Assembly homogenization techniques for core calculations

Abstract We have applied the black-box paradigm to assembly homogenization and introduced current discontinuity factors (CDFs) for an arbitrary low-order operator in the presence of boundary leakage. The CDFs preserve average reaction rates and the assembly partial currents in a given reference situation as well for full assembly as for pin-by-pin homogenization. In the presence of surface leakage, the CDFs depend on the discretization of the low-order operator but can be determined from a few calculations with the low-order operator without scattering. For diffusion-like, low-order operators, the CDFs can be advantageously replaced by flux discontinuity factors (FDFs), which also preserve partial currents. However, the effect of the FDFs is not equivalent to that of the CDFs in the final core calculation. Unlike the CDFs, that are double-valued for homogenization with surface leakage, the FDFs are always single valued. The cases when the low-order operator is diffusion, SP N or quasidiffusion are discussed in detail. We also show that, for full-assembly homogenization without boundary leakage, the FDFs are identical to Smith's discontinuity coefficients (DCs) only if the reference calculation has also been done with diffusion. In the case of diffusion, preliminary test calculations for small PWR motifs show that the FDFs and Smith's DCs give close results, with a better precision for the FDFs when transport effects are predominant.

[1]  Alain Hébert,et al.  Development of a Third-Generation Superhomogénéisation Method for the Homogenization of a Pressurized Water Reactor Assembly , 1993 .

[2]  Dmitriy Y. Anistratov,et al.  HOMOGENIZATION METHODOLOGY FOR THE LOW-ORDER EQUATIONS OF THE QUASIDIFFUSION METHOD , 2002 .

[3]  K. Koebke,et al.  A new approach to homogenization and group condensation , 1980 .

[4]  Farzad Rahnema,et al.  Leakage corrected spatial (assembly) homogenization technique , 1997 .

[5]  A. Kavenoky,et al.  The SPH homogenization method , 1980 .

[6]  Dmitriy Anistratov,et al.  Splitting Method for Solving the Coarse-Mesh Discretized Low-Order Quasi-Diffusion Equations , 2005 .

[7]  G. C. Pomraning Asymptotic and variational derivations of the simplified PN equations , 1993 .

[8]  Igor Zmijarevic,et al.  APOLLO II: A User-Oriented, Portable, Modular Code for Multigroup Transport Assembly Calculations , 1988 .

[9]  Giuseppe Palmiotti,et al.  Simplified spherical harmonics in the variational nodal method , 1997 .

[10]  K. Koebke,et al.  On the Reconstruction of Local Homogeneous Neutron Flux and Current Distributions of Light Water Reactors from Nodal Schemes , 1985 .

[11]  M. J. Abbate,et al.  Methods of Steady-State Reactor Physics in Nuclear Design , 1983 .

[12]  Razvan Nes,et al.  AN ADVANCED NODAL DISCRETIZATION FOR THE QUASI-DIFFUSION LOW-ORDER EQUATIONS , 2002 .

[13]  S. Mittag,et al.  Discontinuity factors for non-multiplying material in two-dimensional hexagonal reactor geometry , 2003 .

[14]  Edward W. Larsen,et al.  Neutron transport and diffusion in inhomogeneous media. I , 1975 .

[15]  Ivan Petrovic,et al.  B N Theory: Advances and New Models for Neutron Leakage Calculation , 2002 .

[16]  D. Leslie THE WEIGHTING OF DIFFUSION COEFFICIENTS IN CELL CALCULATIONS , 1962 .

[17]  Richard Sanchez DUALITY, GREEN'S FUNCTIONS AND ALL THAT , 1998 .

[18]  K. Smith,et al.  ASSEMBLY HOMOGENIZATION TECHNIQUES FOR LIGHT WATER REACTOR ANALYSIS , 1986 .

[19]  M.M.R. Williams,et al.  Handbook of nuclear reactor calculations: Vols I-III, pp. 475, 523 and 465, respectively, Y. Ronen, Ed. CRC Press, West Palm Beach, Florida (1986) , 1988 .

[20]  F. Rahnema,et al.  A heterogeneous finite element method in diffusion theory , 2003 .

[21]  NEUTRON DIFFUSION IN A SPACE LATTICE OF FISSIONABLE AND ABSORBING MATERIALS , 1946 .

[22]  Kord Sterling Smith,et al.  Spatial homogenization methods for light water reactor analysis , 1980 .

[23]  Moon Hee Chang,et al.  DYNAMIC IMPLEMENTATION OF THE EQUIVALENCE THEORY IN THE HETEROGENEOUS WHOLE CORE TRANSPORT CALCULATION , 2002 .

[24]  Farzad Rahnema,et al.  A Monte Carlo based nodal diffusion model for criticality analysis of spent fuel storage lattices , 2003 .

[25]  Dmitriy Anistratov,et al.  Nonlinear methods for solving particle transport problems , 1993 .

[26]  Allan F. Henry,et al.  Nuclear Reactor Analysis , 1977, IEEE Transactions on Nuclear Science.

[27]  M.M.R. Williams,et al.  A transport theory calculation of neutron flux, disadvantage factors and effective diffusion coefficients in square cells and slabs , 1972 .

[28]  Alain Hébert,et al.  A consistent technique for the pin-by-pin homogenization of a pressurized water reactor assembly , 1993 .

[29]  Anne-Marie Baudron,et al.  MINOS: A Simplified Pn Solver for Core Calculation , 2007 .

[30]  Dmitriy Anistratov,et al.  Homogenization Method for the Two-Dimensional Low-Order Quasi-Diffusion Equations for Reactor Core Calculations , 2006 .

[31]  J. M. Aragones,et al.  A Linear Discontinuous Finite Difference Formulation for Synthetic Coarse-Mesh Few-Group Diffusion Calculations , 1986 .