• Title/Summary/Keyword: Code distribution

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Power Density Distribution Calculation of a Pressurized Water Reactor with Fullscope Explicit Modeling by MCNP Code

  • Kim, Jong-Oh;Kim, Jong-Kyung
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05a
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    • pp.179-184
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    • 1996
  • Power density distribution and criticality of a pressurized water reactor are calculated with a Monte Carlo calculation using the MCNP code. The MCNP model is based on one-eighth core symmetry. Individual fuel assemblies are modeled with fullscope three dimensional description except grid spacer. The fuel rod is divided into eight axial segments. Core internals above and below the active fuel region is represented as coolant. After 400 cycle calculations, the system converges to a k value of 1.09151$\pm$0.00066. Fission reaction rate in each rod is also calculated to use as the source term in pressure vessel fluence calculation.

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Prediction of Microstructure Evolution and Hardness Distribution in the Weld Repair of Carbon Steel Pipeline

  • Li, V.;Kim, D.
    • International Journal of Korean Welding Society
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    • v.2 no.2
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    • pp.1-6
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    • 2002
  • This article presents an integrated modeling approach for coupled analysis of heat transfer and microstructure evolution in welding carbon steel. The modeling procedure utilizes commercial finite element code ABAQUS/Standard as the platform for solving the equation of heat conduction. User subroutines that Implement computational thermodynamics and kinetics models are integrated with the FEA code to compute the transient microstructure evolution. In this study, the integrated models are applied to simulate the hot-tap repair welding of carbon steel pipeline. Microstructural components are treated as user output variables. Based on the predicted microstructure and cooling rates, hardness distributions in the welds were also predicted. The predicted microstructure and hardness distribution were found in good agreement with metallographic examinations and hardness measurements. This study demonstrates the applicability of computational models for the development of welding procedure for in-service pipeline repair.

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Study on Optimization Technique for Design of the Road Tunnel Ventilation System (도로터널 환기시스템 설계 프로그램 개발)

  • 유지오;이동호;신현주
    • Journal of the Korean Society of Safety
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    • v.14 no.4
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    • pp.60-70
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    • 1999
  • In this study, the computer code for the optimal design of road tunnel ventilation system based on one-dimensional analysis of the air flow was developed. The control volume method was used to calculate the air velocities and the concentration distribution of pollutants(CO, NOx, Particulate) for various tunnel ventilation system. This code was validated by comparing the calculation results to the practical design data for the road tunnel ventilation system. The calculation results were in accord with the practical design data.

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Application of TULIP/STREAM code in 2-D fast reactor core high-fidelity neutronic analysis

  • Du, Xianan;Choe, Jiwon;Choi, Sooyoung;Lee, Woonghee;Cherezov, Alexey;Lim, Jaeyong;Lee, Minjae;Lee, Deokjung
    • Nuclear Engineering and Technology
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    • v.51 no.8
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    • pp.1871-1885
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    • 2019
  • The deterministic MOC code STREAM of the Computational Reactor Physics and Experiment (CORE) laboratory of Ulsan National Institute of Science and Technology (UNIST), was initially designed for the calculation of pressurized water reactor two- and three-dimensional assemblies and cores. Since fast reactors play an important role in the generation-IV concept, it was decided that the code should be upgraded for the analysis of fast neutron spectrum reactors. This paper presents a coupled code - TULIP/STREAM, developed for the fast reactor assembly and core calculations. The TULIP code produces self-shielded multi-group cross-sections using a one-dimensional cylindrical model. The generated cross-section library is used in the STREAM code which solves eigenvalue problems for a two-dimensional assembly and a multi-assembly whole reactor core. Multiplication factors and steady-state power distributions were compared with the reference solutions obtained by the continuous energy Monte-Carlo code MCS. With the developed code, a sensitivity study of the number of energy groups, the order of anisotropic PN scattering, and the multi-group cross-section generation model was performed on the keff and power distribution. The 2D core simulation calculations show that the TULIP/STREAM code gives a keff error smaller than 200 pcm and the root mean square errors of the pin-wise power distributions within 2%.

