• Title/Summary/Keyword: KAN Code

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A Study on KAN Code ID for Promoting Distribution Information or Agricultural Products (농산물 유통 정보화 촉진을 위한 KAN코드 사용 확대에 관한 연구)

  • Ahn, Seung-Yong;Kang, Kyung-Sik
    • Journal of the Korea Safety Management & Science
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    • v.8 no.5
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    • pp.99-117
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    • 2006
  • Consumers keep demanding for diversified high quality products, valuable services and safety. With this in mind, Distribution Industry is being updated rapidly to accomodate this demand. Meanwhile, Distribution Information Technology of agricultural products has been in slow progress with little in-depth studies. In this study, it has been analyzed the usage of Bar code which is the key element for agricultural Distribution Information Technology. The analysis was conducted through a survey utilizing questionnaire covering 5 Hypermarkets(Super-centers) including big 3 companies. Also, Japanese market trends have been studied to visit a Japan Government Organization concerned, GS1 Japan, an Agricultural Cooperative, an Agricultural Wholesale Market, and a Retail Company. If we could use KAN code for all agricultural products, we could collect and analyze the information of price and trade quantity of them. It opens a new era to understand the agricultural products supply and demand easily. This will certainly make a great contribution to the evolution of agricultural products distribution. From this research, it is suggested that collective efforts by suppliers, wholesalers, retailers and Government Officers are needed to make large scale mutual marketing Organizations, which specialize in sending out agricultural products. The Organization is recommended to standardize and pack every final agricultural products, to promote the use of KAN code.

A Study on the Layout of Master File of POS for Apparel Industry (국내 의류산업의 POS 시스템 사용 실태에 관한 연구)

  • 조진숙;차주희
    • Journal of the Korean Society of Clothing and Textiles
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    • v.24 no.4
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    • pp.451-462
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    • 2000
  • This study is to investigate the current use of POS system in Korean clothing industry, so that we can make suggestions for better use of it. We interviewd companies using POS systems as well as EAN Korea which is in charge of POS data processing. As a results. we found out that standard KAN code has severe difficulties to cope with the diversity of the information which is necessary in clothing industry. Therefore we are making some suggestions to use KAN code as a recognizing code for more structured master data file for extremely diverse clothing items.

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QR Technology Adoption and Effects in Korean Apparel Industry (한국 의류산업의 QR Technology 도입과 효과에 대한 연구)

  • 신상무;장성환
    • Journal of the Korean Society of Costume
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    • v.44
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    • pp.168-179
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    • 1999
  • In order to settle down structural causes of the process of distribution and apparel production in domestic fashion industry, and to raise competitive power with changing market environment, we need to bulid up Quick Response(QR) system based on information technology such as EDI(Electronic Data Interchange), KAN(Korea Article Number), and POS(Point of Sales), POS is the most valuable information tool to promote QR system paractically. The purpose of this study was to investigate motivation of POS adoption, problems in operating the system, and satisfaction on POS effects. Data were collected by sending questionnaire to the managers in apparel firms which were using POS. Statistical devices were t-test, frequency with SAS program. The results fo the study were as follows: 1. The degree of satisfaction to POS effects was rather good. Especially, rapid evaluations on new products gave the greatest satisfaction to the users. 2. Satisfaction degree of POS effects according to introduces time and organization characteristic(number of employees) have no significant difference, but the firms which have higher annual sales volume showed higher satisfaction degree. Merchandise department showed higher satisfaction on POS effects. 3. The motivation of POS adoption was an effective logistics control with consumer information as a marketing strategy. The problems in operating the system were lack of investment, and professionals. They almost didn't have KAN code, instead, have their own code system.

