• 제목/요약/키워드: Karlsruhe

검색결과 81건 처리시간 0.031초

다양한 무기결정구조데이터베이스(ICSD) 검색 시스템 개발 (Development of Various Inorganic Crystal Structure Database Retrieval System)

  • 김지영;이상호;한정민
    • 한국콘텐츠학회:학술대회논문집
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    • 한국콘텐츠학회 2004년도 춘계 종합학술대회 논문집
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    • pp.529-534
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    • 2004
  • 한국과학기술정보연구원(KISTI)에서는 무기결정구조데이터베이스(ICSD, Inorganic Crystal Structure Database)를 국내 화학, 재료 관련 연구 개발자들에게 무료로 제공하고자 하였다. 그리하여 독일의 FIZ Karlsruhe로부터 ICSD의 국내 라이센스를 받아 이 데이터를 사용하여 데이터베이스를 구축하고 웹 기반의 새로운 정보 검색 시스템을 개발하였다. 웹상에서 여러 가지 방법으로 결정구조 정보를 검색 할 수 있는 다양한 메뉴를 구성하였으며 검색 결과에서는 결정구조에 관한 수치 정보 뿐 아니라 X-선 회절 패턴 및 3차원 결정구조 그래픽도 함께 제공하게 되었다. 이 시스템은 앞으로도 데이터의 계속적인 추가, 갱신이 이루어질 예정이며 연구자들이 편리하고 신속하게 정보를 제공받을 수 있도록 검색시스템을 향상시켜 나갈 것이다.

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Development of Electrochemical Processes for Aluminium-Based Coatings for Fusion Applications

  • Konys, J.
    • Corrosion Science and Technology
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    • 제15권6호
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    • pp.314-319
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    • 2016
  • Reduced activation ferritic-martensitic steels (RAFM) are envisaged in future fusion technology as structural material which will be in direct contact with a flowing liquid lead-lithium melt, serving as breeder material. Aluminium-based coatings had proven their ability to protect the structural material from corrosion attack in flowing Pb-15.7Li and to reduce tritium permeation into the coolant, significantly. Coming from scales produced by hot dipping aluminization (HDA), the development of electrochemical-based processes to produce well-defined aluminium-based coatings on RAFM steels gained increased attention in research during the last years. Two different electrochemical processes are described in this paper: The first one, referred to as ECA, is based on the electrodeposition of aluminium from volatile, metal-organic electrolytes. The other process called ECX is based on ionic liquids. All three processes exhibit specific characteristics, for example in the field of processability, control of coating thicknesses (low activation criteria) and heat treatment behavior. The aim of this article is to compare these different coating processes critically, whereby the focus is on the comparison of ECA and ECX processes. New results for ECX will be presented and occurring development needs for the future will be discussed.

디컨볼루션 픽셀층 기반의 도로 이미지의 의미론적 분할 (Deconvolution Pixel Layer Based Semantic Segmentation for Street View Images)

  • Wahid, Abdul;Lee, Hyo Jong
    • 한국정보처리학회:학술대회논문집
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    • 한국정보처리학회 2019년도 춘계학술발표대회
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    • pp.515-518
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    • 2019
  • Semantic segmentation has remained as a challenging problem in the field of computer vision. Given the immense power of Convolution Neural Network (CNN) models, many complex problems have been solved in computer vision. Semantic segmentation is the challenge of classifying several pixels of an image into one category. With the help of convolution neural networks, we have witnessed prolific results over the time. We propose a convolutional neural network model which uses Fully CNN with deconvolutional pixel layers. The goal is to create a hierarchy of features while the fully convolutional model does the primary learning and later deconvolutional model visually segments the target image. The proposed approach creates a direct link among the several adjacent pixels in the resulting feature maps. It also preserves the spatial features such as corners and edges in images and hence adding more accuracy to the resulting outputs. We test our algorithm on Karlsruhe Institute of Technology and Toyota Technologies Institute (KITTI) street view data set. Our method achieves an mIoU accuracy of 92.04 %.

The Netherlands Spatial Development for Port Area in City-Region Focusing on the Case of Kop van Zuid in Rotterdam

  • Lee, Hee Jae;Whang, Heejoon
    • Architectural research
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    • 제22권4호
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    • pp.135-143
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    • 2020
  • The Netherlands is a human-made country and an extremely well-designed European country as well. The general Dutch spatial planning for the city and environment takes place at a regional level. The local community determines the primary development conditions, and the prospect is included in a legally binding land-use plan. Especially, Rotterdam is a representative port city as the center of world trade and the gateway to western Europe. According to the history of war, the city reconstruction and the movement of the port area have led to a general change in Rotterdam and the regional redevelopment project on the southern port area of Mass river for the expansion of city functions and the balanced development. The research purpose is to understand the spatial development of the Netherlands city-region based on the analysis regarding the Kop van Zuid project, which is a representative implemented case in Rotterdam. The theoretical framework is the five dimensions and twelve indicators of territorial governance from the TANGO research project by the EU. The target case is assessed by planning and social aspect, respectively, and the results are discussed based on the theoretical framework. This research has the possibility to be utilized as advanced research by the European perspective for spatial development in other city-regions with the port area, such as Incheon and Busan in Korea.

