• Title/Summary/Keyword: G code

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The nuclear fuel cycle code ANICCA: Verification and a case study for the phase out of Belgian nuclear power with minor actinide transmutation

  • Rodriguez, I. Merino;Hernandez-Solis, A.;Messaoudi, N.;Eynde, G. Van den
    • Nuclear Engineering and Technology
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    • v.52 no.10
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    • pp.2274-2284
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    • 2020
  • The Nuclear Fuel Cycle Code "ANICCA" has been developed by SCK•CEN to answer particular questions about the Belgian nuclear fleet. However, the wide range of capabilities of the code make it also useful for international or regional studies that include advanced technologies and strategies of cycle. This paper shows the main features of the code and the facilities that can be simulated. Additionally, a comparison between several codes and ANICCA has also been made to verify the performance of the code by means of a simulation proposed in the last NEA (OECD) Benchmark Study. Finally, a case study of the Belgian nuclear fuel cycle phase out has been carried out to show the possible impact of the transmutation of the minor actinides on the nuclear waste by the use of an Accelerator Driven System also known as ADS. Results show that ANICCA accomplishes its main purpose of simulating the scenarios giving similar outcomes to other codes. Regarding the case study, results show a reduction of more than 60% of minor actinides in the Belgian nuclear cycle when using an ADS, reducing significantly the radiotoxicity and decay heat of the high-level waste and facilitating its management.

STEP-NC milling data model and part programming (STEP-NC 밀링 데이터 모델 및 파트 프로그래밍)

  • Lee, Byeong-Eon;Jeong, Dae-Hyeok;Seo, Seok-Hwan
    • Proceedings of the Korean Operations and Management Science Society Conference
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    • 2004.05a
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    • pp.249-256
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    • 2004
  • STEP-NC 는 기존의 G-code 를 대체할 새로운 CNC 인터페이스 언어로써 현재 밀링 공정에 대해서는 국제 표준 단계에 있으며 조만간 기존의 G-code 를 대체할 것으로 기대된다. 그러므로 국내에서도 CAD-CAM 업체, CNC maker, 공작기계 제작 업체, 사용자 등 생산 환경 전반에 걸쳐 이에 대한 대응이 시급하다. 본 논문에서는 국내에서의 STEP-NC 의 promotion 을 위해 1) STEP-NC data model 을 분석하고, 2) 파트 프로그램의 작성 방법을 자세히 설명하고, 3) STEP AP203 CAD 파일로부터 STEP-NC 파트 프로그램을 생성하는 과정을 Korea STEP-NC 시스템을 통해서 설명하였다.

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Effect of Shape of External Corrosion in Pipeline on Failure Prediction (외부부식의 형상이 파이프라인의 파손예측에 미치는 영향)

  • Lee, Eok-Seop;Kim, Ho-Jung
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.23 no.11 s.170
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    • pp.2096-2101
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    • 1999
  • This paper presents the effect of shape of external corrosion in pipeline on failure prediction by using numerical simulation. The numerical study for the pipeline failure analysis is based on the FEM(Finite Element Method) with an elastic-plastic and large-deformation analysis. The predicted failure stress assessed for the simulated corrosion defects having different corroded shapes along the pipeline axis are compared with those by methods specified in ANSl/ASME B31G code and a modified B31G code.

Real-Time Surface Interpolator for Multiple Surface Machining Based on a Surface Cycle Command (복합 사이클 코드 지령 방식의 다중곡면 가공을 위한 실시간 곡면 보간기)

  • Koo, Tae-Hoon;Jee, Sung-Chul
    • Journal of the Korean Society for Precision Engineering
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    • v.24 no.8 s.197
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    • pp.97-107
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    • 2007
  • The present CNC machining system if without any CAM software has been limited to 2D or 2.5D plane cut using lines, arcs and curves. If the CNC is equipped with a surface interpolation module and a surface reorganizing module inside it, we can easily try 3D surface machining without aid of CAM software. The existing NURBS surface interpolator is simple and direct to use for a unit surface. However, it enables only machining of each reference surface individually even when machining a simple composite surface. In this paper, we propose a method which can unify and reorganize various reference surfaces with a newly defined NURBS surface cycle command: a multi-repetitive cycle command such as in a CNC turning center. We also introduce a reorganizing rule for reference surfaces using NURBS properties. The usefulness of the proposed method is verified through computer simulation.

Effect of External Corrosion in Pipeline on Failure Prediction

  • Lee, Ouk-Sub;Kim, Ho-Jung
    • International Journal of Precision Engineering and Manufacturing
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    • v.1 no.2
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    • pp.48-54
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    • 2000
  • This paper presents the effect of shape of external corrosion in pipeline on failure prediction by using a numerical simulation. The numerical study for the pipeline failure analysis is based on the FEM(Finite Element Method)with an elastic-plstic and large-deformation analysis. Corrosion pits and narrow corrosion grooves in pressurized pipeline were analysed. A failure criterion, based on the local stress state at the corrosion and a plastic collapse failure mechanism, is proposed. The predicted failure stress assessed for the simulated corrosion defects having different corroded shapes along the pipeline axis compared with those by methods specified in ANSI/ASME B31G code and a modified B31G code. It is concluded the corrosion geometry significantly affects the failure behavior of corroded pipeline and categorisation of pipeline corrosion should be considered in the development of new guidance for integrity assessment.

