You are here

Home » Content

Birinci Tip Chebyshev Polinomları ile Nötron Transport Denklemine Difüzyon Yaklaşımı

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

Journal Name:

  • Süleyman Demirel Üniversitesi Fen Dergisi

Publication Year:

  • 2015

Key Words:

Keywords (Original Language):

Author NameUniversity of AuthorFaculty of Author
Abstract (2. Language): 
The first kind of Chebyshev polynomials are used for the series expansion of the neutron angular flux in neutron transport theory. The first order approximation known as the diffusion approximation is applied to one-dimensional neutron transport equation to determine the diffusion coefficients of one-speed neutrons for selected values of the scattering parameters.
Bookmark/Search this post with
Abstract (Original Language): 
Nötron transport teorisinde açısal akının seri açılımı için I. Tip Chebyshev polinomları kullanıldı. Tek hızlı nötronların difüzyon katsayılarını belirlemek için difüzyon yaklaşımı olarak bilinen ilk mertebe yaklaşımı saçılma parametrelerinin seçilen değerleri için tek boyutlu nötron transport denklemine uygulanmıştır.
FULL TEXT (PDF): 
PDF icon arastirmax-birinci-tip-chebyshev-polinomlari-ile-notron-transport-denklemine-difuzyon-yaklasimi.pdf
  • 2
92
96
  • Turkish

REFERENCES

References: 

[I] Lamarsh J.R., Baratta A.J., 2001. Introduction to nuclear engineering. Prentice Hall, Inc. [2] Davison B., 1958. Neutron transport theory. London, Oxford University Press.
[3] Case K.M, Zweifel P.F., 1967. Linear transport theory. Addison-Wesley Publishing Company.
[4] Aspelund O., 1958. On a new method for solving the (Boltzmann) equation in neutron transport theory,
PICG, 16: 530.
[5] Conkie W.R., 1959. Polynomial approximations in neutron transport theory, Nuclear Science and Engineering. 6: 260-266.
[6] Yabushita S., 1961. Tschebyscheff polynomials approximation method of the neutron transport equation,
Journal of Mathematical Physics, 2: 543-549. [7] Anlı F., Yaşa F., Güngör S., Öztürk H., 2006. TN approximation to neutron transport equation and application
to critical slab problem, Journal of Quantitative Spectroscopy and Radiative Transfer, 101: 129-134. [8] Öztürk H., Anlı F., Güngör S., 2007. TN method for the critical thickness of one-speed neutrons in a slab with
forward and backward scattering, Journal of Quantitative Spectroscopy and Radiative Transfer, 105:
211-216.
[9] Öztürk H., Bülbül A., Kara A., 2010. U1 approximation to the neutron transport equation and calculation of the asymptotic relaxation length, Kerntechnik, 75: 375-376.
[10]
Tıra
ş M., Öztürk H., Bülbül A., 2014. T1 and U1 approximations to neutron transport equation in one-dimensional spherical geometry, Kerntechnik, 79: 163-166.
[II] Yıldırım S., Öztürk H., 2014. Diffusion length calculations for one-speed neutrons in a slab with backward,
forward and linear anisotropic scattering, Kerntechnik, 79: 243-246. [12] Bell G.I., Glasstone, S., 1970. Nuclear reactor theory. New York, VNR Company, 619 p.

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