• Journal of the Korean Society of Costume
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• v.67 no.1
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• pp.130-146
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• 2017

This study focuses on the Mise-en-abyme theories of Lucien $D{\ddot{a}}llenbach$, and presents research methodology to analyze the modern cinema costume in a new view. Inherent aesthetic values of the costume code shown in the film are as follows. First, esthetics value shown is the analogic code through the maximization of factual realism by directing target. Mise-en-abyme placed in this film plays the role of costume codes, and highlights the subject by presenting specifically targeted realistic icons to maximize the realism of the movie. Second, Mise-en-abyme is deployed to the explicit text through costumes code is placed as Displaced code arrangements. In other words, each of the characters is a signifier. Symbolizing a historical era is the device that represents a self-reflective signifier. Third, paradoxically reflected by the overlapped expansion of virtual reality and the self-referential characteristics and are subject to reflect the thinking of the author. Costumes code placed in Mise-en-abyme is expressed in costumes positioned to maximize the realism in the film as described above, and implies narratives and self-reflective mediating tools that symbolism can be seen that the paradoxical metaphor for the reality and the future. In addition, through the metaphor of visual narrative is allegorical representation Mise-en-abyme with ambiguity, and it is a concrete text that can be realized in a variety of creative storytelling methods and image delivery methods of modern fashion. This study confirmed that this costumes to take the point of view of emotional $Mise-en-sc{\grave{e}}ne$ in the process of completing the film's themes and cinematic devices by identifying the roles and aesthetic value of code costumes as the core subjects that make up the narrative of the film.

• Nuclear Engineering and Technology
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• v.52 no.8
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• pp.1603-1610
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• 2020

Due to ever-growing advancements in computers and relatively easy access to them, many efforts have been made to develop high-fidelity, high-performance, multi-physics tools, which play a crucial role in the design and operation of nuclear reactors. For this purpose in this study, the neutronic Monte Carlo and thermal-hydraulic sub-channel codes entitled MCNP and COBRA-EN, respectively, were applied for external coupling with each other. The coupled code was validated by code-to-code comparison with the internal couplings between MCNP5 and SUBCHANFLOW as well as MCNP6 and CTF. The simulation results of all code systems were in good agreement with each other. Then, as the second problem, the core of the VVER-1000 v446 reactor was simulated by the MCNP4C/COBRA-EN coupled code to measure the capability of the developed code to calculate the neutronic and thermohydraulic parameters of real and industrial cases. The simulation results of VVER-1000 core were compared with FSAR and another numerical solution of this benchmark. The obtained results showed that the ability of the MCNP4C/COBRA-EN code for estimating the neutronic and thermohydraulic parameters was very satisfactory.

• Journal of the Korea Concrete Institute
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• v.26 no.2
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• pp.211-218
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• 2014

In the design of reinforced rectangular concrete beam structure, the minimum amount of flexural reinforcement is required to avoid brittle failure. KCI code is based on concept of ultimate strength and usually used as a model code. But bridge design code enacted by Ministry of land, transportation and maritime affairs in 2012 is based on concept of limit state and similar to Euro code EN 1992-2. This means that the minimum reinforcement presented in both design codes has different origination and safety margin. When rectangular concrete beams with minimum reinforcement are designed according to EN and KCI codes, the amount of minimum reinforcement specified in EN code is only 76% of that in KCI code. This makes the design engineers to be confused. In this study, flexural tests were conducted on nine beams with the two different minimum reinforcement specified in KCI and EN design codes. In results, the measured ratios of nominal strength to crack strength from the test were about 25% greater than those evaluated from the equations presented in KCI and EN codes. The EN beams having only 76% of the minimum reinforcement for the KCI beams were fractured by rupture of steel reinforcement but in ductile manner. It is confirmed that the minimum reinforcement concrete beams designed according to both codes have enough safety margin in flexural capacity and moreover in ductility.

• Fire Science and Engineering
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• v.23 no.1
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• pp.33-39
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• 2009

In this study, the combustion properties, which are called the reaction-to-fire's performance, of sandwich panels were tested and analyzed according to both ISO 5660 (cone calorimeter method) and EN 13823 (SBI). Several variables including ignition time, mass loss, heat release rate, smoke production rate and $O_2$ density about four sandwich panels and four core materials (thermal insulation material) were evaluated. Combustion properties' similarity and difference of sandwich panels and core materials were compared by materials and test methods respectively. Finally test results were evaluated by Japanese standard building code, National Building code of Canada and EN 13501-1 as well.

• Journal of the Optical Society of Korea
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• v.20 no.2
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• pp.257-262
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• 2016

A two-dimensional optical code division multiple access (OCDMA) en/decoder composed of four double-ring resonator add/drop filters and three delay waveguides is designed, and a transfer matrix method combined with fast Fourier transform is implemented to provide numerical simulations for the en/decoder. The auto-correlation peak level over the maximum cross-correlation level is larger than 3 at the center of the correctly decoded pulse for most of wavelength hopping and spectral phase code combinations, which assures the BER lower than 10^-3 which corresponds to the forward error correction limit.

