Numerical benchmark solutions for time-dependent neutral particle transport in one-dimensional homogeneous media using integral transport

The time-dependent, neutral particle, single-collision kernels have been used to produce benchmark type solutions in one-dimensional planar and spherical geometries. The solution procedure begins with the formulation of an inhomogeneous integral equation for time-dependent transport. This equation is evaluated using standard integral equation methods and numerical integration techniques. Excellent agreement with benchmark values in the available literature have been achieved for singular sources in planar and spherical infinite medium geometries. The solution technique has been further used to produce finite medium benchmark solutions in the same one-dimensional geometries. This work once again demonstrates, what past experience with steady-state problems has shown, that highly accurate solutions for neutral particle transport can be obtained using the integral equation formulation of the transport equation.

[1]  P. W. McKenty,et al.  The Generation of Time-Dependent Neutron Transport Solutions in Infinite Media , 1977 .

[2]  G. I. Bell,et al.  Nuclear Reactor Theory , 1952 .

[3]  Peter Linz,et al.  Analytical and numerical methods for Volterra equations , 1985, SIAM studies in applied and numerical mathematics.

[4]  S. Loyalka A Numerical Method for Solving Integral Equations of Neutron Transport , 1975 .

[5]  J. Duderstadt,et al.  Nuclear reactor analysis , 1976 .

[6]  J. Douglas Faires,et al.  Numerical Analysis , 1981 .

[7]  William H. Press,et al.  Numerical Recipes: FORTRAN , 1988 .

[8]  Leonard Lewin,et al.  Polylogarithms and Associated Functions , 1981 .

[9]  B. Ganapol,et al.  Time-dependent emergent intensity from an anisotropically-scattering semi-infinite atmosphere , 1982 .

[10]  Barry D Ganapol,et al.  Benchmark values for monoenergetic neutron transport in one-dimensional cylindrical geometry with linearly anisotropic scattering , 1983 .

[11]  Barry D Ganapol SOLUTION OF THE ONE-GROUP TIME-DEPENDENT NEUTRON TRANSPORT EQUATION IN AN INFINITE MEDIUM BY POLYNOMIAL RECONSTRUCTION. , 1986 .

[12]  D. Henderson,et al.  TIME DEPENDENT RADIATION TRANSPORT IN HOHLRAUMS USING INTEGRAL TRANSPORT METHODS , 1998 .

[13]  B. Ganapol Reconstruction of the time-dependent monoenergetic neutron flux from moments , 1985 .

[14]  Gennadi Vainikko,et al.  Multidimensional Weakly Singular Integral Equations , 1993 .

[15]  P. F. Windhofer,et al.  Multiple-Collision Solutions for Time-Dependent Neutron Transport in Slabs of Finite Thickness , 1985 .

[16]  J. Palmeri The one-dimensional monoenergetic time-dependent transport equation in infinite media (revisited) , 1987 .

[17]  Kendall E. Atkinson An introduction to numerical analysis , 1978 .

[18]  D. Henderson,et al.  Time-Dependent Single-Collision Kernels for Integral Transport Theory , 1989 .

[19]  D. Henderson,et al.  Fuel assembly pulsing using time-dependent integral transport methods , 1997 .

[20]  David R. Kincaid,et al.  Numerical mathematics and computing , 1980 .

[21]  B. Ganapol,et al.  Collided flux expansion method for time-dependent neutron transport , 1973 .