TN approximation for the critical size of one-speed neutrons in a slab with anisotropic scattering
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H. Öztürk
Abstract
The critical thickness for one-speed neutrons in a uniform finite slab with anisotropic scattering is investigated using Marshak boundary condition. The angular part of the neutron angular flux is expanded in terms of the Chebyshev polynomials of first kind. Numerical results for the critical thickness of the slab are calculated for various values of the collision and the anisotropy parameters and they are given in the tables together with the ones obtained by Legendre polynomials approximation and the ones available in literature for comparison. The results obtained by the present method are in good accordance with the literature values.
Kurzfassung
Die Berechnung der kritischen Dicke der Neutronen einer Geschwindigkeit innerhalb einer gleichmäßigen endlichen Platte unter Berücksichtigung der anisotropen Streuung wird in diesem Beitrag vorgestellt. Dazu wird der winkelabhängige Teil des Neutronenstromes durch Chebyshev Polynome erster Ordner angenähert. Die Lösung erfolgt unter Berücksichtigung der Marshak Randbedingung. Die Ergebnisse werden für verschiedene Kollisions- und Richtungsabhängigkeitsparameter berechnet und tabellarisch angegeben. Als Vergleichswerte werden Ergebnisse gegenübergestellt, die durch Anwendung der Näherungsmethode mit Legendre Polynomen erzielt wurden und weiteren in der Literatur verfügbaren Daten. Der Vergleich zeigt eine gute Übereinstimmung zwischen den verschiedenen Methoden.
References
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© 2013, Carl Hanser Verlag, München
Artikel in diesem Heft
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- Computational modeling of monoenergetic neutral particle inverse transport problems in slab geometry
- Effects on criticality of selected scattering phase functions in neutron transport equation using the Chebyshev approximation
- U1 and P1 approximations to neutron transport equation for diffusion length calculation
- Technical Notes/Technische Mitteilungen
- TN approximation for the critical size of one-speed neutrons in a slab with anisotropic scattering
- Albedo and constant source problems for extremely anisotropic scattering
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Chemistry aspects of the source term formation for a severe accident in a CANDU type reactor
- Analytical study on degraded core quenching
- Experimental investigations on control of flow instability in single-phase natural circulation loop
- Burnup calculations using serpent code in accelerator driven thorium reactors
- Investigation of neutronic effects in structural material of a hybrid reactor by using the MCNPX Monte Carlo transport code
- Nuclear aspects and cyclotron production of the positron emitter 55Co
- Calculation of age-dependent effective doses for external exposure using the MCNP code
- Effect of Cu2+/Al3+ mole ratio on structure of Cu – Al bimetallic nanoparticles prepared by radiation induced method
- A numerical method for resonance integral calculations
- Computational modeling of monoenergetic neutral particle inverse transport problems in slab geometry
- Effects on criticality of selected scattering phase functions in neutron transport equation using the Chebyshev approximation
- U1 and P1 approximations to neutron transport equation for diffusion length calculation
- Technical Notes/Technische Mitteilungen
- TN approximation for the critical size of one-speed neutrons in a slab with anisotropic scattering
- Albedo and constant source problems for extremely anisotropic scattering
