Diffusion length calculations for one-speed neutrons in a slab with backward, forward and linear anisotropic scattering
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S. Yıldırım
Abstract
The diffusion lengths for one-speed neutrons spreading in a uniform homogeneous slab with backward, forward and linear anisotropic scattering are calculated by using first order approximation of the Chebyshev polynomials of first kind, i. e. T1 method. The method is applied to neutron transport equation by expanding first the neutron angular flux in terms of the Chebyshev polynomials of first kind, and then diffusion lengths for one-speed neutrons are determined for various values of the collision and anisotropy parameters. Numerical results obtained from the present method are tabulated in tables together with the ones already presented in literature.
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© 2014, Carl Hanser Verlag, München
Artikel in diesem Heft
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- Improvement of passive shielding to reduce background components to determinate radioactivity at low energy gamma rays
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Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Simulation of thermal fluid dynamics in parabolic trough receiver tubes with direct steam generation using the computer code ATHLET
- Measurement of velocity profiles of nanofluids in laminar channel flow using Particle Image Velocimetry
- Prediction of correlation between two-phase natural circulation flows in heated and unheated channels of a parallel channel system – based on electrical analogy
- Investigation of (n,γ) reactions in fissionable fluids in a hybrid reactor system
- In-pile modelling of nuclear fuel element for the MTR type reactors – Part 2
- One-step synthesis of Pt-reduced graphene oxide composites based on high-energy radiation technique
- Hamming generalized corrector for reactivity calculation
- Experimental study of flow inversion in MTR upward flow research reactors
- Technical Note
- The effect of burn up on the kinetic parameters for a pressurized water reactor fueled by MOX using MCNPX code
- Diffusion length calculations for one-speed neutrons in a slab with backward, forward and linear anisotropic scattering
- Improvement of passive shielding to reduce background components to determinate radioactivity at low energy gamma rays
- A study of the energy enhancement of electron in radio frequency (RF) linear accelerator of iris loaded waveguards
- Age-dependent effective doses for radionuclides uniformly distributed in air
