Chebyshev spectral-SN method for the neutron transport equation (original) (raw)

Iterative Schemes for the Neutron Di usion Equation

Damian Ginestar

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Evaluation of higher K-rmeigenvalues of the neutron transport equation by Sn-method

Dinesh Sahni

Annals of Nuclear Energy, 1995

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The spectral element method for static neutron transport in AN approximation. Part I

Ernest Mund

Annals of Nuclear Energy, 2013

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A three-dimensional nodal solution for the frequency dependent neutron diffusion equation

Abdulghani Melaibari

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The Spectral Element Approach for the Solution of Neutron

Ernest Mund

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A simple scheme for the direct evaluation of time-eigenvalues of neutron transport equation

anurag gupta

Annals of Nuclear Energy, 2003

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ÅËÅÊÒÐÎÎÑÀÄAEÅÍÍß ÅËÅÊÒÐÎÊÀÒÀ˲ÒÈ×ÍÈÕ ÏÎÊÐÈÒÒ²Â Ó ÑÈÑÒÅÌÀÕ ÍÀ ÎÑÍβ ÍÈÇÜÊÎÒÅÌÏÅÐÀÒÓÐÍÈÕ ÅÂÒÅÊÒÈ×ÍÈÕ ÐÎÇ×ÈÍÍÈʲÂ: ÎÃËßÄ Ë²ÒÅÐÀÒÓÐÈ

Vyacheslav Protsenko

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Total reaction cross sections for neutron-nucleus scattering

K. Amos

Physical Review C, 2002

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Accurate nuclear masses from a three parameter Kohn-Sham DFT approach (BCPM)

X. Viñas, L. Robledo

AIP Conference Proceedings, 2012

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Implicit and iterative methods for the Boltzmann equation

J. Struckmeier

Transport Theory and Statistical Physics, 1996

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Diffusion Approximation to Neutron Transport Equation with First Kind of Chebyshev Polynomials

Ahmet Bülbül

2015

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A new perspective on some approximations used in neutron transport modeling

Milan Hanuš

2013

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Nuclear modeling of (n, x,[gamma]) reactions and determination of partial cross sections

Paul Garrett

2002

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Simplified transport models for neutron energy spectra evaluations

Simone Di Pasquale

2019

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Assessment of the performance of the spectral element method applied to neutron transport problems

Ernest Mund

Annals of Nuclear Energy, 2014

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On the spectrum of discrete-ordinates neutron transport problems

Jesús Pérez Curbelo

2021

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Study of the Eigenvalue Spectra of the Neutron Transport Problem in PN Approximation

Paolo Saracco

EPJ Web of Conferences, 2021

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Arbitrarily high order characteristic methods for solving the neutron transport equation

Yousry Azmy

Annals of Nuclear Energy, 1992

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On eigensolutions of the one-speed neutron transport equation in plane geometry

Nassar Haidar

The Journal of the Australian Mathematical Society. Series B. Applied Mathematics, 1990

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The spectral nodal method applied to multigroup SN neutron transport problems in One-Dimensional geometry with Fixed–Source

Carlos Rafael García Hernández

Progress in Nuclear Energy

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Multi-species Neutron Transport Equation

Simon Harris

Journal of Statistical Physics, 2019

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Improved di-neutron cluster model for He6 scattering

Joaquin Gomez Camacho

Physical Review C, 2007

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Progress in Multidimensional Neutron Transport Computation

Elmer Lewis

Nuclear Science and Engineering, 1977

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ÐÎÑÑÈÉÑÊÀß ÀÊÀÄÅÌÈß ÍÀÓÊ

Egor Loktionov

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A family of transport equations in neutron transport theory

Anil Prinja

Annals of Nuclear Energy, 1991

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Monte Carlo Methods for the Neutron Transport Equation

Simon Harris

SIAM/ASA Journal on Uncertainty Quantification

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The adjoint neutron transport equation and the statistical approach for its solution

Paolo Saracco

The European Physical Journal Plus, 2016

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äàíèëîâ-1 äàíèëîâ-2 è÷êèòèäçå.p65

Sergey Selishchev

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Calculating near-singular eigenvalues of the neutron transport operator with arbitrary order anisotropic scattering

Ernest Mund

Mathematics and Computers in Simulation, 2010

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X-12 Ins. Page (For paper-II).p65

shahzada babar

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