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Time-step selection considerations in the analysis of reactor transients with DIF3D-K

Conference ·
OSTI ID:10159335
The DIF3D-K code solves the three-dimensional, time-dependent multigroup neutron diffusion equations by using a nodal approach for spatial discretization and either the theta method or one of three space-time factorization approaches for temporal integration of the nodal equations. The three space-time factorization options (namely, improved quasistatic, adiabatic and conventional point kinetics) were implemented because of their potential efficiency advantage for the analysis of transients in which the flux shape changes more slowly than its amplitude. Here we describe the implementation of DIF3D-K as the neutronics module within the SAS-HWR accident analysis code. We also describe the neutronics-related time step selection algorithms and their influence on the accuracy and efficiency of the various solution options.
Research Organization:
Argonne National Lab., IL (United States). Reactor Analysis Div.
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
W-31109-ENG-38
OSTI ID:
10159335
Report Number(s):
ANL/RA/CP--78587; CONF-930601--15; ON: DE93012889
Country of Publication:
United States
Language:
English