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A Robust, Relaxation–Free Multiphysics Iteration Scheme for CMFD–Accelerated Neutron Transport k–Eigenvalue Calculations–I: Theory

Nuclear science and engineering, 2021
This paper presents a new robust scheme for coupled physics nuclear reactor calculations. We focus specifically on high-fidelity whole-core transport calculations with coarse mesh finite difference (CMFD) coupled to thermal hydraulics.
Qicang Shen, B. Kochunas
semanticscholar   +1 more source

Precise localization of neutron noise sources based on transport theory and comparison with diffusion theory

, 2021
In an attempt to explore the significance of transport theory in neutron noise, localization of a noise source by Green’s function based on transport theory is investigated.
M. Bahrami, N. Vosoughi
semanticscholar   +1 more source

On the Ronen Method in Simple 1-D Geometries for Neutron Transport Theory Solutions

, 2020
In this work, we apply the Ronen method to obtain highly-accurate approximations to the solution of the neutron transport equation in simple homogeneous problems. Slab, cylindrical, and spherical geometries are studied.
D. Tomatis, R. Gross, E. Gilad
semanticscholar   +1 more source

3D whole-core neutron transport simulation using 2D/1D method via multi-level generalized equivalence theory based CMFD acceleration

Annals of Nuclear Energy, 2018
A new 2D/1D method with multi-level generalized equivalence theory (GET) based coarse mesh finite difference (CMFD) acceleration was proposed for the whole core transport calculation in this paper.
C. Hao   +5 more
semanticscholar   +1 more source

Neutron Transport Theory

Nuclear Science and Engineering, 1975
(1975). Neutron Transport Theory. Nuclear Science and Engineering: Vol. 58, No. 3, pp. 340-340.
openaire   +1 more source

Neutron stochastic transport theory with delayed neutrons

Annals of Nuclear Energy, 1987
Abstract In this paper we have developed the stochastic transport theory with delayed neutrons. From this theory, the Boltzmann transport equation with delayed neutrons for the average flux emerges in a natural way without recourse to any approximation.
J.L. Muñoz-Cobo, G. Verdú
openaire   +1 more source

Fixed Point Theory in MR-Metric Spaces Fundamental Theorems and Applications to Integral Equations and Neutron Transport

European Journal of Pure and Applied Mathematics
This paper establishes a comprehensive framework for fixed point theory in MR-metric spaces,a generalization of standard metric spaces that incorporates three-point relations.
T. Qawasmeh, Abed Al-Rahman M. Malkawi
semanticscholar   +1 more source

Neutron Transport Theory

1971
The general concept of “transport theory” refers to a physical process whereby a particle migrates through a lattice composed of scattering centers. The first important part of this concept is that the migrating material can be considered to be a particle, in the case of interest a neutron which changes its speed of travel as its total energy changes ...
openaire   +1 more source

Neutron Transport: Theory, Modeling, and Computations

Graduate Texts in Physics, 2023
R. M. Kuridan
semanticscholar   +1 more source

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