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An Inline Burnup Algorithm.
- Source :
-
Nuclear Science & Engineering . Aug2023, Vol. 197 Issue 8, p1681-1699. 19p. - Publication Year :
- 2023
-
Abstract
- Inline algorithms have been proposed for coupling Monte Carlo neutron transport solvers with several other physics, such as xenon and iodine densities and thermal hydraulics. This paper proposes a new inline algorithm that can be applied to burnup calculations. The algorithm is a modification of the predictor-corrector method, where the corrector-step nuclide densities are converged simultaneously with the fission source. This could, in principle, obviate the need for two full neutronics solutions per time-step while still allowing the accuracy of predictor-corrector methods with improved stability. This paper describes the algorithm and demonstrates its stability properties through a Fourier analysis. Although not unconditionally stable, judicious use of batching and relaxation are shown to greatly improve the algorithm's stability properties in realistic systems. [ABSTRACT FROM AUTHOR]
Details
- Language :
- English
- ISSN :
- 00295639
- Volume :
- 197
- Issue :
- 8
- Database :
- Academic Search Index
- Journal :
- Nuclear Science & Engineering
- Publication Type :
- Academic Journal
- Accession number :
- 164872225
- Full Text :
- https://doi.org/10.1080/00295639.2022.2106732