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Constraining the magnetohydrodynamic turbulence around Geminga by observing the γ-ray halo beyond 100 TeV. [PDF]

Sci Adv
Tibet ASγ Collaboration.
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
exaly   +2 more sources

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.
CARLOS G Aguilar-Madera, Gilberto Espinosa-Paredes   +1 more
exaly   +2 more sources

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 ...
H Afarideh, Gilberto Espinosa-Paredes
exaly   +2 more sources

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
openaire   +1 more source

The solution of coupled fractional neutron diffusion equations with delayed neutrons

International Journal of Nuclear Energy Science and Technology, 2010
The distribution of the neutron population in a nuclear reactor is described by using transport equations. One possible solution of the fractional neutron transport equation is given by the fractional neutron diffusion equation. This paper presents the application of an analytical approximation method for the solution of one group of fractional neutron
T. Sardar, S. Saha Ray, R.K. Bera, B.B. Biswas, S. Das   +4 more
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Discontinuous variational solutions for the neutron diffusion equation

Annals of Nuclear Energy, 1996
Abstract A maximum variational principle derived by a least squares method is used to obtain discontinuous finite element solution to the neutron diffusion equation. Here the principle is applied with locally constant and locally linear trial functions to determine a discontinuous finite element solution for a number of one group diffusion problems ...
R.T. Ackroyd, A.M. Gashut, O.A. Abuzid
openaire   +1 more source