• Title/Summary/Keyword: G code

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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.

NUMERICAL CODE DEVELOPMENT OF THE MULTIPHASE FLOW AROUND AN UNDERWATER VEHICLE UNDER SUBMARINE WAKE. (후류중에 있는 수중운동체의 캐비테이션 유동 현상 및 유체력 변화 해석 코드 개발)

  • Park, S.I.;Ha, C.T.;Park, W.G.;Lee, K.C.
    • 한국전산유체공학회:학술대회논문집
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    • 2010.05a
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    • pp.115-121
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    • 2010
  • Cavitating flow is widely shown in many engineering systems, such as marine propellers, pump impellers, nozzles, injectors, torpedoes, etc. The present work focuses on the numerical analysis of the multiphase flow around the underwater vehicle which was launched from a submarine. The governing equation is the Navier-Stokes equation with a homogeneous mixture mode. The multiphase flow solver uses an implicit preconditioning scheme in curvilinear coordinate. For the code validation, the results from the present work are compared with the existing experimental and numerical results, and a reasonably good agrements are obtained. The multiphase flow around an underwater vehicle is simulated which includes submarine wake effects.

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The Behavior of Shock Wave through a Circular Tunnel around Supersonic Cylinder using FVS Upwind Scheme (FVS를 이용한 터널을 통과하는 초음속 실린더 주위의 충격파 거동 해석)

  • Ko M. H.;Shin C. H.;Park W. G.
    • 한국전산유체공학회:학술대회논문집
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    • 1999.11a
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    • pp.29-35
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    • 1999
  • A two-dimensional Euler code based on flux vector splitting scheme has been developed to simulate the behavior of supersonic shock wave over the cylinder. AF+ADI scheme was used for time integration. The sliding multiblock technique was implemented to handle the relative motion of the moving cylinder and the stationary tunnel. The code is validated with a problem of subsonic flow around a Naca-0012 airfoil. The Computation results show complex phenomena of the propagation of shock waves and the reflection as expansion wave at tunnel exit.

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Numerical Analysis of Sprays in the Combustion Chamber of Diesel Engine (디젤 분무 거동에 관한 수치 해석적 연구)

  • Cha K. S.;Choi J. W.;Park C. G.
    • Journal of computational fluids engineering
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    • v.5 no.1
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    • pp.8-13
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    • 2000
  • In this study, the spray models incorporated into the GTT code were tested for sprays injected in quiescent swirling gases and for the sprays impinging on a flat wall, and the validity of the models has been confirmed by comparing the calculated results with the experimental data. Using this code, the gas flow, spray behavior and fuel vapor distributions in the combustion chamber of a D.I engine have been numerically analyzed with respect to the constant injection pressure and the injection pressure varying with injection time.

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Numerical analysis of free surface flow s using least square/level-set method (최소자승법과 Level-set 방법을 이 용한 자유표면 유동의 수치해석)

  • Choi, Hyoung-G.
    • 한국전산유체공학회:학술대회논문집
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    • 2008.03b
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    • pp.565-567
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    • 2008
  • In the present study, a least square/level set based two-phase flow code has been developed using finite element discretization, which can be utilized for the analysis of a free surface flow problem in a complex geometry. Since the finite element method is employed for the spatial discretization of governing equations, an unstructured mesh can be naturally adopted for the level set simulation of a bubble-in-liquid flow without an additional load for the code development except that solution methods of the hyperbolic type redistancing and advection equations of the level set function should be devised in order to give a bounded solution on the unstructured mesh. For the discretization of hyperbolic type redistancing and advection equations, least square method is adopted. From the numerical experiments of the present study, it is shown that the proposed method is both robust and accurate.

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Excitation Enhancement Based on a Selective-Band Harmonic Model for Low-Bit-Rate Code-Excited Linear Prediction Coders (저전송률 코드여기 선형 예측 부호화기를 위한 선택적 대역 하모닉 모델 기반 여기신호 개선 알고리즘)

  • Lee, Mi-Suk;Kim, Hong-Kook;Choi, Seung-Ho;Kim, Do-Young
    • Speech Sciences
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    • v.11 no.2
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    • pp.259-269
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    • 2004
  • In this paper, we propose a new excitation enhancement technique to improve the speech quality of low bit-rate code-excited linear prediction (CELP) coders. The proposed technique is based on a harmonic model and it is employed only in the decoding process of speech coders without any additional bits. We develop the procedure of harmonic model parameter estimation and harmonic generation, and apply this technique to a current state-of-the-art low bit rate speech coder, ITU-T G.729 Annex D. Also, its performance is measured by using the ITU-T P.862 PESQ score and compared to those of the phase dispersion filter and the long-term postfilter applied to the decoded excitation. It is shown that the proposed excitation enhancement technique can improve the quality of decoded speech and provide better quality for male speech than other techniques.

