Results 251 to 260 of about 6,219 (301)

Individualized Dose-volume Reconstruction Workflow for the Normal Tissues of Pediatric Patients Treated with Passive Scattering Proton Therapy. [PDF]

Radiat Res
Griffin KT, Schuemann J, McNamara AL, Morató S, Joseph K, Esposito CE, Shin J, Mille MM, Jung JW, Lee C, Kitahara CM, Gibson TM, Berrington de González A, Yock TI, Paganetti H, Lee C.   +15 more
europepmc   +1 more source

Comparison of time-of-flight and MIEZE neutron spectroscopy of H₂O. [PDF]

J Appl Crystallogr
Beddrich L, Jochum JK, Bender P, Spitz L, Wendl A, Franz C, Busch S, Juranyi F, Pfleiderer C, Soltwedel O.   +9 more
europepmc   +1 more source

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Neutron transport equation

2021
Liangzhi Cao
exaly   +2 more sources

On the stochastic nonlinear neutron transport equation

Proceedings of the Royal Society of Edinburgh: Section A Mathematics, 1992
SynopsisThe probability that a neutron leads to a divergent chain reaction in a nuclear reactor is governed by a nonlinear integro-partial-differential equation [1]. A model case of this equation was completely analysed by Pazy and Rabinowitz [2,3].
Mustapha Mokhtar-Kharroubi
openaire   +2 more sources

Stability of P_2 Methods for Neutron Transport Equation

Journal of Partial Differential Equations, 2002
Summary: The \(P_2\) approximation to the one-group planar neutron transport theory is discussed. The stability of the solutions for \(P_2\) equations with general boundary conditions, including the Marshak boundary condition, is proved. Moreover, the stability of the upwind difference scheme for the \(P_2\) equation is demonstrated.
Yuan, Guangwei, Shen, Zhijun, Shen, Longjun, Zhou, Yulin   +3 more
openaire   +2 more sources

Transport equation with delayed neutrons

Transport Theory and Statistical Physics, 1990
Abstract In nuclear fission reactor, the decay constant of delayed neutron will often determine the time behavior of the neutron population in a subcritical system or supercritical system or in a critical system in which a neutron source or cross section change with time.
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Eigenvalues of the neutron transport equation

Proceedings of the Physical Society, 1965
Results are given of the eigenvalues obtained for the neutron pulsed-source and diffusion-length problems using the gas kernel. Three methods of solution are reported: the diffusion approximation, the spherical harmonic (P3) approximation and the B0 approximation.
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Optimized Eigenvalue Solvers for the Neutron Transport Equation

2018
A discrete ordinates method has been developed to approximate the neutron transport equation for the computation of the lambda modes of a given configuration of a nuclear reactor core. This method is based on discrete ordinates method for the angular discretization, resulting in a very large and sparse algebraic generalized eigenvalue problem.
Antoni Vidal-Ferràndiz, Sebastián González-Pintor, Damián Ginestar, Amanda Carreño, Gumersindo Verdú   +4 more
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Numerical solution of the neutron transport equation

Journal of Nuclear Energy, 1969
Abstract An outline of a procedure for directly solving the singular integral form of the one-speed neutron transport equation is given. The procedure is illustrated by considering the Milne problem and a one-region critical problem. Examples of numerical results obtained for these two problems are presented.
R.L. Bowden, A.G. Bullard
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A family of transport equations in neutron transport theory

Annals of Nuclear Energy, 1991
Abstract The backward formulation of problems in neutron transport is considered. Boundary conditions are developed from the adjoint system which in turn is rigorously obtained from a variational principle. The variational principle is derived by constraining the flux with the forward transport equation and affiliated boundary/initial conditions ...
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