Analytical benchmark test set for criticality code verification

A number of published numerical solutions to analytic eigenvalue (k{sub eff}) and eigenfunction equations are summarized for the purpose of creating a criticality verification benchmark test set. The 75-problem test set allows the user to verify the correctness of a criticality code for infinite medium and simple geometries in one- and two-energy groups, one- and two-media, and both isotropic and linearly anisotropic neutron scattering. A three- and six-energy group infinite medium problem are also included in the test set. The problem specifications will produce both k{sub eff}=1 and the quoted k{sub {infinity}} to at least five decimal places. Additional uses of the test set for code verification are also discussed. Los Alamos report LA-13511 contains the details of all 75 test problems.

[1]  G. C. Pomraning,et al.  Linear Transport Theory , 1967 .

[2]  J. F. Briesmeister.  MCNP-A General Monte Carlo N-Particle Transport Code , 1993 .

[3]  R. M. Westfall.  Benchmark solutions for the infinite critical cylinder , 1983 .

[4]  R. A. Forster,et al.  Analytical Benchmark Test Set for Criticality Code Verification , 1999 .

[5]  R. A. Forster,et al.  TWO-GROUP TRANSPORT SOLUTIONS TO THE ONE-DIMENSIONAL CRITICAL SLAB PROBLEM. , 1969 .

[6]  N. G. Sjöstrand,et al.  Criticality and time eigenvalues in one-speed neutron transport , 1990 .

[7]  M. A. Atalay.  The critical slab problem for reflecting boundary conditions in one-speed neutron transport theory , 1996 .

[8]  G. Spiga,et al.  Anisotropy of Scattering and Fission in Neutron Transport Theory , 1977 .

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

[10]  N. Garis,et al.  One-Speed Neutron Transport Eigenvalues for Reflected Slabs and Spheres , 1991 .

[11]  R. S. Baker,et al.  DANTSYS: A diffusion accelerated neutral particle transport code system , 1995 .

[12]  D. G. Hurst,et al.  Reactor Physics Constants , 1964 .

[13]  Roberto D. M. Garcia,et al.  Two-Media Problems in Two-Group Neutron Transport Theory , 1978 .

[14]  G. E. Bosler,et al.  CRITICAL SLAB SOLUTION TO THE TWO-GROUP NEUTRON TRANSPORT EQUATION FOR LINEARLY ANISOTROPIC SCATTERING. , 1972 .

[15]  Ely M. Gelbard,et al.  Computation of standard deviations in Eigenvalue calculations , 1990 .

[16]  E. Lewis,et al.  Computational Methods of Neutron Transport , 1993 .

[17]  A. Leonard,et al.  Comparisons of Exact and SN Solutions of the Monoenergetic Critical Equation with Anisotropic Scattering , 1965 .

[18]  C. A. Zoldi.  A Numerical and Experimental Study of a Shock-Accelerated Heavy Gas Cylinder , 2002 .

[19]  J. E. Stewart,et al.  MONOENERGETIC NEUTRON TRANSPORT IN A FINITE CRITICAL REFLECTED SLAB SYSTEM. , 1972 .

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

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

[22]  C. E. Siewert,et al.  F/sub N/ method in neutron-transport theory. Part II: applications and numerical results , 1979 .

[23]  Robert M. Westfall,et al.  Singular eigenfunction solution of the monoenergetic neutron transport equation for finite radially reflected critical cylinders. , 1973 .

[24]  C. E. Siewert,et al.  On Two-Group Critical Problems in Neutron-Transport Theory , 1986 .

[25]  M. A. Atalay.  The reflected slab and sphere criticality problem with anisotropic scattering in one-speed neutron transport theory , 1997 .

[26]  N. G. Sjöstrand.  Criticality of reflected spherical reactors for neutrons of one speed , 1986 .

[27]  D. C. Sahni,et al.  Real criticality eigenvalues of the one-speed-linear transport operator , 1995 .

[28]  G. Leaf,et al.  Benchmark Values for the Slab and Sphere Criticality Problem in One-Group Neutron Transport Theory , 1974 .

[29]  D. C. Sahni,et al.  Some new results pertaining to criticality and time eigenvalues of one-speed neutron transport equation , 1996 .

[30]  E. B. Dahl,et al.  Eigenvalue Spectrum of Multiplying Slabs and Spheres for Monoenergetic Neutrons with Anisotropic Scattering , 1979 .

[31]  C. E. Siewert,et al.  Neutron transport in two dissimilar media with anisotropic scattering , 1976 .

[32]  Barry D Ganapol,et al.  The Green's function method for nuclear engineering applications , 1997 .