Implementation and benchmarking of the local weight window generation function for OpenMC

  • Hu, Yuan;Yan, Sha;Qiu, Yuefeng
    • Nuclear Engineering and Technology
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    • 제54권10호
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    • pp.3803-3810
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    • 2022
  • OpenMC is a community-driven open-source Monte Carlo neutron and photon transport simulation code. The Weight Window Mesh (WWM) function and an automatic Global Variance Reduction (GVR) method was recently developed and implemented in a developmental branch of OpenMC. This WWM function and GVR method broaden OpenMC's usage in general purposes deep penetration shielding calculations. However, the Local Variance Reduction (LVR) method, which suits the source-detector problem, is still missing in OpenMC. In this work, the Weight Window Generator (WWG) function has been developed and benchmarked for the same branch. This WWG function allows OpenMC to generate the WWM for the source-detector problem on its own. Single-material cases with varying shielding and sources were used to benchmark the WWG function and investigate how to set up the particle histories utilized in WWG-run and WWM-run. Results show that there is a maximum improvement of WWM generated by WWG. Based on the above results, instructions on determining the particle histories utilized in WWG-run and WWM-run for optimal computation efficiency are given and tested with a few multi-material cases. These benchmarks demonstrate the ability of the OpenMC WWG function and the above instructions for the source-detector problem. This developmental branch will be released and merged into the main distribution in the future.

Application of artificial neural network for the critical flow prediction of discharge nozzle

  • Xu, Hong;Tang, Tao;Zhang, Baorui;Liu, Yuechan
    • Nuclear Engineering and Technology
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    • 제54권3호
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    • pp.834-841
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    • 2022
  • System thermal-hydraulic (STH) code is adopted for nuclear safety analysis. The critical flow model (CFM) is significant for the accuracy of STH simulation. To overcome the defects of current CFMs (low precision or long calculation time), a CFM based on a genetic neural network (GNN) has been developed in this work. To build a powerful model, besides the critical mass flux, the critical pressure and critical quality were also considered in this model, which was seldom considered before. Comparing with the traditional homogeneous equilibrium model (HEM) and the Moody model, the GNN model can predict the critical mass flux with a higher accuracy (approximately 80% of results are within the ±20% error limit); comparing with the Leung model and the Shannak model for critical pressure prediction, the GNN model achieved the best results (more than 80% prediction results within the ±20% error limit). For the critical quality, similar precision is achieved. The GNN-based CFM in this work is meaningful for the STH code CFM development.

Experimental research on 2 stage GM-type pulse tube refrigerator for cryopump

  • Park, Seong-Je;Ko, Jun-Seok;Hong, Yong-Ju;Kim, Hyo-Bong;Yeom, Han-Kil;Koh, Deuk-Yong
    • 한국초전도ㆍ저온공학회논문지
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    • 제12권2호
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    • pp.29-33
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    • 2010
  • The experimental results of the 2 stage Gifford-McMahon(GM) type pulse tube refrigerator (PTR) or cryopump are presented in this paper. The objectives of his study are to develop design technology of the integral type 2 stage PTR which rotary valve is directly connected to he hot end of the regenerator and acquire its improved performance. Design of the 2 stage PTR is conducted by FZKPTR(Forschungs Zentrum Karlsruhe Pulse Tube Refrigerator) program for the design of pulse tube refrigerators. The fabricated PTR has U-type configuration and incorporates orifice valve, double-inlet valve and reservoir as phase control mechanism. Rotary valve is used to make pulsating pressure and is directly connected to inlet of $1^{st}$ stage regenerator. From experiments, cooling performance map and pressure waveform at each point were measured for different operating frequencies. Experimental results show the best cooling performance with 2 Hz operation in spite of small pressure amplitude. The lowest temperatures of the 2 stage PTR were 16.9 K at the second stage and 58.0 K at the first stage. The cooling capacities achieved were 14.4 W at 79 K, the first stage and 3.6 W at 29 K, the second stage.

