• 제목/요약/키워드: Neutron Transport Equation

검색결과 33건 처리시간 0.02초

Variational nodal methods for neutron transport: 40 years in review

  • Zhang, Tengfei;Li, Zhipeng
    • Nuclear Engineering and Technology
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    • 제54권9호
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    • pp.3181-3204
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    • 2022
  • The variational nodal method for solving the neutron transport equation has evolved over 40 years. Based on a functional form of the Boltzmann neutron transport equation, the method now comprises a complete set of variants that can be employed for different problems. This paper presents an extensive review of the development of the variational nodal method. The emphasis is on summarizing the whole theoretical system rather than validating the methodologies. The paper covers the variational nodal formulation of the Boltzmann neutron transport equation, the Ritz procedure for various application purposes, the derivation of boundary conditions, the extension for adjoint and perturbation calculations, and treatments for anisotropic scattering sources. Acceleration approaches for constructing response matrices and solving the resulting system of algebraic equations are also presented.

A new approach for calculation of the neutron noise of power reactor based on Telegrapher's theory: Theoretical and comparison study between Telegrapher's and diffusion noise

  • Bahrami, Mona;Vosoughi, Naser
    • Nuclear Engineering and Technology
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    • 제52권4호
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    • pp.681-688
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    • 2020
  • The telegrapher's theory was used to develop a new formulation for the neutron noise equation. Telegrapher's equation is supposed to demonstrate a more realistic approximation for neutron transport phenomena, especially in comparison to the diffusion theory. The physics behind such equation implies that the signal propagation speed is finite, instead of the infinite as in the case of ordinary diffusion. This paper presents the theory and results of the development of a new method for calculation of the neutron noise using the telegrapher's equation as its basis. In order to investigate the differences and strengths of the new method against the diffusion based neutron noise, a comparison was done between the behaviors of two methods. The neutron noise based on SN transport considered as a precision measuring point. The Green's function technique was used to calculate the neutron noise based on telegrapher's and diffusion methods as well as the transport. The amplitude and phase of Green's function associated with the properties of the medium and frequency of the noise source were obtained and their behavior was compared to the results of the transport. It was observed, the differences in some cases might be considerable. The effective speed of propagation for the noise perturbations were evaluated accordingly, resulting in considerable deviations in some cases.

단순 우성 중성자 수송방정식을 이용한 노달 수송해법 (Nodal Transport Methods Using the Simplified Even-Parity Neutron Transport Equation)

  • 노태완
    • 방사성폐기물학회지
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    • 제16권2호
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    • pp.211-221
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    • 2018
  • 중성자 확산방정식에 대해 개발된 노달 확산이론을 단순 우성 중성자 수송방정식에 적용할 수 있는 노달 수송이론을 제시한다. 노달이론으로 다항식전개 노달법과 해석함수전개 노달법을 채택하였고 단순 우성 수송방정식은 수송방정식에 대한 합리적 근사이며 기존의 노달해법이 방향 차분된 단순 우성 수송방정식에 정확히 적용될 수 있음을 수치적으로 확인하였다. 본 연구에서는 방법론 개발이 목적이므로 노드 당 최소한의 미지수를 정의하여 사용했지만 미지수를 추가함으로써 정확도를 증가시킬 수 있음은 기존의 노달 확산이론의 경우와 같다. 즉 중성자 수송방정식에 대해 노달이론을 적용하여 소격격자에 대해 계산 정확성이 확보되고 이는 결국 계산 효율성 증대로 나타난다.

다차원 2계 중성자 수송방정식의 방향근사를 위한 영역상수법 (Piecewise-Constant Method for Angular Approximation for the Second-Order Multidimensional Neutron Transport Equations)

  • 노태완
    • 에너지공학
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    • 제16권1호
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    • pp.46-52
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    • 2007
  • 특정한 방향에 대해 방향중성자속(angular neutron flux)을 정의하는 방향차분 방정식(discrete-ordinates or $S_{N}$ equation)과 달리 방향변수를 구분된 방향영역에 대하여 적분한 값을 사용하고, 해당 방향영역 내에서 방향중성자속이 일정하다고 가정하는 영역상수법(piecewise-constant method)을 개발하였다. 기존 방향차분법과 본 연구에서 개발된 영역상수법을 1계 수송방정식(1'st-order Boltzmann transport equation)과 2계 우성 방정식(even-parity equation)에 적용하여 방향차분 방정식인 $S_{N}$ 방정식과 유사 방향차분방정식($S_{N}$-like equation)인 $PC_{N}$ 방정식을 유도하였다. 우성 방정식에 영역상수법을 적용한 경우 기존 방향차분법의 단점인 광첨두 현상(ray effect)이 현저히 감소함을 확인하였는데 이는 우성 방정식의 혼합 미분항의 기여도가 작아지기 때문인 것으로 판단된다. 이러한 이론은 우성 방정식에서 혼합 미분항이 제거된 단순우성 방정식(simplified even-parity equation)을 사용하는 경우 광첨두 현상이 완전 제거 또는 극단적으로 감소되었던 이전의 결과를 이론적으로 설명한다.

