You are here

Home » Content

Nötron Transportu için Küresel Geometride Özdeğer Hesaplaması

Eigenvalue Calculation for Transport Theory in Spherical Geometry

Journal Name:

  • Kahramanmaraş Sütçü İmam Üniversitesi Doğa Bilimleri Dergisi

Publication Year:

  • 2003

Key Words:

Keywords (Original Language):

Author NameUniversity of AuthorFaculty of Author
Abstract (2. Language): 
In this study, eigenvalue and eigenvector of transport equation which are current topics of nuclear physics are investigated. Spherical geometry problem of neutron was reduced the slab geometry problem with our approach. This equation is then solved in this slab geometry with producing eigenvalue
Bookmark/Search this post with
Abstract (Original Language): 
Bu çalışmada nükleer fiziğin güncel konularından biri olan transport eşitliğinin özdeğeri incelendi. Analizi zor olan nötronların küresel geometri problemi bizim yaklaşımımızla düzlem geometri problemine indirgenmiştir. Sonrada bu geometride özdeğerler üretilerek çözüme ulaşılmıştır.
FULL TEXT (PDF): 
PDF icon arastirmax-notron-transportu-icin-kuresel-geometride-ozdeger-hesaplamasi.pdf
  • 2
28
33
  • Turkish

REFERENCES

References: 

Anlı, F., S. Güngör, 1996. Annals of Nuclear Energy, 23, 669.
Anlı, F., 2001. Spectral Green’s Function method for neutron transport. Ann. Nucl.
Energy, vol.28, 1033-1042.
Anlı, F., 1994. Üç boyutlu kartezyen geometride diskret ordinat problemlerinin
Spectral Green fonksiyonları ile çözümü. Ç. Ü. Fen Bilimleri Enstitüsü, Adana.
Aronson, R., 1984 a. Critical problems in spherical geometry. Nuclear Science and
Engineering, 86, 136-149.
Case, K.M., P.F. Zweifel, 1967. Linear Transport Theory. Wesley company.
London.
Duderstadt, J.J., W.R. Martin, 1978. Transport Theory. The unv. of Michigan, Ann
Arbor.
Garis, N.S., 1991. One speed neutron transport eigenvalues for reflected slabs and
spheres. Nucl. Sci. and Engng., 107, 343-358.
Kaşkaş, A., C. Tezcan, M.Ç. Güleçyüz, 2000. The solution of the third form
transport equation using singular eigen functions. JQSRT., 66(2000), 519-528.
Mitsis, G. J., 1963. Transport solutions to the mono energetic critical problems.
(Thesis), ANL-6787.
Sahni, D.C., A. Sharma, 2000. Computation of higher spherical harmonics moment
of the angular flux for neutron transport problems in spherical geometry. Ann,
Nucl. Energy, 27, 411-433.
Sharma, A., 2000. Spherical harmonics moments of neutron angular flux for
spherically symmetric systems. Am. Nucl. Energy, 715-721.
Seiwert, C.E., P. Grandjean, 1979. Three basic neutron transport problems in
spherical geometry. Nucl. Sci. and Engng., 70, 96-110.
Seiwert, C.E., S. J. Wright, 1999. Efficient eigenvalue calculations in radiative
transfer. JQSRT, 62, 685-688.
Yavuz, M., 1997. Methods for computing SN eigenvalue and eigenvectors of slab
geometry transport problems. Ann. of Nucl. Energy, Vol. 25, 149-160.
Woznicki, Z. I., 1998. The nümerical anaalysis of eigenvalue problem solutions in
the multigroup neutron diffusion theory. Prog. Nucl. Energy, Vol. 33, 302-391.

Thank you for copying data from http://www.arastirmax.com