Results 1 to 10 of about 80,385 (278)

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

Constraining gravity with hadron physics: neutron stars, modified gravity and gravitational waves [PDF]

open access: yesEPJ Web of Conferences, 2017
The finding of Gravitational Waves (GW) by the aLIGO scientific and VIRGO collaborations opens opportunities to better test and understand strong interactions, both nuclear-hadronic and gravitational.
Llanes-Estrada Felipe J.
doaj   +3 more sources

$ L^2 $ diffusive expansion for neutron transport equation

open access: yesCommunications in Analysis and Mechanics
One of the most classical and fundamental mathematical problems in kinetic theory is to study the diffusive limit of the neutron transport equation. As $ {\varepsilon}{\rightarrow}0 $, the phase space density $ u^{{\varepsilon}}({x}, {w}) $
Yan Guo, Lei Wu
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

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

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

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

Simulation of the burnup in cell calculation using the wimsd-5b code considering different nuclear data libraries

open access: yesBrazilian Journal of Radiation Sciences, 2021
This work proposes to implement the cell calculation considering the fuel burning using the WIMSD-5B code. The cell calculation procedure allows determining the nuclear parameters present in the multi-group neutron diffusion equation and for this purpose
Desirée Yael de Sena Tavares   +2 more
doaj   +1 more source

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