Results 1 to 10 of about 4,488 (165)

Numerical Approximation for Fractional Neutron Transport Equation [PDF]

open access: yesJournal of Mathematics, 2021
Fractional neutron transport equation reflects the anomalous transport processes in nuclear reactor. In this paper, we will construct the fully discrete methods for this type of fractional equation with Riesz derivative, where the generalized WENO5 ...
Zhengang Zhao, Yunying Zheng
doaj   +3 more sources

Existence and Uniqueness Theorems for the Neutron Transport Equation [PDF]

open access: yesJournal of Mathematical Physics, 1963
In an attempt to understand the conditions under which the neutron transport equation has solutions, and the properties of those solutions, a number of existence and uniqueness theorems are proved. One finds that the properties of the solution are closely related to the boundedness of the source as well as to certain velocity-space integrals of the ...
P F Zweifel, Case K M, Zweifel P F
exaly   +3 more sources

COMPARISON OF CHEBYSHEV AND ANDERSON ACCELERATIONS FOR THE NEUTRON TRANSPORT EQUATION [PDF]

open access: yesEPJ Web of Conferences, 2021
This work focuses on the k-eigenvalue problem of the neutron transport equation. The variables of interest are the largest eigenvalue (keff) and the corresponding eigenmode is called the fundamental mode.
Calloo Ansar   +2 more
doaj   +3 more sources

A splitting iterative method for solving the neutron transport equation

open access: yesMathematical 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
doaj   +3 more sources

Monte Carlo Methods for the Neutron Transport Equation [PDF]

open access: yesSIAM/ASA Journal on Uncertainty Quantification, 2022
This paper continues our treatment of the Neutron Transport Equation (NTE) building on the work in [arXiv:1809.00827v2], [arXiv:1810.01779v4] and [arXiv:1901.00220v3], which describes the flux of neutrons through inhomogeneous fissile medium. Our aim is to analyse existing and novel Monte Carlo (MC) algorithms, aimed at simulating the lead eigenvalue ...
Alexander M. G. Cox   +3 more
openaire   +3 more sources

ANALYSIS OF TIME-EIGENVALUE AND EIGENFUNCTIONS IN THE CROCUS BENCHMARK [PDF]

open access: yesEPJ Web of Conferences, 2021
Time-dependent neutron transport in non-critical state can be expressed by the natural mode equation. In order to estimate the dominant eigenvalue and eigenfunction of the natural mode, CEA had extended the α-k method and developed the generalized ...
Nauchi Yasushi   +2 more
doaj   +1 more source

Influence of the spatial grid type on the result of calculating the neutron fields in the nuclear power plant shielding [PDF]

open access: yesNuclear Energy and Technology, 2023
The paper considers the influence of the spatial grid type on the result of solving the equation of neutron transport in the nuclear power plant (NPP) shielding.
Olga V. Nikolaeva   +4 more
doaj   +3 more sources

Implementation of the time dependent neutron transport algorithm in 2D utilizing modular ray tracing by method of characteristic framework [PDF]

open access: yesمجله علوم و فنون هسته‌ای, 2023
This paper discusses the implementation of an algorithm for solving 2D time-dependent neutron transport equations in heterogeneous media. A novel modular ray tracing algorithm where neutrons are allowed to travel a longer path before being removed from ...
S. Ghaseminejad   +3 more
doaj   +1 more source

Variational nodal methods for neutron transport: 40 years in review

open access: yesNuclear Engineering and Technology, 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 ...
Tengfei Zhang, Zhipeng Li
doaj   +1 more source

Transport theory and systems theory [PDF]

open access: yesNuclear Technology and Radiation Protection, 2005
The simulation of singular nonlinear transport equation is obtained via corresponding neutron or photon kinetic equation. The conditions for convergence of the non stationary transport process to ward the pure dif fusion across the equilibriums are ...
Rastović Danilo
doaj   +1 more source

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