Development of a computer code for thermal hydraulics of reactors (THOR). Seventh quarterly progress report, April--June 1976. [BWR; PWR].

Author: Levine, M. M.
Published: United States : [publisher not identified], 1976.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1976.
Physical Description: microfiche : negative ; 11 x 15 cm

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Summary

The purpose of the code development work reported is to construct a computer code for the prediction of thermohydraulic transients in water-cooled nuclear reactor systems. The fundamental formulation of fluid dynamics is to be based on the one-dimensional drift flux model for non-homogeneous, non-equilibrium flows of two-phase mixtures. Particular emphasis is placed on component modeling, automatic predictions of initial steady state conditions, freedom in the selection of computed spatial detail, development of reliable constitutive descriptions, and modular code structure. The hydraulic finite difference code based on the implicit Euler method has been applied to the RSR Standard Problem Number 2. The Reference Code, based on the method of characteristics, was modified for later application to transients ending in a steady state. Modifications were begun on the Reference Code to incorporate an improved phase change algorithm. Expressions were developed for computing vapor diffusion velocity from vapor drift velocity for various flow regimes in horizontal and vertical pipes. Preliminary analysis has been started on the steam generator; order of magnitude calculations were performed to assay the important effects. A network model of the reactor hydraulic system has been formulated on the nodal basis. The system state is given by the pressure, mixture enthalpy, and vapor concentration at each node (interface), and flow rates in each path (one dimensional component). The number and types of equations required to achieve system balance have been specified. The computation for system balance has been worked out. A host code structured program was written and checked using a library of dummy subroutines to describe the reactor components.

Report Numbers

BNL-NUREG-50618

Other Subject(s)

Collection

U.S. Atomic Energy Commission depository collection.

Note

DOE contract number: EY-76-C-02-0016
OSTI Identifier 7216001
Research organization: Brookhaven National Lab., Upton, NY (USA).

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