A Study on High-Speed Extraction of Bar Code Region for Parcel Automatic Identification (소포 자동식별을 위한 바코드 관심영역 고속 추출에 관한 연구)

  • Park, Moon-Sung;Kim, Jin-Suk;Kim, Hye-Kyu;Jung, Hoe-Kyung
    • The KIPS Transactions:PartD
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    • v.9D no.5
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    • pp.915-924
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    • 2002
  • Conventional Systems for parcel sorting consist of two sequences as loading the parcel into conveyor belt system and post-code input. Using bar code information, the parcels to be recorded and managed are recognized. This paper describes a 32 $\times$ 32 sized mini-block inspection to extract bar code Region of Interest (ROI) from the line Charged Coupled Device (CCD) camera capturing image of moving parcel at 2m/sec speed. Firstly, the Min-Max distribution of the mini-block has been applied to discard the background of parcel and region of conveying belts from the image. Secondly, the diagonal inspection has been used for the extraction of letters and bar code region. Five horizontal line scanning detects the number of edges and sizes and ROI has been acquired from the detection. The wrong detected area has been deleted by the comparison of group size from labeling processes. To correct excluded bar code region in mini-block processes and for analysis of bar code information, the extracted ROI 8 boundary points and decline distribution have been used with central axis line adjustment. The ROI extraction and central axis creation have become enable within 60~80msec, and the accuracy has been accomplished over 99.44 percentage.

Sanitary Characterization of Commercial Fish Jerky (시판 어육포의 위생학적 특성)

  • Kang, Mun Ki;Park, Sun Young;Lee, Su Gwang;Heu, Min Soo;Kim, Jin-Soo
    • Korean Journal of Fisheries and Aquatic Sciences
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    • v.50 no.2
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    • pp.111-119
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    • 2017
  • We assessed the sanitary quality of fish jerky based on domestic standards (Korean FDA, Standards on Quality of Seafood and Seafood Products, KS) and compared the characteristics of fish jerky with those of other commercial animal jerky products. The standards encompassed sensory properties (form, flavor, color, texture, and foreign matter), moisture, and microbial properties (Escherichia coli and Staphylococcus aureus). Based on the standards, some fish jerkies did not meet standards on sensory form (code 5) and color (code 11), moisture content (code 7 and 12), E. coli (code 2, 4, 5, 9, 10 and 14) and S. Aureus (code 5). These results suggest that commercial fish jerky should be monitored and controlled on safety to ensure the distribution of high-quality products.

Fatigue Evaluation of Steam Separators of Heat Recovery Steam Generators According to the ASME Boiler and Pressure Vessel Code (ASME Boiler & Pressure Vessel Code에 따른 배열회수보일러 기수분리기의 피로 평가)

  • Lee, Boo-Youn
    • Journal of the Korean Society of Manufacturing Process Engineers
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    • v.17 no.4
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    • pp.150-159
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    • 2018
  • The present research deals with a finite element analysis and fatigue evaluation of a steam separator of a high-pressure evaporator for the Heat Recovery Steam Generator (HRSG). The fatigue during the expected life of the HRSG was evaluated according to the ASME Boiler and Pressure Vessel Code Section VIII Division 2 (ASME Code). First, based on the eight transient operating conditions prescribed for the HRSG, temperature distribution of the steam separator was analyzed by a transient thermal analysis. Results of the thermal analysis were used as a thermal load for the structural analysis and used to determine the mean cycle temperature. Next, a structural analysis for the transient conditions was carried out with the thermal load, steam pressure, and nozzle load. The maximum stress location was found to be the riser nozzle bore, and hence fatigue was evaluated at that location, as per ASME Code. As a result, the cumulative usage factor was calculated as 0.00072 (much less than 1). In conclusion, the steam separator was found to be safe from fatigue failure during the expected life.