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Application features of The detailed rules of Census (1896) through the change of house Kan numbers in Gyeonpyeong-bang, Jung-seo in Hanseong-bu -Focused on Gyeonpyeong-bang 1-tong to 23-tong in 1903 and 1906- (한성부 중서 견평방에서 가택 칸수의 변화를 통해서 살펴본 「호구조사세칙」(1896)의 적용 양상 -1903년과 1906년의 견평방 1통에서 23통까지를 대상으로-)

  • Cho, Yun-O;Woo, Don-Son
    • Journal of architectural history
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    • v.28 no.6
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    • pp.19-30
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    • 2019
  • This study explores the application aspect of The detailed rules of Census (1896) through the change of Kan numbers in Gyeonpyeong-bang. Although Gyeonpyeong-bang was a high-priority area because of its location, it was difficult to trace the operation of the urban situation due to lack of data. This study is focusing on restoring space and society in the Gyeonpyeong-bang using the information on the type of houses and the number of Kan listed in the family register of Hanseong-bu. The detailed rules of Census sets out provisions for the family registry and the rules of making Tong. Especially when it comes to the rules of making Tong, this rule deals with the code of making ten Hos into one Tong. This study was conducted by dividing the status of the Tong into three types: uncompleted Tong, exceeded Tong without vacant Ho number, and exceeded Tong with the vacant Ho number. Since these three types of Tong are in the process of change towards the complete Tong with 10 Hos, they were thought to be able to demonstrate the specific application of the rules. This study will be meaningful as a case study that expands the point of existing research on the Tong making rules, which was not focused relatively on restoring urban conditions at that time, by looking at the changes in exceptions that deviated from the Sipgajaktong rule.

One-step Monte Carlo global homogenization based on RMC code

  • Pan, Qingquan;Wang, Kan
    • Nuclear Engineering and Technology
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    • v.51 no.5
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    • pp.1209-1217
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    • 2019
  • Due to the limitation of the computers, the conventional homogenization method is based on many assumptions and approximations, and some tough problems such as energy spectrum and boundary condition are faced. To deal with those problems, the Monte Carlo global homogenization is adopted. The Reactor Monte Carlo code RMC is used to study the global homogenization method, and the one-step global homogenization method is proposed. The superimposed mesh geometry is also used to divide the physical models, leading to better geometric flexibility. A set of multigroup homogenization cross sections is online generated for each mesh under the real neutron energy spectrum and boundary condition, the cross sections are adjusted by the superhomogenization method, and no leakage correction is required. During the process of superhomogenization, the author-developed reactor core program NLSP3 is used for global calculation, so the global flux distribution and equivalent homogenization cross sections could be solved simultaneously. Meanwhile, the calculated homogenization cross section could accurately reconstruct the non-homogenization flux distribution and could also be used for fine calculation. This one-step global homogenization method was tested by a PWR assembly and a small reactor model, and the results show the validity.

Acceleration method of fission source convergence based on RMC code

  • Pan, Qingquan;Wang, Kan
    • Nuclear Engineering and Technology
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    • v.52 no.7
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    • pp.1347-1354
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    • 2020
  • To improve the efficiency of MC criticality calculation, an acceleration method of fission source convergence which gives an improved initial fission source is proposed. In this method, the MC global homogenization is carried out to obtain the macroscopic cross section of each material mesh, and then the nonlinear iterative solution of the SP3 equations is used to determine the fission source distribution. The calculated fission source is very close to the real fission source, which describes its space and energy distribution. This method is an automatic computation process and is tested by the C5G7 benchmark, the results show that this acceleration method is helpful to reduce the inactive cycles and overall running time.

Criticality benchmarking of ENDF/B-VIII.0 and JEFF-3.3 neutron data libraries with RMC code