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Optimum Radial Build of a Low Aspect Ratio Tokamak Reactor

  • Hong, B.G.;Hwang, Y.S.;Kang, J.S.
    • Proceedings of the Korean Vacuum Society Conference
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    • 2011.02a
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    • pp.397-397
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    • 2011
  • In a low aspect ratio (LAR) tokamak reactor with a superconducting toroidal field (TF) coil, the radial build of TF coil and the shield play a key role in determining the size of a reactor. For self-consistent determination of the reactor components and physics parameters, a system analysis code is coupled with one-dimensional radiation transport code. Conceptual design study of a compact superconducting LAR tokamak reactor with aspect ratio less than 2.5 was conducted and the optimum radial build was identified. It is shown that the use of an improved shielding material and high temperature superconducting magnets with high critical current density opens up the possibility of a fusion power plant with compact size and small re-circulating power simultaneously at low aspect ratio, and that by using an inboard neutron reflector instead of breeding blanket, tritium self-sufficiency is possible with outboard blanket only and thus compact sized reactor is viable.

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Arc Flash Hazard Analysis (전력기술.정보 - 아크 플래시 위험 분석)

  • Lee, Seong-U
    • Electric Engineers Magazine
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    • s.350
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    • pp.21-25
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    • 2011
  • 전기설비에 접근하여 활선작업을 수행하는 과정에서 "안전조치, 작업공구, 먼지, 분진, 쥐, 절연" 등의 문제로 기인하는 단락사고가 발생하면 플라즈마(plasma) 아크 형태의 전기적 방전이 일어나므로, 아크 플래시 위험에 노출된 작업자는 심각한 화상은 물론 생명에 위험을 초래할 수 있다. 이러한 위험으로부터 근로자를 보호하기 위하여 IEEE Std. 1584에 수행절차와 방법에 대하여 상세히 해설하고 있고, NFPA 70E는 보호기준 등을 규정하고 있다. 국내에서도 이 기준 등을 참고하여 산업안전기준에 관한 규칙에 의거, 활선작업 및 활선근접작업에 관한 기술지침(KOSHA CODE E-3G-2005)과 난연성 전기 작업복 선정에 관한 기술지침(KOSHA CODE E-32-2006을 규정하고 있다. 그러나 국내에서는 외국 기업 일부를 제외하고는 아크 플래시 위험분석 업무를 실무에 적용하는 사례를 찾아보기 어렵다. 또한 적용 범위에 있어서도 난연성 전기 작업복 선정에 관한 기술지침을 600V 이상의 활선작업 및 활선근접 작업시만 착용하도록 한정한 것은 아크 플래시 위험에 대한 보호가 충분하지 않은 것으로 판단된다. 오히려 고압보다도 저압회로 고장 지점의 최소 단락전류에서 차단기의 동작시간이 지연되는 경우, 사고에너지를 더 증가시키기 때문에 위험성과 빈도는 높아질 수 있다 이와 관련하여 본문에서는 "아크 플래시 위험" 분석 및 평가방법에 대하여 살펴보기로 한다.

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Development of RETRAN-03/MOV Code for Thermal-Hydraulic Analysis of Nuclear Reactor Under Mowing Conditions

  • Kim, Jae-Hak;Park, Good-Cherl
    • Nuclear Engineering and Technology
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    • v.28 no.6
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    • pp.542-550
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    • 1996
  • Nuclear ship reactors have several features different from land-based PWR's. Especially, effects of ship motions on reactor thermal-hydraulics and good load following capability for abrupt load changes are essential characteristics of nuclear ship reactors. This study modified the RETRAN-03 to analyze the thermal-hydraulic transients under three-dimensional ship motions, named RETRAN-03/MOV in order to apply to future marine reactors. First Japanese nuclear ship MUTSU reactor have been analyzed under various ship motions to verify this code. Calculations have been peformed under rolling, heaving and stationary inclination conditions during normal operation. Also, the natural circulation has been analyzed, which can provide the decay heat removal to ensure the passive safety of marine reactors. As results, typical thermal-hydraulic characteristics of marine reactors such as flow rate oscillations and S/G water level oscillations have been successfully simulated at various conditions.

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A Study of the Preventive Diagnostic Algorithm of Gas in Oil for Power Transformer (가스분석을 이용한 변압기의 이상진단 알고리즘 연구)

  • Choi, I.H.;Kweon, D.J.;Jung, G.J.;You, Y.P.;Sun, J.H.;Kim, K.H.
    • Proceedings of the KIEE Conference
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    • 2000.07c
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    • pp.1903-1905
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    • 2000
  • Power transformers have a tendency of ultra-high voltage capacity as power demand increases day after day KEPCO also will have plan to supply transmission power from 345KV to 765KV in the early of 2000. Therefore, the fault by insulation destruction gives rise to large area of power failure in huge capacity transformers. On-line predictive diagnostics is very important in power transformers because of economic loss and its spreading effect. This study presents the algorithm for transformer oil analysis used KEPCO code, IEC code, gas pattern method and Dornenburg & Roger Ratio method. We also describe the MMI display of expert system programmed by Element Expert Tool(Neuron Data Inc.).

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