• 제목/요약/키워드: FusionNet

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티셔츠 원 포인트 그래픽에 나타난 Mix & Match 시각 이미지 분석 (The Analysis of Mix & Match Visual Image of One-Point Graphic Appeared in T-shirt)

  • 이미연
    • 복식문화연구
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    • 제13권5호
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    • pp.777-789
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    • 2005
  • Mix & Match Visual Image, appearing in T-shirt one-point graphics, is a new visual image emerged as a result of several trends: development of cutting-edge machinery and computer programs, various needs of consumers, and an international trend of fusion concept. Thus, a concrete research of Mix & Match Visual Images is demanding. This paper studies one-point graphic, which appeared in the SamsungDesignNet, Interfashion Planning, and firstviewkorea, with a focus on apparel T-shirt of women's wear and casual wear from 2001 to 2004. The study shows that the most preferred independent visual image in Mix & Match Visual Images is a typography, and next is in the order of marks, symbols, geometric diagrams and abstract shapes, animals and plants, characters, materials, and collages. As Mix & Match of independent visual images was mainly combined typography with other independent visual images, we need to develop more Mix & Match Visual Images using various independent visual images's mix and match. Then, T-shirt will be one of the most representative items in Korean fashion trend that enable consumers to express their characters, escaping from the old-fashioned concept that T-shirt is just a T-shirt.

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Neutronics analysis of TRIGA Mark II research reactor

  • Rehman, Haseebur;Ahmad, Siraj-ul-Islam
    • Nuclear Engineering and Technology
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    • 제50권1호
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    • pp.35-42
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    • 2018
  • This article presents clean core criticality calculations and control rod worth calculations for TRIGA (Training, Research, Isotope production-General Atomics) Mark II research reactor benchmark cores using Winfrith Improved Multi-group Scheme-D/4 (WIMS-D/4) and Program for Reactor In-core Analysis using Diffusion Equation (PRIDE) codes. Cores 133 and 134 were analyzed in 2-D (r, ${\theta}$) and 3-D (r, ${\theta}$, z), using WIMS-D/4 and PRIDE codes. Moreover, the influence of cross-section data was also studied using various libraries based on Evaluated Nuclear Data File (ENDF/B-VI.8 and VII.0), Joint Evaluated Fission and Fusion File (JEFF-3.1), Japanese Evaluated Nuclear Data Library (JENDL-3.2), and Joint Evaluated File (JEF-2.2) nuclear data. The simulation results showed that the multiplication factor calculated for all these data libraries is within 1% of the experimental results. The reactivity worth of the control rods of core 134 was also calculated with different homogenization approaches. A comparison was made with experimental and reported Monte Carlo results, and it was found that, using proper homogenization of absorber regions and surrounding fuel regions, the results obtained with PRIDE code are significantly improved.

KAERIT 토카막의 플라즈마 생성 실험 (Plasma Initiation in the KAERIT Tokamak)

  • In, Sang-Ryul;Bak, Hae-Ill
    • Nuclear Engineering and Technology
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    • 제20권4호
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    • pp.246-252
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    • 1988
  • KAERIT 토카막 장치의 플라즈마 생성을 위한 수소기차 방전실험에 관해 기술하였다. 이 실험에서는 일주전압, 토로이달 자장, 충전기체 압력, 오차자장 및 예비전리 등이 방전시작에 미치는 영향이 연구되었다. 오차자장은 방전에 가장 큰 영향을 미치는 인자로서 방전전압이 최소가 되는 것은 결국 오차자장 성분을 가장 잘 상쇄시켰을 때였다. 예비전리의 효과는 전반적으로 두드러지지는 않았지만 밀폐 성능이 나쁠수록 상대적으로 크게 나타났다. 실험적으로 구해진 방전시작조건은 이론적인 모델의 계산결과와 비교하였다. 실험에서의 방전영역이 이론적인 계산결과에 비해 줄어드는 경향을 보이고 있는 것은 고려되지 않은 다른 인자에 기인하는 것으로 판단되지만 토카막의 방전시작단계를 다루기에는 이 모델로도 충분하다.

