Alternative scattering kernels for the first estimates of a reactor:diffusion length

作     者：Hakan Oztürk Ayca Simsek Yapar 

作者机构：Department of PhysicsFaculty of Arts and SciencesOsmaniye Korkut Ata University80000 OsmaniyeTurkey 

出 版 物：《Nuclear Science and Techniques》 (核技术（英文）)

年 卷 期：2018年第29卷第3期

页      面：86-91页

核心收录：

学科分类：08[工学] 0807[工学-动力工程及工程热物理] 0827[工学-核科学与技术] 0703[理学-化学] 0702[理学-物理学] 0801[工学-力学（可授工学、理学学位）] 

基　　金：supported by the Academic Research Projects Unit of Osmaniye Korkut Ata University(No.OKBAP-2014-PT3-019) 

主　　题：Scattering kernel Diffusion length Chebyshev polynomials Transport equation 

摘      要：Diffusion-length calculations of neutrons are performed using the Chebyshev polynomials of the second kind. The neutrons are assumed to move with constant energy in a uniform homogeneous slab. An alternative scattering kernel called an Anl?–Gngr phase function and a traditional Henyey–Greenstein phase function are used for the scattering function in the stationary neutron transport equation. First, analytic expressions and then numerical results are obtained for the diffusion length for various values of the scattering and cross-sectional *** results obtained from both scattering kernels for the diffusion length of the neutrons are given in tables side by side for comparison. The applicability of the method is easily demonstrated by these results.