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Tilted-Ring Modeling of Warped Spiral Galaxies

  • Bae, Hyun-Jin;Chung, Ae-Ree;Jozsa, Gyula I.G.;Kim, Sung-Soo;Yoon, Suk-Jin
    • The Bulletin of The Korean Astronomical Society
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    • v.35 no.2
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    • pp.30.2-30.2
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    • 2010
  • A direct tilted-ring fitting method allows us to investigate kinematic structure of spiral galaxies. By employing the method to high-resolution HI data cubes, we can more easily trace warp characteristics of spiral galaxies than ever. In this contribution, we make use of TiRiFiC to VLA HI data cube of spiral galaxies in Virgo cluster, and present our preliminary yet interesting results. The TiRiFiC (Tilted-Ring-Fitting-Code) is publicly available code that provides 'best-fit' tilted-ring parameters (i.e. position angle and inclination) via chi-square minimization technique. We also discuss possible biases (e.g., resolution dependency) and its effect on our conclusions.

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CTF/DYN3D multi-scale coupled simulation of a rod ejection transient on the NURESIM platform

  • Perin, Yann;Velkov, Kiril
    • Nuclear Engineering and Technology
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    • v.49 no.6
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    • pp.1339-1345
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    • 2017
  • In the framework of the EU funded project NURESAFE, the subchannel code CTF and the neutronics code DYN3D were integrated and coupled on the NURESIM platform. The developments achieved during this 3-year project include assembly-level and pin-by-pin multiphysics thermal hydraulics/neutron kinetics coupling. In order to test this coupling, a PWR rod ejection transient was simulated on a MOX/UOX minicore. The transient is simulated using two different models of the minicore. In the first simulation, both codes model the core with an assembly-wise resolution. In the second simulation, a pin-by-pin fuel-centered model is used in CTF for the central assembly, and a pin power reconstruction method is applied in DYN3D. The analysis shows the influence of the different models on global parameters, such as the power and the average fuel temperature, but also on local parameters such as the maximum fuel temperature.

High volumes of data conversion based on Hadoop (Hadoop을 이용한 대용량 데이터 변환)

  • Lee, Kang Eun;Jeong, Min Jin;Jeong, Dabin;Kim, Sungsuk;Yang, Sun-Ok
    • Proceedings of the Korea Information Processing Society Conference
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    • 2019.05a
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    • pp.72-74
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    • 2019
  • Hadoop은 대용량 데이터의 분산 처리 응용을 지원하는 프레임워크이다. 이는 마스터 노드와 데이터 노드간에 Map-Reduce 과정을 거쳐 분산 처리를 지원한다. 이에 본 연구에서는 3D 프린팅을 위해 생성한 3D 모델을 프린터가 인식할 수 있는 G-code로 변환하는 작업을 Hadoop에서 수행하였다. 3D 모델은 대개 2차원 개체(페이셋)를 이용하여 표면을 표현하는데, 이 개체를 높이(Z 축)에 따라 슬라이싱한 후각 레이어별로 G-code를 생성하여야 한다. 우선 5대의 컴퓨터에 Hadoop 클러스터를 설치한 후, 대상 3D 모델에 다양한 속성값을 변경하면서 변환작업을 진행하여 Hadoop 프로그래밍의 장점을 확인할 수 있었다.

Advances for the time-dependent Monte Carlo neutron transport analysis in McCARD

  • Sang Hoon Jang;Hyung Jin Shim
    • Nuclear Engineering and Technology
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    • v.55 no.7
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    • pp.2712-2722
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    • 2023
  • For an accurate and efficient time-dependent Monte Carlo (TDMC) neutron transport analysis, several advanced methods are newly developed and implemented in the Seoul National University Monte Carlo code, McCARD. For an efficient control of the neutron population, a dynamic weight window method is devised to adjust the weight bounds of the implicit capture in the time bin-by-bin TDMC simulations. A moving geometry module is developed to model a continuous insertion or withdrawal of a control rod. Especially, the history-based batch method for the TDMC calculations is developed to predict the unbiased variance of a bin-wise mean estimate. The developed methods are verified for three-dimensional problems in the C5G7-TD benchmark, showing good agreements with results from a deterministic neutron transport analysis code, nTRACER, within the statistical uncertainty bounds. In addition, the TDMC analysis capability implemented in McCARD is demonstrated to search the optimum detector positions for the pulsed-neutron-source experiments in the Kyoto University Critical Assembly and AGN201K.

ON GENERALIZED ZERO-DIFFERENCE BALANCED FUNCTIONS

  • Jiang, Lin;Liao, Qunying
    • Communications of the Korean Mathematical Society
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    • v.31 no.1
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    • pp.41-52
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    • 2016
  • In the present paper, by generalizing the definition of the zero-difference balanced (ZDB) function to be the G-ZDB function, several classes of G-ZDB functions are constructed based on properties of cyclotomic numbers. Furthermore, some special constant composition codes are obtained directly from G-ZDB functions.