Calculation of Diffusion Lengths using PN and Modified UN Method for Forward and Backward Scattering
Öz
Anahtar Kelimeler
Kaynakça
- Anli, F.; Yasa, F.; Güngör, S.; Öztürk, H.: TN approximation to neutron transport equation and application to critical slab problem. J.Quant. Spectrosc. Radiat. Transfer 101 (2006) 129
- Bell, G.I.; Glasstone, S.: Nuclear reactor theory. New York, VNR Company, 1972
- Bülbül, A; Ulutas, M.; Anli, F.: Application of the UN approximation to the neutron transport equation in slab geometry. Kerntechnik 73/1-2 (2008) 61
- Bülbül, A; Anli, F.: Modified Chebyshev polynomial (UN) approximation in the neutron transport theory and computation of critical half thicknessesKerntechnik 74/1-2 (2009)
- Case, K.M.; Zweifel, P. F.: Linear Transport Theory. Addison-Wesley Company, 1967
- Davison, B.: Neutron transport theory. London, Oxford University Press, 1958
- Gulecyuz, M. C., Senyigit ., Ersoy, A., 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, (2018) 1, 81-90.
- Lamarsh, J. R.; Baratta, A. J.: Introduction to nuclear engineering. Prentice Hall, Inc., 2001
Ayrıntılar
Birincil Dil
İngilizce
Konular
-
Bölüm
Araştırma Makalesi
Yazarlar
Ahmet Bülbül
*
Türkiye
Yayımlanma Tarihi
30 Haziran 2021
Gönderilme Tarihi
9 Haziran 2021
Kabul Tarihi
15 Haziran 2021
Yayımlandığı Sayı
Yıl 2021 Cilt: 3 Sayı: 1