Impact of PSI-KIT Nitriding model on hypothetical Spent Fuel Pool accident simulation

  • Mateusz Malicki;Terttaliisa Lind
    • Nuclear Engineering and Technology
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    • 제55권7호
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    • pp.2504-2515
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    • 2023
  • In past years the Paul Scherrer Institute (PSI, Switzerland) and the Karlsruhe Institue of Technology (KIT, Germany)) collaborated to develop a model to account for the active role of nitrogen in the air oxidation of a Zircalloy cladding. The "PSI-KIT Nitriding Model for Zirconium based Fuel Cladding" model was implemented at PSI into PSI-MELCOR 1.8.6. In order to make a preliminary evaluation of the effect of the new model on the evolution of full-scale spent fuel pool accidents, one spent fuel pool event was analyzed using the PSI research version of PSI-MELCOR 1.8.6, which includes the nitriding model. To adapt an existing input deck for the calculations, a sensitivity study was conducted to find an optimal nodalization for the analyses. The nitriding model results were compared to those calculated with the MELCOR 1.8.6-PSI without the new nitriding model. The results demonstrate the effect of the nitriding reactions in spent fuel pool accident progression. Moreover, they confirm the impact of ZrN formation during cladding oxidation in air when the oxidation reactions lead to oxygen starvation inside the fuel assemblies. The nitriding reaction led to higher chemical heat generation during the accident and to an earlier failure of the cladding than when the effect of nitrogen reactions was not considered. It should be noted that the nitriding model, as implemented in the PSI version of MELCOR 1.8.6 has not yet been conclusively validated. Thereby the results presented in this paper should be treated as a preliminary demonstration of the capabilities of the model.

Developing drought stress index for monitoring Pinus densiflora diebacks in Korea

  • Cho, Nanghyun;Kim, Eunsook;Lim, Jong-Hwan;Seo, Bumsuk;Kang, Sinkyu
    • Journal of Ecology and Environment
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    • 제44권3호
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    • pp.115-125
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    • 2020
  • Background: The phenomenon of tree dieback in forest ecosystems around the world, which is known to be associated with high temperatures that occur simultaneously with drought, has received much attention. Korea is experiencing a rapid rise in temperature relative to other regions. Particularly in the growth of evergreen conifers, temperature increases in winter and spring can have great influence. In recent years, there have been reports of group dieback of Pinus densiflora trees in Korea, and many studies are being conducted to identify the causes. However, research on techniques to diagnose and monitor drought stress in forest ecosystems on local and regional scales has been lacking. Results: In this study, we developed and evaluated an index to identify drought and high-temperature vulnerability in Pinus densiflora forests. We found the Drought Stress Index (DSI) that we developed to be effective in generally assessing the drought-reactive physiology of trees. During 2001-2016, in Korea, we refined the index and produced DSI data from a 1 × 1-km unit grid spanning the entire country. We found that the DSI data correlated with the event data of Pinus densiflora mass dieback compiled in this study. The average DSI value at times of occurrence of Pinus densiflora group dieback was 0.6, which was notably higher than during times of nonoccurrence. Conclusions: Our combination of the Standard Precipitation Index and growing degree days evolved and short- and long-term effects into a new index by which we found meaningful results using dieback event data. Topographical and biological factors and climate data should be considered to improve the DSI. This study serves as the first step in developing an even more robust index to monitor the vulnerability of forest ecosystems in Korea.

OECD/NEA BENCHMARK FOR UNCERTAINTY ANALYSIS IN MODELING (UAM) FOR LWRS - SUMMARY AND DISCUSSION OF NEUTRONICS CASES (PHASE I)

  • Bratton, Ryan N.;Avramova, M.;Ivanov, K.
    • Nuclear Engineering and Technology
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    • 제46권3호
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    • pp.313-342
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    • 2014
  • A Nuclear Energy Agency (NEA), Organization for Economic Co-operation and Development (OECD) benchmark for Uncertainty Analysis in Modeling (UAM) is defined in order to facilitate the development and validation of available uncertainty analysis and sensitivity analysis methods for best-estimate Light water Reactor (LWR) design and safety calculations. The benchmark has been named the OECD/NEA UAM-LWR benchmark, and has been divided into three phases each of which focuses on a different portion of the uncertainty propagation in LWR multi-physics and multi-scale analysis. Several different reactor cases are modeled at various phases of a reactor calculation. This paper discusses Phase I, known as the "Neutronics Phase", which is devoted mostly to the propagation of nuclear data (cross-section) uncertainty throughout steady-state stand-alone neutronics core calculations. Three reactor systems (for which design, operation and measured data are available) are rigorously studied in this benchmark: Peach Bottom Unit 2 BWR, Three Mile Island Unit 1 PWR, and VVER-1000 Kozloduy-6/Kalinin-3. Additional measured data is analyzed such as the KRITZ LEU criticality experiments and the SNEAK-7A and 7B experiments of the Karlsruhe Fast Critical Facility. Analyzed results include the top five neutron-nuclide reactions, which contribute the most to the prediction uncertainty in keff, as well as the uncertainty in key parameters of neutronics analysis such as microscopic and macroscopic cross-sections, six-group decay constants, assembly discontinuity factors, and axial and radial core power distributions. Conclusions are drawn regarding where further studies should be done to reduce uncertainties in key nuclide reaction uncertainties (i.e.: $^{238}U$ radiative capture and inelastic scattering (n, n') as well as the average number of neutrons released per fission event of $^{239}Pu$).