S4 solution of the transport equation for eigenvalues using Legendre polynomials

Numerical solution of the transport equation for monoenergetic neutrons scattered isotropically through the medium of a finite homogeneous slab is studied for the determination of the eigenvalues. After obtaining the discrete ordinates form of the transport equation, separated homogeneous and partic...
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Autor*in:	Öztürk Hakan [verfasserIn] Bülbül Ahmet [verfasserIn]

Format:	E-Artikel
Sprache:	Englisch

Erschienen:	2017

Übergeordnetes Werk:	In: EPJ Web of Conferences - EDP Sciences, 2010, 154, p 01014(2017)
Übergeordnetes Werk:	volume:154, p 01014 ; year:2017

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DOI / URN:	10.1051/epjconf/201715401014

Katalog-ID:	DOAJ015108724

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author	Öztürk Hakan
spellingShingle	Öztürk Hakan misc QC1-999 misc Physics S4 solution of the transport equation for eigenvalues using Legendre polynomials
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title	S4 solution of the transport equation for eigenvalues using Legendre polynomials
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title_auth	S4 solution of the transport equation for eigenvalues using Legendre polynomials
abstract	Numerical solution of the transport equation for monoenergetic neutrons scattered isotropically through the medium of a finite homogeneous slab is studied for the determination of the eigenvalues. After obtaining the discrete ordinates form of the transport equation, separated homogeneous and particular solutions are formed and then the eigenvalues are calculated using the Gauss-Legendre quadrature set. Then, the calculated eigenvalues for various values of the c0, the mean number of secondary neutrons per collision, are given in the tables.
abstractGer	Numerical solution of the transport equation for monoenergetic neutrons scattered isotropically through the medium of a finite homogeneous slab is studied for the determination of the eigenvalues. After obtaining the discrete ordinates form of the transport equation, separated homogeneous and particular solutions are formed and then the eigenvalues are calculated using the Gauss-Legendre quadrature set. Then, the calculated eigenvalues for various values of the c0, the mean number of secondary neutrons per collision, are given in the tables.
abstract_unstemmed	Numerical solution of the transport equation for monoenergetic neutrons scattered isotropically through the medium of a finite homogeneous slab is studied for the determination of the eigenvalues. After obtaining the discrete ordinates form of the transport equation, separated homogeneous and particular solutions are formed and then the eigenvalues are calculated using the Gauss-Legendre quadrature set. Then, the calculated eigenvalues for various values of the c0, the mean number of secondary neutrons per collision, are given in the tables.
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title_short	S4 solution of the transport equation for eigenvalues using Legendre polynomials
url	https://doi.org/10.1051/epjconf/201715401014 https://doaj.org/article/10cfc39d254a45a898d7c12f80d73e60 https://doaj.org/toc/2100-014X
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