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Anli-Güngör Saçılma Fonksiyonu ile Modifiye UN Metodu Kullanılarak Difüzyon Katsayılarının Hesaplanması

Year 2022, Volume: 4 Issue: 1, 60 - 65, 30.06.2022
https://doi.org/10.54990/okufed.1052708

Abstract

Modifiye U1 yaklaşımı nötron transport denklemine uygulandı ve Anli- Güngör saçılması kullanılarak saçılma parametresinin bazı değerleri için difüzyon katsayıları hesaplandı. Analitik difüzyon katsayısı terimi verildi ve Modifiye U1 ve P1 yaklaşımından elde edilen sayısal sonuçlar farklı çarpışma ve t parametreleri için birbiri ile kıyaslandı.

References

  • 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.
  • Bülbül, A. & Anlı, F. (2009). Modified Chebyshev polynomial (UN) approximation in the neutron transport theory and computation of critical half thicknesses. Kerntechnik, 74(1-2), 65-69.
  • Bülbül, A., Ulutas, M. & Anli, F. (2008). Application of the UN approximation to the neutron transport equation in slab geometry. Kerntechnik, 73(1-2), 61-65.
  • Case, K.M. & Zweifel, P. F. (1967). Linear Transport Theory. Addison-Wesley Company.
  • Gulecyuz, M. C., Senyigit M. & Ersoy, A. (2018). Milne problem for non-absorbing medium with extremely anisotropic scattering kernel in the case of specular and diffuse reflecting boundaries, Indian Journal of Physics, 92(1), 81-90.
  • Lamarsh, J. R. & Baratta, A. J. (2001). Introduction to nuclear engineering . Upper Saddle River, NJ: Prentice hall.
  • Öztürk, H., Anlı, F. & Güngör, S. (2007). Application of the UN method to the reflected critical slab problem for one-speed neutrons with forward and backward scattering. Kerntechnik, 72(1-2), 74-76.
  • Öztürk, H., Bülbül, A. & Kara, A. (2010). U1 approximation to the neutron transport equation and calculation of the asymptotic relaxation length. Kerntechnik, 75(6), 375-376. https://doi.org/10.3139/124.110107
  • Stacey, W. M., (2007). Nuclear reactor physics. Wiley-Vch Verlag GmbH &Co.KGaA, Weinheim.
  • Yildiz, C. (1998). Variation of the critical slab thickness with the degree of strongly anisotropic scattering in one-speed neutron transport theory. Annals of Nuclear Energy, 25(8), 529-540.
Year 2022, Volume: 4 Issue: 1, 60 - 65, 30.06.2022
https://doi.org/10.54990/okufed.1052708

Abstract

References

  • 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.
  • Bülbül, A. & Anlı, F. (2009). Modified Chebyshev polynomial (UN) approximation in the neutron transport theory and computation of critical half thicknesses. Kerntechnik, 74(1-2), 65-69.
  • Bülbül, A., Ulutas, M. & Anli, F. (2008). Application of the UN approximation to the neutron transport equation in slab geometry. Kerntechnik, 73(1-2), 61-65.
  • Case, K.M. & Zweifel, P. F. (1967). Linear Transport Theory. Addison-Wesley Company.
  • Gulecyuz, M. C., Senyigit M. & Ersoy, A. (2018). Milne problem for non-absorbing medium with extremely anisotropic scattering kernel in the case of specular and diffuse reflecting boundaries, Indian Journal of Physics, 92(1), 81-90.
  • Lamarsh, J. R. & Baratta, A. J. (2001). Introduction to nuclear engineering . Upper Saddle River, NJ: Prentice hall.
  • Öztürk, H., Anlı, F. & Güngör, S. (2007). Application of the UN method to the reflected critical slab problem for one-speed neutrons with forward and backward scattering. Kerntechnik, 72(1-2), 74-76.
  • Öztürk, H., Bülbül, A. & Kara, A. (2010). U1 approximation to the neutron transport equation and calculation of the asymptotic relaxation length. Kerntechnik, 75(6), 375-376. https://doi.org/10.3139/124.110107
  • Stacey, W. M., (2007). Nuclear reactor physics. Wiley-Vch Verlag GmbH &Co.KGaA, Weinheim.
  • Yildiz, C. (1998). Variation of the critical slab thickness with the degree of strongly anisotropic scattering in one-speed neutron transport theory. Annals of Nuclear Energy, 25(8), 529-540.
There are 10 citations in total.

Details

Primary Language Turkish
Journal Section Research Articles
Authors

Ahmet Bülbül

Publication Date June 30, 2022
Acceptance Date June 27, 2022
Published in Issue Year 2022 Volume: 4 Issue: 1

Cite

APA Bülbül, A. (2022). Anli-Güngör Saçılma Fonksiyonu ile Modifiye UN Metodu Kullanılarak Difüzyon Katsayılarının Hesaplanması. Osmaniye Korkut Ata Üniversitesi Fen Edebiyat Fakültesi Dergisi, 4(1), 60-65. https://doi.org/10.54990/okufed.1052708