• Earthquakes and Structures
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• v.4 no.3
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• pp.265-283
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• 2013

This research was prompted by the paucity of specific code provisions regarding the design of short columns for shear. The purpose of this paper was to investigate whether the use of the normal shear design procedure of various codes may or may not be applied to reliably calculate the shear strength of short columns. Provisions of the codes American ACI 318M-08, Canadian CSA A23.3-04, Japanese AIJ Guidelines, New Zealand NZS 3101, European EN 1998 (EC8) parts 1 and 3, combined with EN 1992-1-1 (EC2), and draft fib Model Code 2010, as well as a strut-and-tie model are applied on short columns tested under cyclic loading that failed in shear. Actual shear resistances are compared to predictions, and the resulting shortcomings of the codes are identified. EN1998-3 appears to be the only code among those considered that may be reliably applied to estimate the shear resistance of short columns. Further, the proposed strut-and tie model can be a useful tool for the detailed design and assessment of short columns.

• International Journal of Computer Science & Network Security
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• v.22 no.11
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• pp.241-247
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• 2022

Ad hoc network is self-organized network powered by battery. The reliability of virtual user identification and channel security are reduced when SNR is low due to limited user energy. In order to solve this problem, a joint virtual user identification and channel security en/decoding method is proposed in this paper. Transmitter-receiver-based virtual user identification code is generated by executing XOR operation between orthogonal address code of transmitter and pseudo random address code of receiver and encrypted by channel security code to acquire orthogonal random security sequence so as to improve channel security. In order to spread spectrum as well as improve transmission efficiency, data packet is divided into 6-bit symbols, each symbol is mapped with an orthogonal random security sequence. Subspace-based method is adopted by receiver to process received signal firstly, and then a judgment model is established to identify virtual users according to the previous processing results. Simulation results indicate that the proposed method obtains 1.6dB E_b/N₀ gains compared with reference methods when miss alarm rate reaches 10^-3.

• Journal of Convergence for Information Technology
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• v.9 no.2
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• pp.85-93
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• 2019

There is currently no recognized standard for the size of lifts. Each elevator manufacturer sets the maximum allowable floor area that meets the capacity calculation standard of the elevator using the maximum used car floor area, which is defined by EN-CODE and the domestic inspection standard, and determines the elevator size based on their own standards. In this paper, we propose a method to more easily determine the elevator size. To do this, we implemented a program that calculates the size of the elevator by inputting the dimensions of the hoistway. This program will be useful method for quick decision making and elevator installation considering the elevator factors according to the already determined hoistway size of the building and calculating the EN-CODE currently used and the size of the elevator according to domestic inspection standards.

• Nuclear Engineering and Technology
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• v.56 no.5
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• pp.1574-1583
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• 2024

Small Modular Reactors (SMRs) are compact nuclear reactors designed to generate electric power up to 300 MWe. They could be assembled in factory, and then transported to be directly installed on-stie. CAREM (Central Argentina de Elementos Modulares) is a national SMR development project, based on light water reactor technology supervised by Argentina's National Atomic Energy Commission (CNEA). It is a natural circulation-based SMR with an indirect-cycle, including specific items and parts that simplify the design and improve safety performance. In this paper, the thermal-hydraulic study of CAREM-25 advanced small modular reactor is conducted by using COBRA-EN modified code and the Porous Media Approach (PMA) for the first time. According to PMA approach, each fuel assembly is modeled and divided into a network of lumped regions. While complex geometries are defined, the thermal-hydraulic parameters such as temperature and density are calculated for coolant and fuel rods. The obtained results show that the temperature in the fuel center may reach a peak around 1280 K in the hottest fuel assembly. Finally, the comparison of results from both methods (modified COBRA-EN and PMA) presented an appropriate consistency.

• Nuclear Engineering and Technology
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• v.55 no.5
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• pp.1593-1603
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• 2023

In deterministic and Monte Carlo transport codes, b-delayed emission is included using a group structure where all of the precursors are grouped together in 6 groups or families, but given the increase in computational power, nowadays there is no reason to keep this structure. Furthermore, there have been recent efforts to compile and evaluate all the available b-delayed neutron emission data and to measure new and improved data on individual precursors. In order to be able to perform a transient Monte Carlo simulation, data from individual precursors needs to be implemented in a transport code. This work is the first step towards the development of a tool to explore the effect of individual precursors in a fissile system. In concrete, individual precursor data is included by expanding the capabilities of the open source Monte Carlo code OpenMC. In the modified code - named Time Dependent OpenMC or OpenMC(TD)- time dependency related to β-delayed neutron emission was handled by using forced decay of precursors and combing of the particle population. The data for continuous energy neutron cross-sections was taken from JEFF-3.1.1 library. Regarding the data needed to include the individual precursors, cumulative yields were taken from JEFF-3.1.1 and delayed neutron emission probabilities and delayed neutron spectra were taken from ENDF-B/VIII.0. OpenMC(TD) was tested in a monoenergetic system, an energy dependent unmoderated system where the precursors were taken individually or in a group structure, and in a light-water moderated energy dependent system, using 6-groups, 50 and 40 individual precursors. Neutron flux as a function of time was obtained for each of the systems studied. These results show the potential of OpenMC(TD) as a tool to study the impact of individual precursor data on fissile systems, thus motivating further research to simulate more complex fissile systems.