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A Finite Element Depletion Diffusion Calculation Method with Space-Dependent Cross Sections

Alain Kavenoky, Jean-Jacques Lautard

Nuclear Science and Engineering / Volume 64 / Number 2 / October 1977 / Pages 563-575

Technical Paper / dx.doi.org/10.13182/NSE77-A27390

A new solution method for the diffusion depletion equation is presented. Space-dependent macroscopic cross sections are represented in the framework of a finite element basis, and the finite element method is extended to deal with these space-dependent cross sections. This method has been implemented in the NEPTUNE system of reactor calculation to be applied to two- and three-dimensional depletion calculation of large reactors. Numerical calculations are presented, and comparisons are performed with standard methods.