COMMIX-1A three-dimensional in-vessel simulation of the FFTF transient thermal hydraulics

Technical Report · Sat May 01 04:00:00 EDT 1982

OSTI ID:5194555

Vanka, S P; Domanus, H M; Sha, W T

The three-dimensional flow and temperature fields occurring in the FFTF during a flow transient followed by a reactor scram have been simulated by the COMMIX-1A computer code. The transient simulated corresponds to the tests conducted at the Hanford Engineering and Development Laboratory. The COMMIX-1A code employs the porous media formulation in which the concepts of volume porosity, surface permeability, distributed resistance, and distributed heat source are used to model a flow domain with internal structures. The governing equations for conservation of mass, momentum, and energy are solved as a boundary-value problem in space and as an initial-value problem in time. The present report presents the calculated results for the steady-state reactor fullpower operation and for a transient from full flow down to natural circulation combined with a power scram. The results are compared with experimental measurements, where applicable.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5194555
• Report Number(s): NUREG/CR-2773; ANL-CT-82-14; ON: DE82019343
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
C CODES
COMPUTER CODES
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID METAL COOLED REACTORS
MECHANICS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
TEMPERATURE DISTRIBUTION
TEMPERATURE GRADIENTS
TEST REACTORS
THREE-DIMENSIONAL CALCULATIONS
TRANSIENTS