نتائج البحث

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

• Authors : Wu, Yingjie¹ (AUTHOR) ; Zhang, Han¹ (AUTHOR) ; Liu, Lixun¹ (AUTHOR)

• Source: Energies (19961073). Mar2024, Vol. 17 Issue 6, p1499. 16p.

تفاصيل العنوان

PARALLEL MESHLESS RADIAL BASIS FUNCTION COLLOCATION METHOD FOR NEUTRON DIFFUSION PROBLEMS.

• Authors : TANBAY, Tayfun¹

• Source: Uludag University Journal of the Faculty of Engineering (UUJFE). 2024, Vol. 29 Issue 1, p173-189. 17p.

تفاصيل العنوان

Residual resampling-based physics-informed neural network for neutron diffusion equations

• Authors : Zhang, Heng; He, Yun-Ling; Liu, Dong

Subjects: Computer Science - Machine Learning

تفاصيل العنوان

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)

تفاصيل العنوان

Using Laplace Residual Power Series Method in Solving Coupled Fractional Neutron Diffusion Equations with Delayed Neutrons System.

• Authors : Shqair, Mohammed¹ (AUTHOR) ; Ghabar, Ibrahim¹ (AUTHOR); Burqan, Aliaa¹ (AUTHOR)

• Source: Fractal & Fractional. Mar2023, Vol. 7 Issue 3, p219. 11p.

تفاصيل العنوان

A posteriori error estimates for mixed finite element discretizations of the Neutron Diffusion equations.

• Authors : Ciarlet, Patrick¹; Do, Minh Hieu²; Madiot, François²

• Source: ESAIM: Mathematical Modelling & Numerical Analysis (ESAIM: M2AN). Jan/Feb2023, Vol. 57 Issue 1, p1-27. 27p.

تفاصيل العنوان

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)

تفاصيل العنوان

Reduced basis method for non-symmetric eigenvalue problems: application to the multigroup neutron diffusion equations

• Authors : Taumhas, Yonah Conjungo; Dusson, Geneviève; Ehrlacher, Virginie

Subjects: Mathematics - Numerical Analysis

تفاصيل العنوان

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)

تفاصيل العنوان

On the uncertainty analysis of the data-enabled physics-informed neural network for solving neutron diffusion eigenvalue problem

• Authors : Yang, Yu; Gong, Helin; Yang, Qihong

Subjects: Computer Science - Machine Learning; Physics - Data Analysis, Statistics and Probability

تفاصيل العنوان