always been of great interest. In this paper, finite element analysis of anisotropic material behavior has been carried out based on a multiresolution continuum theory. Gurson Tvergaard Needleman (GTN) damage model has been applied as a constitutive model at macroscale. Effects of plastic anisotropy on deformation behavior are assessed using Hill's 48 yield function for anisotropic material and von Mises yield function for isotropic material, respectively. The material parameters for both isotropic and anisotropic damage models have systematically been determined from microstructure through unit cell modeling. The newly proposed linear approximation of local velocity gradient resolved the underdetermined problem of the previous homogenization process. Anisotropic material behaviors of a tensile specimen have been investigated by the proposed multiresolution continuum theory
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Source
15 refs, 5 figs
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Journal Article
Journal
Journal of Mechanical Science and Technology; ISSN 1738-494X; ; v. 26(9); p. 2863-2868
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[en] Currently, the Republic of Korea operates a total of 28 nuclear power plants, including those under construction. Although every part of a nuclear power plant is important for safe operation, most attention is paid to the nuclear fuel assembly. The assembly is divided into fuel rods containing fuel assembly fuel and spacer grids. The spacer grid is an important component for core cooling by keeping the fuel rods protected and spaced apart. The spacer grid is produced from a strap bar, which is the base plate, and by spot welding eight edges of the strap bar. However, the spot welding machine has a large capacity and power supply such that the welding quality varies depending on the weld metal and surface conditions. As a result, the welding point may be defective. Therefore, this study aims to analytically verify the performance of a newly designed spacer grid for metal 3D AM as well as present analytical criteria for product development
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Secondary Subject
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19 refs, 10 figs, 2 tabs
Record Type
Journal Article
Journal
Journal of Mechanical Science and Technology (Online); ISSN 1976-3824; ; v. 36(1); p. 297-303
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AbstractAbstract
[en] Although it is widely known that both size and chirality play significant roles in vibration behaviors of single walled carbon nanotubes (SWCNTs), there haven't been yet enough studies specifying the relationship between structure and vibration mode shape of SWCNTs. We have analyzed the chirality and length dependence of SWCNT by using normal mode analysis based elastic network model in which all interatomic interactions of the given SWCNTs structure are represented by a network of linear spring connections. As this method requires relatively short computation time compared to molecular dynamics simulation, we can efficiently analyze vibration behavior of SWCNTs. To ensure the relationship between SWCNT structure and its vibration mode shapes, we simulated more than one hundred SWCNTs having different types of chirality and length. Results indicated that the first two major mode shapes are bending and breathing. The minimum length of nanotube for maintaining the bending mode does not depend on chirality but on its diameter. Our simulations pointed out that there is a critical aspect ratio between diameter and length to determine vibration mode shapes, and it can be empirically formulated as a function of nanotube length and diameter. Therefore, uniformity control is the most important premise in order to utilize vibration features of SWCNTs. It is also expected that the obtained vibration aspect will play an important role in designing nanotube based devices such as resonators and sensors more accurately
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Source
35 refs, 5 figs, 2 tabs
Record Type
Journal Article
Journal
Journal of Mechanical Science and Technology; ISSN 1738-494X; ; v. 26(11); p. 3433-3438
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AbstractAbstract
[en] To ensure the safety margin of a reactor pressure vessel (RPV) under normal operating conditions, it is regulated through the pressure-temperature (P-T) limit curve. The stress intensity factor (SIF) obtained by the internal pressure and thermal load should be obtained through crack analysis of the nozzle corner crack in advance to generate the P-T limit curve for the nozzle. In the ASME code Section XI, Appendix G, the SIF via the internal pressure for the nozzle corner crack is expressed as a function of the cooling or heating rate, and the wall thickness, however, the SIF via the thermal load is presented as a polynomial format based on the stress linearization analysis results. Inevitably, the SIF can only be obtained through finite element (FE) analysis. In this paper, simple prediction equations of the SIF via the thermal load under, cool-down and heat-up conditions are presented. For the Korean standard nuclear power plant, three geometric variables were set and 72 cases of RPV models were made, and then the heat transfer analysis and thermal stress analysis were performed sequentially. Based on the FE results, simple engineering solutions predicting the value of thermal SIF under cool-down and heat-up conditions are suggested
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14 refs, 14 figs, 5 tabs
Record Type
Journal Article
Journal
Nuclear Engineering and Technology; ISSN 1738-5733; ; v. 54(6); p. 2188-2197
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[en] Thermal fatigue cracking induced by thermal stratification, cycling and striping have been observed in several PWR plants. Especially, thermal striping, the highly fluctuating thermal layer, became one of the significant problems, since it can cause un predicted high cycle thermal fatigue (HCTF) at piping systems. This problem are usually found in T junctions of energy cooling systems, where cold and hot flows with high level of turbulence mix together. Thermal striping can cause the networks of fatigue crack at the vicinity of weld parts and these cracks can propagate to significant depth in a relatively short time. Therefore, thermal striping and fatigue crack initiations should be predicted in advance to prevent the severe failure of piping systems. The final goal of this research is to develop a rational thermal and mechanical model considering thermohydraulic characteristics of thermal striping and an evaluation procedure to predict the initiation of thermal fatigue crack. As a first step, we evaluated the fatigue damage in a T junction using two widely used methods. Then, we analyzed the results of each method and conducted comparisons and verifications
Primary Subject
Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2012; [2 p.]; 2012 autumn meeting of the KNS; Kyoungju (Korea, Republic of); 24-26 Oct 2012; Available from KNS, Daejeon (KR); 5 refs, 5 figs, 1 tab
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Miscellaneous
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Conference
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