  • Zheng, Lei;Huang, Shanfang;Wang, Kan
    • Nuclear Engineering and Technology
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    • v.52 no.9
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    • pp.1917-1925
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    • 2020
  • New versions of ENDF/B and JEFF data libraries have been released during the past two years with significant updates in the neutron reaction sublibrary and the thermal neutron scattering sublibrary. In order to get a more comprehensive impression of the criticality quality of these two latest neutron data libraries, and to provide reference for the selection of the evaluated nuclear data libraries for the science and engineering applications of the Reactor Monte Carlo code RMC, the criticality benchmarking of the two latest neutron data libraries has been performed. RMC was employed as the computational tools, whose processing capability for the continuous representation ENDF/B-VIII.0 thermal neutron scattering laws was developed. The RMC criticality validation suite consisting of 116 benchmarks was established for the benchmarking work. The latest ACE format data libraries of the neutron reaction and the thermal neutron scattering laws for ENDF/B-VIII.0, ENDF/B-VII.1, and JEFF-3.3 were downloaded from the corresponding official sites. The ENDF/B-VII.0 data library was also employed to provide code-to-code validation for RMC. All the calculations for the four different data libraries were performed by using a parallel version of RMC, and all the calculated standard deviations are lower than 30pcm. Comprehensive analyses including the C/E values with uncertainties, the δk/σ values, and the metrics of χ2 and < |Δ| >, were conducted and presented. The calculated keff eigenvalues based on the four data libraries generally agree well with the benchmark evaluations for most cases. Among the 116 criticality benchmarks, the numbers of the calculated keff eigenvalues which agree with the benchmark evaluations within 3σ interval (with a confidence level of 99.6%) are 107, 109, 112, and 113 for ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0 and JEFF-3.3, respectively. The present results indicate that the ENDF/B-VIII.0 neutron data library has a better performance on average.

Domain Decomposition Strategy for Pin-wise Full-Core Monte Carlo Depletion Calculation with the Reactor Monte Carlo Code

  • Liang, Jingang;Wang, Kan;Qiu, Yishu;Chai, Xiaoming;Qiang, Shenglong
    • Nuclear Engineering and Technology
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    • v.48 no.3
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    • pp.635-641
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    • 2016
  • Because of prohibitive data storage requirements in large-scale simulations, the memory problem is an obstacle for Monte Carlo (MC) codes in accomplishing pin-wise three-dimensional (3D) full-core calculations, particularly for whole-core depletion analyses. Various kinds of data are evaluated and quantificational total memory requirements are analyzed based on the Reactor Monte Carlo (RMC) code, showing that tally data, material data, and isotope densities in depletion are three major parts of memory storage. The domain decomposition method is investigated as a means of saving memory, by dividing spatial geometry into domains that are simulated separately by parallel processors. For the validity of particle tracking during transport simulations, particles need to be communicated between domains. In consideration of efficiency, an asynchronous particle communication algorithm is designed and implemented. Furthermore, we couple the domain decomposition method with MC burnup process, under a strategy of utilizing consistent domain partition in both transport and depletion modules. A numerical test of 3D full-core burnup calculations is carried out, indicating that the RMC code, with the domain decomposition method, is capable of pin-wise full-core burnup calculations with millions of depletion regions.

Research on the calculation method of sensitivity coefficients of reactor power to material density based on Monte Carlo perturbation theory

  • Wu Wang;Kaiwen Li;Yuchuan Guo;Conglong Jia;Zeguang Li;Kan Wang
    • Nuclear Engineering and Technology
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    • v.55 no.12
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    • pp.4685-4694
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    • 2023
  • The ability to calculate the material density sensitivity coefficients of power with respect to the material density has broad application prospects for accelerating Monte Carlo-Thermal Hydraulics iterations. The second-order material density sensitivity coefficients for the general Monte Carlo score have been derived based on the differential operator sampling method in this paper, and the calculation of the sensitivity coefficients of cell power scores with respect to the material density has been realized in continuous-energy Monte Carlo code RMC. Based on the power-density sensitivity coefficients, the sensitivity coefficients of power scores to some other physical quantities, such as power-boron concentration coefficients and power-temperature coefficients considering only the thermal expansion, were subsequently calculated. The effectiveness of the proposed method is demonstrated in the power-density coefficients problems of the pressurized water reactor (PWR) moderator and the heat pipe reactor (HPR) reflectors. The calculations were carried out using RMC and the ENDF/B-VII.1 neutron nuclear data. It is shown that the calculated sensitivity coefficients can be used to predict the power scores accurately over a wide range of boron concentration of the PWR moderator and a wide range of temperature of HPR reflectors.