Time-step selection considerations in the analysis of reactor transients with DIF3D-K
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; TRN: 93:016359
- Resource Relation:
- Conference: American Nuclear Society (ANS) annual meeting,San Diego, CA (United States),20-24 Jun 1993; Other Information: PBD: [1993]
- Country of Publication:
- United States
- Language:
- English
Similar Records
An improved quasistatic option for the DIF3D nodal kinetics code
An improved quasistatic option for the DIF3D nodal kinetics code
Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
REACTOR PHYSICS
D CODES
TRANSIENTS
REACTOR ACCIDENTS
REACTOR SAFETY
HEAT TRANSFER
HYDRAULICS
COMPUTER CALCULATIONS
ALGORITHMS
NEUTRON FLUX
220100
990200
220900
THEORY AND CALCULATION
MATHEMATICS AND COMPUTERS