Results 11 to 20 of about 80,385 (278)
A ROBUST SECOND-ORDER MULTIPLE BALANCE METHOD FOR TIME-DEPENDENT NEUTRON TRANSPORT SIMULATIONS [PDF]
A second-order “Time-Dependent Multiple Balance” (TDMB) method for solving neutron transport problems is introduced and investigated. TDMB consists of solving two coupled equations: (i) the original balance equation (the transport equation integrated ...
Variansyah Ilham +2 more
doaj +1 more source
Multi-species Neutron Transport Equation [PDF]
The Neutron Transport Equation (NTE) describes the flux of neutrons through inhomogeneous fissile medium. Whilst well treated in the nuclear physics literature (cf. [9, 27]), the NTE has had a somewhat scattered treatment in mathematical literature with a variety of different approaches (cf. [8, 25]).
Alexander M. G. Cox +3 more
openaire +3 more sources
In this article, we present an application of the coarse-mesh Deterministic Spectral Method (SDM) to generate multigroup angular fluxes in one-dimensional spatial domains using the neutron transport stationary equation, in the formulation of discrete ...
F. T. C. S. Balbina +2 more
doaj +1 more source
The telegrapher's theory was used to develop a new formulation for the neutron noise equation. Telegrapher's equation is supposed to demonstrate a more realistic approximation for neutron transport phenomena, especially in comparison to the diffusion ...
Mona Bahrami, Naser Vosoughi
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Direct discrete method and its application to neutron transport problems [PDF]
The objective of this paper is to introduce a new direct method for neutronic calculations. This method, called direct discrete method, is simpler than the application of the neutron transport equation and more compatible with the physical meanings of ...
Vosoughi Naser +3 more
doaj +1 more source
Analysis of Kobayashi benchmark with indigenous Monte Carlo neutron transport code PATMOC
The solution of the neutron transport equation is the basic input for the reactor physics design of a nuclear reactor system. Because of the complexities of geometry and cross-section data, the neutron transport equation is generally solved using ...
Amod Kishore Mallick, Umasankari Kannan
doaj +1 more source
Solution of neutron-transport multigroup equations system in subcritical systems [PDF]
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
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
STUDY OF THE EIGENVALUE SPECTRA OF THE NEUTRON TRANSPORT PROBLEM IN PN APPROXIMATION [PDF]
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
Probing Mechanical and Chemical Instabilities in Neutron-Rich Matter [PDF]
The isospin-dependence of mechanical and chemical instabilities is investigated within a thermal and nuclear transport model using a Skyrme-type phenomenological equation of state for neutron-rich matter.
Akmal +49 more
core +2 more sources

