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Year 2018, Volume: 2 Issue: 3, 287 - 291, 15.12.2018

Abstract

References

  • 1. Lamarsh, J.R., Baratta, A.J., Introduction to nuclear engineering. 2001, USA: Prentice Hall, Inc.
  • 2. Davison, B., Neutron transport theory. 1958, London: Oxford University Press.
  • 3. Case, K.M, Zweifel, P.F., Linear transport theory. 1967, USA: Addison-Wesley Publishing Company.
  • 4. Aspelund, O., On a new method for solving the (Boltzmann) equation in neutron transport theory. PICG, 1958. 16: p.530-534.
  • 5. Conkie, W.R., Polynomial approximations in neutron transport theory. Nucl. Sci. Eng., 1959. 6: p.260-266.
  • 6. Yabushita, S., Tschebyscheff polynomials approximation method of the neutron transport equation. J. Math. Phys., 1961. 2: p.543-549.
  • 7. Anlı, F., Yaşa, F., Güngör, S., Öztürk, H., TN approximation to neutron transport equation and application to critical slab problem. J. of Quant. Spectros. Radiat. Trans., 2006. 101: p.129-134.
  • 8. Öztürk, H., Anlı, F., Güngör, S., TN method for the critical thickness of one-speed neutrons in a slab with forward and backward scattering. J. of Quant. Spectros. Radiat. Trans., 2007. 105: p.211-216.
  • 9. Tıraş, M., Öztürk, H., Bülbül, A., T1 and U1 approximations to neutron transport equation in one-dimensional spherical geometry. Kerntechnik, 2014. 79: p.163-166.
  • 10. Yıldırım, S., Öztürk, H., Diffusion length calculations for one-speed neutrons in a slab with backward, forward and linear anisotropic scattering. Kerntechnik, 2014. 79: p.243-246.
  • 11. Arfken, G., Mathematical methods for physicists. 1985, London: Academic Press, Inc.
  • 12. Bell, G.I., Glasstone, S., Nuclear reactor theory. 1972, New York: VNR Company.

Calculation of the diffusion lengths for one-speed neutrons in a slab with forward and backward scattering

Year 2018, Volume: 2 Issue: 3, 287 - 291, 15.12.2018

Abstract

The diffusion lengths for
one-speed neutrons in a slab are calculated using the first kind of Chebyshev
polynomials approximation (TN)
method. The scattering models are constituted in place of the scattering
function with an argument of the cosine of the neutron scattering angle.
Therefore, the forward-backward-isotropic (FBI) scattering model is used as the
scattering function in transport equation which describes the interaction and
the conservation of the neutrons throughout a system. In the solution
algorithm, first the neutron angular flux is expanded in terms of the Chebyshev
polynomials of first kind. After inserting this expansion in the transport
equation, the coupled differential equations are derived using the properties
of the Chebyshev polynomials of first kind. These equations are solved together
and then the diffusion equation is obtained by applying the first order
approximation (N = 1) which is known
as the diffusion approximation. Finally, the diffusion lengths for one-speed
neutrons are calculated for selected values of the collision, backward and
forward scattering parameters. The calculated diffusion lengths are given in
the tables together with the ones already obtained in literature in order to
indicate the applicability of the present method. The convenience and rapid
convergence of the present method with its easily executable equations can be
observed from the derived equations and the results in tables.

References

  • 1. Lamarsh, J.R., Baratta, A.J., Introduction to nuclear engineering. 2001, USA: Prentice Hall, Inc.
  • 2. Davison, B., Neutron transport theory. 1958, London: Oxford University Press.
  • 3. Case, K.M, Zweifel, P.F., Linear transport theory. 1967, USA: Addison-Wesley Publishing Company.
  • 4. Aspelund, O., On a new method for solving the (Boltzmann) equation in neutron transport theory. PICG, 1958. 16: p.530-534.
  • 5. Conkie, W.R., Polynomial approximations in neutron transport theory. Nucl. Sci. Eng., 1959. 6: p.260-266.
  • 6. Yabushita, S., Tschebyscheff polynomials approximation method of the neutron transport equation. J. Math. Phys., 1961. 2: p.543-549.
  • 7. Anlı, F., Yaşa, F., Güngör, S., Öztürk, H., TN approximation to neutron transport equation and application to critical slab problem. J. of Quant. Spectros. Radiat. Trans., 2006. 101: p.129-134.
  • 8. Öztürk, H., Anlı, F., Güngör, S., TN method for the critical thickness of one-speed neutrons in a slab with forward and backward scattering. J. of Quant. Spectros. Radiat. Trans., 2007. 105: p.211-216.
  • 9. Tıraş, M., Öztürk, H., Bülbül, A., T1 and U1 approximations to neutron transport equation in one-dimensional spherical geometry. Kerntechnik, 2014. 79: p.163-166.
  • 10. Yıldırım, S., Öztürk, H., Diffusion length calculations for one-speed neutrons in a slab with backward, forward and linear anisotropic scattering. Kerntechnik, 2014. 79: p.243-246.
  • 11. Arfken, G., Mathematical methods for physicists. 1985, London: Academic Press, Inc.
  • 12. Bell, G.I., Glasstone, S., Nuclear reactor theory. 1972, New York: VNR Company.
There are 12 citations in total.

Details

Primary Language English
Journal Section Research Articles
Authors

Hakan Öztürk

Ökkeş Ege This is me

Publication Date December 15, 2018
Submission Date March 2, 2018
Acceptance Date August 28, 2018
Published in Issue Year 2018 Volume: 2 Issue: 3

Cite

APA Öztürk, H., & Ege, Ö. (2018). Calculation of the diffusion lengths for one-speed neutrons in a slab with forward and backward scattering. International Advanced Researches and Engineering Journal, 2(3), 287-291.
AMA Öztürk H, Ege Ö. Calculation of the diffusion lengths for one-speed neutrons in a slab with forward and backward scattering. Int. Adv. Res. Eng. J. December 2018;2(3):287-291.
Chicago Öztürk, Hakan, and Ökkeş Ege. “Calculation of the Diffusion Lengths for One-Speed Neutrons in a Slab With Forward and Backward Scattering”. International Advanced Researches and Engineering Journal 2, no. 3 (December 2018): 287-91.
EndNote Öztürk H, Ege Ö (December 1, 2018) Calculation of the diffusion lengths for one-speed neutrons in a slab with forward and backward scattering. International Advanced Researches and Engineering Journal 2 3 287–291.
IEEE H. Öztürk and Ö. Ege, “Calculation of the diffusion lengths for one-speed neutrons in a slab with forward and backward scattering”, Int. Adv. Res. Eng. J., vol. 2, no. 3, pp. 287–291, 2018.
ISNAD Öztürk, Hakan - Ege, Ökkeş. “Calculation of the Diffusion Lengths for One-Speed Neutrons in a Slab With Forward and Backward Scattering”. International Advanced Researches and Engineering Journal 2/3 (December 2018), 287-291.
JAMA Öztürk H, Ege Ö. Calculation of the diffusion lengths for one-speed neutrons in a slab with forward and backward scattering. Int. Adv. Res. Eng. J. 2018;2:287–291.
MLA Öztürk, Hakan and Ökkeş Ege. “Calculation of the Diffusion Lengths for One-Speed Neutrons in a Slab With Forward and Backward Scattering”. International Advanced Researches and Engineering Journal, vol. 2, no. 3, 2018, pp. 287-91.
Vancouver Öztürk H, Ege Ö. Calculation of the diffusion lengths for one-speed neutrons in a slab with forward and backward scattering. Int. Adv. Res. Eng. J. 2018;2(3):287-91.



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