Development of the Discrete-Ordinates, Nodal Transport Methods Using the Simplified Even-Parity Neutron Transport Equation

  • Noh, Taewan
    • Nuclear Engineering and Technology
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    • 제32권6호
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    • pp.605-617
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    • 2000
  • Nodal transport methods are studied for the solution of two dimensional discrete-ordinates, simplified even-parity transport equation(SEP) which is known to be an approximation to the true transport equation. The polynomial expansion nodal method(PEN) and the analytic function expansion nodal method(AFEN)which have been developed for the diffusion theory are used for the solution of the discrete-ordinates form of SEP equation. Our study shows that while the PEN method in diffusion theory can directly be converted without complication, the AFEN method requires a theoretical modification due to the nonhomogeneous property of the transport equation. The numerical results show that the proposed two methods work well with the SEP transport equation with higher accuracies compared with the conventional finite difference method.

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확산 가속법을 이용한 SAAF 중성자 수송 방정식의 해법 (Solution of the SAAF Neutron Transport Equation with the Diffusion Synthetic Acceleration)

  • 노태완;김성진
    • 에너지공학
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    • 제17권4호
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    • pp.233-240
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    • 2008
  • 최근 새로운 2계 자기 수반형(self-adjoint) 중성자 수송 방정식으로 기존의 우성 및 기성 수송 방정식 외에 SAAF(Self-Adjoint Angular Flux) 수송 방정식이 소개되어, 이에 대한 적절한 경계조건, 수치해법, 정확도 등에 관한 논의가 활발히 진행되고 있다. 본 연구에서는 SAAF 수송 방정식의 수학적, 물리적 의미를 고찰하고 기존의 우성 및 기성 수송 방정식과의 연관성을 명확히 하였으며, Boltzmann 수송 방정식의 1계 차분식에서 2계의 SAAF 수송 방정식의 차분식을 유도하는 방법을 확산 가속법(diffusion synthetic acceleration method)과 함께 소개하였다. 유도된 SAAF 차분법이 계산 효율성과 수송해의 정확도를 증가시킴을 수치결과로 확인하였다.

A New Acceleration Method of Additive Angular Dependent Rebalance with Extrapolation for Discrete Ordinates Transport Equation

  • Park, Chang-Je;Cho, Nam-Zin
    • Nuclear Engineering and Technology
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    • 제34권4호
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    • pp.314-322
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    • 2002
  • A new extrapolation method is developed and applied to the additive angular dependent rebalance (AADR) acceleration for discrete ordinates neutron transport calculations. With this extrapolation, the convergence of AADR solution for distinct discretizations between the high- order and low-order equations is remarkably improved and thus the “inconsistent discretization problem” is resolved. Fourier analysis is also performed to find the optimal extrapolation and weighting parameters, which give the smallest spectral radius. The numerical tests demonstrate that the AADR with extrapolation works well as predicted by the Fourier analysis.

ANALOG COMPUTING FOR A NEW NUCLEAR REACTOR DYNAMIC MODEL BASED ON A TIME-DEPENDENT SECOND ORDER FORM OF THE NEUTRON TRANSPORT EQUATION

  • Pirouzmand, Ahmad;Hadad, Kamal;Suh, Kune Y.
    • Nuclear Engineering and Technology
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    • 제43권3호
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    • pp.243-256
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    • 2011
  • This paper considers the concept of analog computing based on a cellular neural network (CNN) paradigm to simulate nuclear reactor dynamics using a time-dependent second order form of the neutron transport equation. Instead of solving nuclear reactor dynamic equations numerically, which is time-consuming and suffers from such weaknesses as vulnerability to transient phenomena, accumulation of round-off errors and floating-point overflows, use is made of a new method based on a cellular neural network. The state-of-the-art shows the CNN as being an alternative solution to the conventional numerical computation method. Indeed CNN is an analog computing paradigm that performs ultra-fast calculations and provides accurate results. In this study use is made of the CNN model to simulate the space-time response of scalar flux distribution in steady state and transient conditions. The CNN model also is used to simulate step perturbation in the core. The accuracy and capability of the CNN model are examined in 2D Cartesian geometry for two fixed source problems, a mini-BWR assembly, and a TWIGL Seed/Blanket problem. We also use the CNN model concurrently for a typical small PWR assembly to simulate the effect of temperature feedback, poisons, and control rods on the scalar flux distribution.

The Variational Method Applied to the Neutron Transport Equation

  • Kim, Sang-Won;Pac, Pong-Youl
    • Nuclear Engineering and Technology
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    • 제3권4호
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    • pp.203-208
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    • 1971
  • Noether의 이론을 1차원의 중성자 수송방정식에 적용하였다. 1차원의 Boltzmann방정식의 functional을 불변케 하는 변환을 구했으며 이결과 중성자속과 그의 Adjoint 중성자속의 곱이 보존된다는 법칙을 유도하였다. 이 보존법칙으로부터 1차원의 Boltzmann방정식의 가능한 해의 형태를 얻었고 이것을 이미 알려진 해와 비교하였다.

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방향차분법을 적용한 시간종속 복사 열전달 계산 (Application of Discrete-Ordinate Method to the Time Dependent Radiative Heat Transfer Calculations)

  • 노태완
    • 에너지공학
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    • 제15권4호
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    • pp.250-255
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    • 2006
  • 원자력 분야에서 중성자 수송계산을 위해 개발되어 널리 사용되는 방향차분법을 시간 종속 복사 열전달식의 해를 구하는데 적용하였다. 광자의 방향별 밀도를 자체수반형 2계 편미분방정식으로 나타내어 해의 안정성을 높였고 매질의 온도방정식의 비선형성은 다단계 선형화법을 사용하여 근사하였다. 본 연구에서 개발된 해법을 전형적인 Marshak wave 문제에 적용하였고 계산 결과를 기존의 Monte Carlo의 계산결과와 비교하여 그 우월성을 보였다.