CUED Publications database

Microscopic depletion with the correction of microscopic cross sections in nodal diffusion code DYN3D

Bilodid, Y and Fridman, E and Kliem, S and Kotlyar, D and Shwageraus, E (2016) Microscopic depletion with the correction of microscopic cross sections in nodal diffusion code DYN3D. In: UNSPECIFIED pp. 1205-1214..

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Abstract

The evolution of nuclear fuel nuclide content with burnup is affected by operating conditions (e.g. coolant density, fuel temperature, boron acid concentration, etc.), which vary in time and space and cannot be predicted in advance. However, lattice codes assume some average fuel depletion conditions to generate homogenized macroscopic cross sections (XS) for nodal diffusion codes such as DYN3D. Deviation of local operational history from average conditions leads to accumulation of errors in XS, which is referred as spectral history effects. The paper presents a general hybrid method that combines the detailed isotopic depletion with correction of micro- and macro-diffusion parameters to better account for the spectral history effects. The method was implemented in DYN3D and verified against Monte Carlo code Serpent, which was also used to generate the XS. The observed differences are within the statistical uncertainties. The paper also discusses the number of considered nuclides, optimization of computational costs and possible utilization of the detailed nuclide content for explicit decay heat calculation.

Item Type: Conference or Workshop Item (UNSPECIFIED)
Subjects: UNSPECIFIED
Divisions: Div A > Energy
Depositing User: Cron Job
Date Deposited: 17 Jul 2017 19:39
Last Modified: 03 Aug 2017 03:11
DOI: