Öz
Tek boyutlu nötron transport denkleminde difüzyon uzunluğu hesaplamaları için Modifiye U1 ve P1 yaklaşımları kullanıldı. Yaklaşımlar ileri-geri saçılmalı tek hızlı nötron transport denklemine uygulandı. Analitik difüzyon uzunluğu denklemleri elde edildi ve farklı çarpışma parametreleri (c) için U1 ve P1 yaklaşımından elde edilen sayısal sonuçlar birbiri arasında kıyaslandı.
Anahtar Kelimeler
U1 yaklaşımı Transport Denklemi Difüzyon Uzunluğu İleri- Geri Saçılma.
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
- Öztürk, H.; Anli, F.; Güngör, S.: Application of the UN method to the reflected critical slab problem for one-speed neutrons with forward and backward scattering. Kerntechnik 72/1-2 (2007) 74
- Öztürk, H., Bülbül, A. and Kara, : U1 approximation to neutron transport equation and calculation of the asymptotic relaxation length, Kerntechnik ,75/6 (2010) 375
- Stacey, W. M.: Nuclear reactor physics. Wiley-Vch Verlag GmbH &Co.KGaA, Weinheim, 2007
- Yildiz, C.: Variation of the critical slab thickness with the degree of strongly anisotropic scattering in one-speed neutron transport theory. Ann. Nucl. Energy 25 (1998) 529
Calculation of Diffusion Lengths using PN and Modified UN Method for Forward and Backward Scattering
Öz
Modified U1 and P1 approximations are used for the calculation of diffusion lengths in one- dimensional neutron transport equation. The approximations are applied to one-speed neutron transport equation with forward and backward scattering. Analytical diffusion length equations are obtained and the numerical results obtained from modified U1 and P1 approximations for different collision parameters (c) are compared with each other.
Anahtar Kelimeler
: U1 Approximation Transport Equation Diffusion length Forward-backward scattering
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
- Öztürk, H.; Anli, F.; Güngör, S.: Application of the UN method to the reflected critical slab problem for one-speed neutrons with forward and backward scattering. Kerntechnik 72/1-2 (2007) 74
- Öztürk, H., Bülbül, A. and Kara, : U1 approximation to neutron transport equation and calculation of the asymptotic relaxation length, Kerntechnik ,75/6 (2010) 375
- Stacey, W. M.: Nuclear reactor physics. Wiley-Vch Verlag GmbH &Co.KGaA, Weinheim, 2007
- Yildiz, C.: Variation of the critical slab thickness with the degree of strongly anisotropic scattering in one-speed neutron transport theory. Ann. Nucl. Energy 25 (1998) 529
Ayrıntılar
| Birincil Dil | İngilizce |
|---|---|
| Bölüm | Araştırma Makaleleri |
| Yazarlar | |
| Yayımlanma Tarihi | 30 Haziran 2021 |
| Kabul Tarihi | 15 Haziran 2021 |
| Yayımlandığı Sayı | Yıl 2021 Cilt: 3 Sayı: 1 |
