ESTS0015 SCORE-EVET.
SCORE-EVET, 3-D Hydraulic Reactor Core Analysis
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| SCORE-EVET | ESTS0015/01 | Arrived | 23-MAY-2002 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| ESTS0015/01 | CDC 7600 |
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3. DESCRIPTION OF PROGRAM OR FUNCTION
SCORE-EVET was developed to study multidimensional transient fluid flow in nuclear reactor fuel rod arrays. The conservation equations used were derived by volume averaging the transient compressible three-dimensional local continuum equations in Cartesian coordinates. No assumptions associated with subchannel flow have been incorporated into the derivation of the conservation equations. In addition to the three-dimensional fluid flow equations, the SCORE-EVET code contains a one-dimensional steady state solution scheme to initialize the flow field, steady state and transient fuel rod conduction models, and comprehensive correlation packages to describe fluid-to-fuel rod interfacial energy and momentum exchange. Velocity and pressure boundary conditions can be specified as a function of time and space to model reactor transient conditions, such as a hypothesized loss-of-coolant accident (LOCA) or flow blockage. The basic volume-averaged transient three-dimensional equations for flow in porous media are solved in their general form with constitutive relationships and boundary conditions tailored to define the porous medium as a matrix of fuel rods. By retaining generality in the form of the conservation equations, a wide range of fluid flow problem configurations, from computational regions representing a single fuel rod subchannel to multichannels, or even regions without a fuel rod, can be modeled without restrictive assumptions. The completeness of the conservation equations has allowed SCORE-EVET to be used, with modification to the constitutive relationships, to calculate three-dimensional laminar boundary layer development, flow fields in large bodies of water, and, with the addition of a
turbulence model, turbulent flow in pipe expansions and tees.
SCORE-EVET was developed to study multidimensional transient fluid flow in nuclear reactor fuel rod arrays. The conservation equations used were derived by volume averaging the transient compressible three-dimensional local continuum equations in Cartesian coordinates. No assumptions associated with subchannel flow have been incorporated into the derivation of the conservation equations. In addition to the three-dimensional fluid flow equations, the SCORE-EVET code contains a one-dimensional steady state solution scheme to initialize the flow field, steady state and transient fuel rod conduction models, and comprehensive correlation packages to describe fluid-to-fuel rod interfacial energy and momentum exchange. Velocity and pressure boundary conditions can be specified as a function of time and space to model reactor transient conditions, such as a hypothesized loss-of-coolant accident (LOCA) or flow blockage. The basic volume-averaged transient three-dimensional equations for flow in porous media are solved in their general form with constitutive relationships and boundary conditions tailored to define the porous medium as a matrix of fuel rods. By retaining generality in the form of the conservation equations, a wide range of fluid flow problem configurations, from computational regions representing a single fuel rod subchannel to multichannels, or even regions without a fuel rod, can be modeled without restrictive assumptions. The completeness of the conservation equations has allowed SCORE-EVET to be used, with modification to the constitutive relationships, to calculate three-dimensional laminar boundary layer development, flow fields in large bodies of water, and, with the addition of a
turbulence model, turbulent flow in pipe expansions and tees.
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4. METHOD OF SOLUTION
The numerical technique used to solve the volume-averaged three-dimensional equations is based on the marker and cell (MAC) method for incompressible flow, as modified by Hirt and Cook, and the implicit continuous fluid Eulerian (ICE) method for compressible flow. The one-dimensional transient heat conduction equation used in the fuel rod thermal transport model is solved by dividing the fuel and cladding into a finite number of nodes and applying a Crank-Nicolson implicit finite difference formulation.
The numerical technique used to solve the volume-averaged three-dimensional equations is based on the marker and cell (MAC) method for incompressible flow, as modified by Hirt and Cook, and the implicit continuous fluid Eulerian (ICE) method for compressible flow. The one-dimensional transient heat conduction equation used in the fuel rod thermal transport model is solved by dividing the fuel and cladding into a finite number of nodes and applying a Crank-Nicolson implicit finite difference formulation.
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8. RELATED AND AUXILIARY PROGRAMS
An auxiliary program to convert the formatted water properties data to a binary data file for use by SCORE-EVET is included in the package. If the fuel rod thermal model is used, the fluid-solid interfacial heat transfer is calculated by a slightly modified version of the heat transfer and critical heat flux correlations developed for RELAP4/MOD5.
An auxiliary program to convert the formatted water properties data to a binary data file for use by SCORE-EVET is included in the package. If the fuel rod thermal model is used, the fluid-solid interfacial heat transfer is calculated by a slightly modified version of the heat transfer and critical heat flux correlations developed for RELAP4/MOD5.
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10. REFERENCES
- Walter J. Wnek, John D. Ramshaw, John A. Trapp. E. Daniel Hughes,
and Charles W. Solbrig,
"Transient Three-Dimensional Thermal-Hydraulic Analysis of Nuclear Reactor Fuel Rod Arrays: General Equations and Numerical Scheme",
ANCR-1207 (November 1975);
- C.W. Hirt and J.L. Cook,
"Calculating Three-Dimensional Flows around Structures and over
Rough Terrain",
Journal of Computational Physics, Vol. 10, pp. 324-340 (1972).
- Walter J. Wnek, John D. Ramshaw, John A. Trapp. E. Daniel Hughes,
and Charles W. Solbrig,
"Transient Three-Dimensional Thermal-Hydraulic Analysis of Nuclear Reactor Fuel Rod Arrays: General Equations and Numerical Scheme",
ANCR-1207 (November 1975);
- C.W. Hirt and J.L. Cook,
"Calculating Three-Dimensional Flows around Structures and over
Rough Terrain",
Journal of Computational Physics, Vol. 10, pp. 324-340 (1972).
ESTS0015/01, included references:
- R.L. Benedetti, L.V. Lords and D.M. Kiser:SCORE-EVET - A Computer Code for the Multidimensional Transient
Thermal-Hydraulic Analysis of Nuclear Fuel Rod Arrays
TREE-NUREG-1133 (February 1978).
- L. Eyberger:
SCORE-EVET Tape Description and Implementation Information
NESC 82-89 (August 14, 1982) + Attachments.
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ESTS0015/01
source program mag tapeSCORE-EVET Source File SRCTPtest-case data mag tapeSCORE-EVET Sample Problem 1 DATTP
test-case data mag tapeSCORE-EVET Sample Problem 2 DATTP
test-case data mag tapeSCORE-EVET Sample Problem 3 DATTP
symb data lib mag tapeFormatted Water Properties Library LBSTP
test-case data mag tapeConversion Program to Create Binary Water DATTP
test-case data mag tapeJCL Control Information DATTP
test-case output listing Sample Problem 1, Cycle 600 Output OUTLS
test-case output listing Sample Problem 2, Cycle 1000 Output OUTLS
report TREE-NUREG-1133 (February 1978) REPPT
prog. note NESC Note 82-89 (August 14, 1982) NOTPT
Keywords: equations of state, fluid flow, fuel rods, heat transfer, hydraulics, loss-of-coolant accident, transients.