Results 61 to 70 of about 80,518 (195)
Approximate Solution to Neutron Transport Equation with Linear Anisotropic Scattering [PDF]
Journal of Nuclear Science and Technology, 1983 A method to obtain an approximate solution to the transport equation, when both sources and collisions show a linearly anisotropic behavior, is outlined and the possible implications for numerical calculations in applied neutronics as well as shielding evaluations are investigated. The form of the differential system of equations taken by the method is
COPPA, Gianni, RAVETTO, PIERO, SUMINI M.
openaire +2 more sources
Pin-by-pin Calculation of Reactor Core-Based on Quasi-diffusion in Rectangular Grid
Yuanzineng kexue jishu, 2023 Physical calculations of reactor cores are fundamental for reactor core design and nuclear safety analysis. The second generation of core calculation theory and methods based on advanced component homogenization theory and modern coarse grid block ...
YAN Jiangtao;LIU Kun;ZHUANG Kun;WANG Senshan;ZHANG Kaihui;ZHANG Xinxin
doaj
Optimal Monte Carlo particle splitting for neutron transport equation [PDF]
EPJ Web of ConferencesGlobal tallying problem is hard to be solved efficiently when using Monte carlo method to simulate neutron transport equation, especially for sys- tem with big scale and/or strong imbalanced characteristics.
ShangGuan DanHua +4 more
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The ORNL-SNAP shielding program [PDF]
, 1972 The effort in the ORNL-SNAP shielding program is directed toward the development and verification of computer codes using numerical solutions to the transport equation for the design of optimized radiation shields for SNAP power systems.
Clifford, C. E. +3 more
core +1 more source
Connecting the Pygmy Dipole Resonance to the neutron skin
, 2013 We study the correlation between the neutron skin development and the low-energy dipole response associated with the pygmy dipole resonance (PDR) in connection with the properties of symmetry energy.
Baran, V. +4 more
core +1 more source
$ L^2 $ diffusive expansion for neutron transport equation
Communications in Analysis and Mechanics14 pages, 2 ...
Guo, Yan, Wu, Lei
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Spectral Method for 1-D Neutron Transport Equation
Journal of Scientific ComputingIn this paper, we present an efficient fully spectral approximation scheme for exploring the one-dimensional steady-state neutron transport equation. Our methodology integrates the spectral-(Petrov-)Galerkin scheme in the spatial dimension with the Legendre-Gauss collocation scheme in the directional dimension.
Haonan Zhang, Huiyuan Li, Zhimin Zhang
openaire +2 more sources
A splitting iterative method for solving the neutron transport equation
Mathematical Modelling and Analysis, 2009 This paper presents an iterative method based on a self‐adjoint and m‐accretive splitting for the numerical treatment of the steady state neutron transport equation.
Onana Awono, Jacques Tagoudjeu
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Validity and regularization of classical half-space equations
, 2016 Recent result [Wu and Guo, Comm. Math. Phys., 2015] has shown that over the 2D unit disk, the classical half-space equation (CHS) for the neutron transport does not capture the correct boundary layer behaviour as long believed. In this paper we develop a
Li, Qin, Lu, Jianfeng, Sun, Weiran
core +1 more source
The eigenvalues of one-speed neutrons in a slab with forward and backward scattering
Tehnički Glasnik, 2019 The eigenvalue spectrum is studied for one-speed neutrons in a slab with forward and backward scattering. First, the transport equation describing the interaction of neutrons in a system with general geometry is given.
Ökkeş Ege, Hakan Öztürk
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