Results 251 to 260 of about 5,356 (294)

Development of a nodal method for the solution of the neutron diffusion equation in cylindrical geometry

, 2008
Mehmet Mercimek
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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
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Analytical solution of the monoenergetic neutron transport equation in one dimension with linearly anisotropic scatering using diffusion sinthetic approximation

, 2011
Ralph dos Santos Mansur
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Helium spin-echo as a surface-sensitive probe of vibrational energy dissipation.

Faraday Discuss
Tamtögl A, Ellis J, Allison W, Sabik A, Antczak G, Jardine AP.   +5 more
europepmc   +1 more source

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A Lie symmetries interpretation of the neutron diffusion equation

Annals of Nuclear Energy, 2021
Abstract The neutron diffusion equation has, in the time since its initial development during the 1940s, become firmly established as the mathematical centerpiece through which thousands of nuclear engineers have been introduced to and trained in the physics and phenomenology of neutron transport.
Scott D. Ramsey, Tyler J. Remedes
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Time-dependent neutron diffusion coefficient for the effective diffusion equation

Progress in Nuclear Energy, 2019
Abstract The time-dependency of neutron diffusion coefficient as well as neutronic interfacial coefficients in nuclear reactors at short time-scale is investigated via the volume averaging method. The boundary-value problems of governing differential equation for spatial deviations around averages of local variables are developed in this work.
Gilberto Espinosa-Paredes, CARLOS G Aguilar-Madera   +1 more
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On the numerical solution of the neutron fractional diffusion equation

Annals of Nuclear Energy, 2014
Abstract In order to core calculation in the nuclear reactors there is a new version of neutron diffusion equation which is established on the fractional partial derivatives, named Neutron Fractional Diffusion Equation (NFDE). In the NFDE model, neutron flux in each zone depends directly on the all previous zones (not only on the nearest neighbors ...
Gilberto Espinosa-Paredes, Hossein Afarideh   +1 more
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Multiscale model reduction for neutron diffusion equation

Журнал «Математические заметки СВФУ», 2021
Modelling of dynamic processes in nuclear reactors is carried out, mainly, on the basis of the multigroup diffusion approximation for the neutron flux. The neutron diffusion approximation is widely used for reactor analysis and applied in most engineering calculation codes.
Vasilev, Aleksandr O., Spiridonov, Denis A., Avvakumov, Alexander V.   +2 more
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Averaging the neutron diffusion equation

Progress in Nuclear Energy, 2009
This paper presents a general theoretical analysis of the neutron motion problem in a nuclear reactor, where large variations on neutron cross-sections normally preclude the use of the classical neutron diffusion equation. A volume-averaged neutron diffusion equation (VANDE) is derived which includes correction terms to diffusion and nuclear reaction ...
R. Vázquez-Rodríguez, G. Espinosa-Paredes, J.B. Morales-Sandoval, A. Vázquez-Rodríguez, E.-G. Espinosa-Martinez   +4 more
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