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

Y. Bilodid, E. Fridman, S. Kliem, D. Kotlyar, E. Shwageraus

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

1 Scopus citations

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.

Original languageEnglish
Title of host publicationPhysics of Reactors 2016, PHYSOR 2016
Subtitle of host publicationUnifying Theory and Experiments in the 21st Century
PublisherAmerican Nuclear Society
Pages1205-1214
Number of pages10
ISBN (Electronic)9781510825734
StatePublished - 1 Jan 2016
Externally publishedYes
EventPhysics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016 - Sun Valley, United States
Duration: 1 May 20165 May 2016

Publication series

NamePhysics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century
Volume2

Conference

ConferencePhysics of Reactors 2016: Unifying Theory and Experiments in the 21st Century, PHYSOR 2016
Country/TerritoryUnited States
CitySun Valley
Period1/05/165/05/16

Keywords

  • CRAM
  • DYN3D
  • History effects
  • Micro-depletion

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Nuclear and High Energy Physics

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