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Design Study for Pulsed Proton Beam Generation

  • Kim, Han-Sung;Kwon, Hyeok-Jung;Seol, Kyung-Tae;Cho, Yong-Sub
    • Nuclear Engineering and Technology
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    • 제48권1호
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    • pp.189-199
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    • 2016
  • Fast neutrons with a broad energy spectrum, with which it is possible to evaluate nuclear data for various research fields such as medical applications and the development of fusion reactors, can be generated by irradiating proton beams on target materials such as beryllium. To generate short-pulse proton beam, we adopted a deflector and slit system. In a simple deflector with slit system, most of the proton beam is blocked by the slit, especially when the beam pulse width is short. Therefore, the available beam current is very low, which results in low neutron flux. In this study, we proposed beam modulation using a buncher cavity to increase the available beam current. The ideal field pattern for the buncher cavity is sawtooth. To make the field pattern similar to a sawtooth waveform, a multiharmonic buncher was adopted. The design process for the multiharmonic buncher includes a beam dynamics calculation and three-dimensional electromagnetic simulation. In addition to the system design for pulsed proton generation, a test bench with a microwave ion source is under preparation to test the performance of the system. The design study results concerning the pulsed proton beam generation and the test bench preparation with some preliminary test results are presented in this paper.

The bubble problem of the plasma facing material: A finite element study

  • Kang, Xiaoyan;Cheng, Xiyue;Deng, Shuiquan
    • Nuclear Engineering and Technology
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    • 제52권10호
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    • pp.2290-2298
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    • 2020
  • The damage of first wall material in fusion reactor due to the bubbles caused by plasma has been studied by introducing a relation between the von Mises equivalent stress and the temperature field. The locations and shapes of the bubbles and the synergetic effect between the different bubbles under steady operational conditions have been studied using the finite elements method. Under transient heat loads, plastic deformations have been found to occur, and are significantly enhanced by the presence of the bubbles. The calculated concentration locations of von Mises equivalent stress are well consistent with the observed crack positions of the tungsten surface in many test experiments. Our simulations show that the damage of the bubbles is not severe enough to lead to catastrophic failure of the tungsten armor; however, it can cause local and gradual detachment of tungsten surface, which provides a reasonable explanation for the observed pits and rough or hairy surface morphology etc. Considering the transient heat loads, the lower bound of the security thickness of the tungsten tile is estimated to be greater than 2 mm.

Automatic Classification of Drone Images Using Deep Learning and SVM with Multiple Grid Sizes

  • Kim, Sun Woong;Kang, Min Soo;Song, Junyoung;Park, Wan Yong;Eo, Yang Dam;Pyeon, Mu Wook
    • 한국측량학회지
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    • 제38권5호
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    • pp.407-414
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    • 2020
  • SVM (Support vector machine) analysis was performed after applying a deep learning technique based on an Inception-based model (GoogLeNet). The accuracy of automatic image classification was analyzed using an SVM with multiple virtual grid sizes. Six classes were selected from a standard land cover map. Cars were added as a separate item to increase the classification accuracy of roads. The virtual grid size was 2-5 m for natural areas, 5-10 m for traffic areas, and 10-15 m for building areas, based on the size of items and the resolution of input images. The results demonstrate that automatic classification accuracy can be increased by adopting an integrated approach that utilizes weighted virtual grid sizes for different classes.

Two-Stream Convolutional Neural Network for Video Action Recognition

  • Qiao, Han;Liu, Shuang;Xu, Qingzhen;Liu, Shouqiang;Yang, Wanggan
    • KSII Transactions on Internet and Information Systems (TIIS)
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    • 제15권10호
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    • pp.3668-3684
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    • 2021
  • Video action recognition is widely used in video surveillance, behavior detection, human-computer interaction, medically assisted diagnosis and motion analysis. However, video action recognition can be disturbed by many factors, such as background, illumination and so on. Two-stream convolutional neural network uses the video spatial and temporal models to train separately, and performs fusion at the output end. The multi segment Two-Stream convolutional neural network model trains temporal and spatial information from the video to extract their feature and fuse them, then determine the category of video action. Google Xception model and the transfer learning is adopted in this paper, and the Xception model which trained on ImageNet is used as the initial weight. It greatly overcomes the problem of model underfitting caused by insufficient video behavior dataset, and it can effectively reduce the influence of various factors in the video. This way also greatly improves the accuracy and reduces the training time. What's more, to make up for the shortage of dataset, the kinetics400 dataset was used for pre-training, which greatly improved the accuracy of the model. In this applied research, through continuous efforts, the expected goal is basically achieved, and according to the study and research, the design of the original dual-flow model is improved.

Fuzzy-PID controller for motion control of CFETR multi-functional maintenance platform

  • Li, Dongyi;Lu, Kun;Cheng, Yong;Zhao, Wenlong;Yang, Songzhu;Zhang, Yu;Li, Junwei;Wu, Huapeng
    • Nuclear Engineering and Technology
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    • 제53권7호
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    • pp.2251-2260
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    • 2021
  • The motion control of the divertor maintenance system of the China Fusion Engineering Test Reactor (CFETR) was studied in this paper, in which CFETR Multi-Functional Maintenance Platform (MFMP) was simplified as a parallel robot for the convenience of theoretical analysis. In order to design the motion controller of parallel robot, the kinematics analysis of parallel robot was carried out. After that, the dynamic modeling of the hydraulic system was built. As the large variation of heavy payload on MFMP and highly nonlinearity of the system, A Fuzzy-PID controller was built for self-tuning PID controller parameters by using Fuzzy system to achieve better performance. In order to test the feasibility of the Fuzzy-PID controller, the simulation model of the system was built in Simulink. The results have showed that Fuzzy-PID controller can significantly reduce the angular error of the moving platform and provide the stable motion for transferring the divertor.

Finite element analysis of high-density polyethylene pipe in pipe gallery of nuclear power plants

  • Shi, Jianfeng;Hu, Anqi;Yu, Fa;Cui, Ying;Yang, Ruobing;Zheng, Jinyang
    • Nuclear Engineering and Technology
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    • 제53권3호
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    • pp.1004-1012
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    • 2021
  • High density polyethylene (HDPE) pipe has many advantages over metallic pipe, and has been used in non-safety related application for years in some nuclear power plants (NPPs). Recently, HDPE pipe was introduced into safety related applications. The main difference between safety-related and non-safety-related pipes in NPPs is the design method of extra loadings such as gravity, temperature, and earthquake. In this paper, the mechanical behavior of HDPE pipe under various loads in pipe gallery was studied by finite element analysis (FEA). Stress concentrations were found at the fusion regions on inner surface of mitered elbows of HDPE pipe system. The effects of various factors were analyzed, and the influence of various loads on the damage of HDPE pipe system were evaluated. The results of this paper provide a reference for the design of nuclear safety-related Class 3 HDPE pipe. In addition, as the HDPE pipes analyzed in this paper were suspended in pipe gallery, it can also serve as a supplementary reference for current ASME standard on Class 3 HDPE pipe, which only covers the application for buried pipe application.

Evaluation of MCC seismic response according to the frequency contents through the shake table test

  • Chang, Sung-Jin;Jeong, Young-Soo;Eem, Seung-Hyun;Choi, In-Kil;Park, Dong-Uk
    • Nuclear Engineering and Technology
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    • 제53권4호
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    • pp.1345-1356
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    • 2021
  • Damage to nuclear power plants causes human casualties and environmental disasters. There are electrical facilities that control safety-related devices in nuclear power plants, and seismic performance is required for them. The 2016 Gyeongju earthquake had many high-frequency components. Therefore, there is a high possibility that an earthquake involving many high frequency components will occur in South Korea. As such, it is necessary to examine the safety of nuclear power plants against an earthquake with many high-frequency components. In this study, the shaking table test of electrical facilities was conducted against the design earthquake for nuclear power plants with a large low-frequency components and an earthquake with a large high-frequency components. The response characteristics of the earthquake with a large high-frequency components were identified by deriving the amplification factors of the response through the shaking table test. In addition, safety of electrical facility against the two aforementioned types of earthquakes with different seismic characteristics was confirmed through limit-state seismic tests. The electrical facility that was performed to the shaking table test in this study was a motor control center (MCC).