The SKN (Synthetic Kernel) approximation is proposed for solving radiative transfer problems in linearly anisotropically scattering homogeneous and inhomogeneous participating plane-parallel medium. The radiative integral equations for the incident energy and the radiative heat flux using synthetic kernels are reduced to a set of coupled second-order differential equations for which proper boundary conditions are established. Performance of the three quadrature sets proposed for isotropic scattering medium are further tested for linearly anisotropically scattering medium. The method and its convergence with respect to the proposed quadrature sets are explored by comparing the results of benchmark problems using the exact, P11, and S128 solutions. The SKN method yields excellent results even for low orders using appropriate quadrature set.

1.
Altac¸, Z., 1989, “The SKN approximation: A New Method for Solving the Integral Transport Equations,” Ph.D. thesis, Iowa State University, Ames, IA.
2.
Altac¸
,
Z.
, and
Spinrad
,
B. I.
,
1990
, “
The SKN Method I: A High Order Transport Approximation to Neutron Transport Problems
,”
Nucl. Sci. Eng.
,
106
, pp.
471
479
.
3.
Spinrad
,
B. I.
, and
Altac¸
,
Z.
,
1990
, “
The SKN Method II: Heterogeneous Problems
,”
Nucl. Sci. Eng.
,
106
, pp.
480
488
.
4.
Altac¸, Z., and Tekkalmaz, M., 2001, “The SKN approximation for Solving Radiation Transport Problems In Absorbing, Emitting, and Scattering Rectangular Geometries,” Proc. 3rd International Symposium on Radiation Transfer, M. P. Mengu¨c¸ and N. Selc¸uk, eds., Begell House Inc., New York, pp. 119–129.
5.
Altac¸
,
Z.
,
2002
, “
The SKn Approximation for Solving Radiative Transfer Problems in Absorbing, Emitting, and Isotropically Scattering Plane-parallel Medium: Part I
,”
ASME J. Heat Transfer
,
124
(
4
), pp.
674
684
.
6.
O¨zis¸ik, M. N., 1973, Radiative Transfer, John Wiley & Sons, Inc.
7.
Abramowitz, M., and Stegun, I. A., 1964, Handbook of Mathematical Functions, Dover Publications Inc.
8.
Layolka, S. K., and Tsai, R. W., 1975, “A Numerical Method for Solving Integral Equations of Neutron Transport-II,” Nuclear Science & Engineering, 58, pp. 317.
You do not currently have access to this content.