نتائج البحث

PARALLEL MESHLESS RADIAL BASIS FUNCTION COLLOCATION METHOD FOR NEUTRON DIFFUSION PROBLEMS

• Authors : Tayfun Tanbay

Subjects: paralel; ağsız; radyal baz fonksiyonu

• Source: Uludağ University Journal of The Faculty of Engineering, Vol 29, Iss 1, Pp 173-190 (2024)

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Parallel meshless radial basis function collocation method for neutron diffusion problems ; Nötron difüzyon problemleri için paralel ağsız radyal baz fonksiyonu kollokasyon yöntemi

• Authors : Tanbay, Tayfun; Tayfun

Subjects: Parallel; Meshless; Radial basis function

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Apply implicitly restarted Arnoldi method to solving eigenvalue problem and reducing dimensionality in neutron diffusion

• Authors : XIANG Zhaocai; CHEN Qiafeng; ZHAO Pengcheng

Subjects: neutron diffusion equation; implicitly restarted arnoldi method; proper orthogonal decomposition

• Source: He jishu, Vol 47, Iss 2, Pp 135-141 (2024)

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Calculation of Thermal Neutron Diffusion Length in a Light Water Media using MCNP Code

• Authors : M. Arkani

Subjects: mcnp code; neutron diffusion length; neutron flux

• Source: مجله علوم و فنون هسته‌ای, Vol 44, Iss 3, Pp 165-170 (2023)

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A solution for the neutron diffusion equation in the spherical and hemispherical reactors using the residual power series

• Authors : Ahmad El-Ajou; Mohammed Shqair; Ibrahim Ghabar

Subjects: neutron diffusion; power series; radial flux

• Source: Frontiers in Physics, Vol 11 (2023)

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A variational nodal formulation for multi-dimensional unstructured neutron diffusion problems

• Authors : Qizheng Sun; Wei Xiao; Xiangyue Li

Subjects: Variational nodal method; Unstructured mesh; Neutron diffusion equation

• Source: Nuclear Engineering and Technology, Vol 55, Iss 6, Pp 2172-2194 (2023)

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Solving the discretised neutron diffusion equations using neural networks

• Authors : Phillips, TRF; Heaney, CE; Chen, B

Subjects: convolutional neural network; finite difference method; finite volume method

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Solution of Neutron Diffusion Problem Based on COMSOL Multiphysics and Its Application Analysis on Micro Gas-cooled Reactor

• Authors : HUANG Zheng; YUAN Yuan; LIU Guoming

Subjects: htgr; micro gas-cooled reactor; neutron diffusion equation

• Source: Yuanzineng kexue jishu, Vol 57, Iss 3, Pp 565-575 (2023)

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An Efficient and Robust ILU(k) Preconditioner for Steady-State Neutron Diffusion Problem Based on MOOSE

• Authors : Yingjie Wu; Han Zhang; Lixun Liu

Subjects: preconditioning; JFNK; coloring algorithm

• Source: Energies, Vol 17, Iss 6, p 1499 (2024)

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Development of the S3-HACNEM Simulator Program in order to Solving the Forward and Adjoint Neutron Diffusion Equation for Rectangular Geometry Reactor Cores

• Authors : A. Kolali; D. Naghavi Dizaji; N. Vosoughi

Subjects: simulator; adjoint calculation; diffusion equation

• Source: مجله علوم و فنون هسته‌ای, Vol 45, Iss 1, Pp 21-28 (2024)

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