Results 21 to 30 of about 6,219 (301)

On the boundary conditions for the neutron transport equation [PDF]

open access: yesThe European Physical Journal Plus, 2020
The solution of the linear transport equation used for the study of neutral particle fields requires the imposition of appropriate boundary conditions. The choice of the conditions to impose for an infinite medium is not straightforward. The question has been given different formulations in the literature with various justifications based on some ...
P. Saracco   +3 more
openaire   +2 more sources

Solution of neutron-transport multigroup equations system in subcritical systems [PDF]

open access: yesNuclear Energy and Technology, 2018
An iteration method has been implemented to solve a neutron transport equation in a multigroup diffusion approximation. A thermoelectric generator containing plutonium dioxide, used as a source of thermal and electric power in spacecraft, was studied.
Igor V. Shamanin   +4 more
doaj   +3 more sources

Bulk Density Response and Experimental Study of Pulsed Neutron-Gamma Density Logging

open access: yesFrontiers in Earth Science, 2022
The pulsed neutron-gamma density logging technique is used to measure the bulk density of formations based on the detection of gamma rays from the inelastic scattering of neutrons in the formations.
Hu Wang   +6 more
doaj   +1 more source

Topics in Core-Collapse Supernova Theory: The Formation of Black Holes and the Transport of Neutrinos [PDF]

open access: yes, 2012
Core-Collapse Supernovae are one of the most complex astrophysical systems in the universe. They deeply entwine aspects of physics and astrophysics that are rarely side by side in nature.
O'Connor, Evan Patrick
core   +1 more source

Laplace-transform-based method to calculate back-reflected radiance from an isotropically scattering half-space [PDF]

open access: yes, 1997
We present a method to determine the back-reflected radiance from an isotropically scattering half-space with matched boundary. This method has the advantage that it leads very quickly to the relevant equations, the numerical solution of which is also ...
Rinzema, K.,   +5 more
core   +1 more source

Neutrino treatment in multidimensional astrophysical simulations : a new spectral scheme [PDF]

open access: yes, 2014
Neutrinos play a central role in modern physics and astrophysics. Their extremely weak interaction rate with baryons and other leptons makes their detection on the Earth difficult and challenging.
Perego, Albino
core   +1 more source

STUDY OF THE EIGENVALUE SPECTRA OF THE NEUTRON TRANSPORT PROBLEM IN PN APPROXIMATION [PDF]

open access: yesEPJ Web of Conferences, 2021
The study of the steady-state solutions of neutron transport equation requires the introduction of appropriate eigenvalues: this can be done in various different ways by changing each of the operators in the transport equation; such modifications can be ...
Saracco P.   +4 more
doaj   +1 more source

Verification of the Discrete Ordinates Goal-Oriented Multi-Collision Source Algorithm with Neutron Streaming Problems

open access: yesEnergies, 2022
The shielding calculation of neutron streaming problems with ducts is characterized by the strong anisotropy of angular flux, which poses a challenge for the analysis of nuclear installations.
Xinyu Wang   +3 more
doaj   +1 more source

Numerical analysis of the neutron multigroup $SP_N$ equations

open access: yesComptes Rendus. Mathématique, 2021
The multigroup neutron $SP_N$ equations, which are an approximation of the neutron transport equation, are used to model nuclear reactor cores. In their steady state, these equations can be written as a source problem or an eigenvalue problem.
Jamelot, Erell, Madiot, François
doaj   +1 more source

PARTIAL NEUTRON TRANSPORT EQUATIONS

open access: yesPROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. SERIES: NUCLEAR AND REACTOR CONSTANTS, 2019
To analyze the spatial kinetics of the reactor, a system of equations for the spatial kinetics of the reactor, consisting of two equations, is usually used. One of them describes the behavior of the neutron flux density, and the second describes the behavior of the precursors of delayed neutrons.
I Chernova, V Bereznev, E Seleznev
openaire   +1 more source

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