IAEA0835 FASVER2.
FASVER, 2 Group 2-D Diffusion in X-Y Geometry and Adjoint Solution for PWR with Reflector
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM 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 PROGRAMMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| FASVER-4 | IAEA0835/02 | Tested | 03-JUL-1986 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| IAEA0835/02 | DEC VAX 11/750 | IBM 3081 |
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3. DESCRIPTION OF PROBLEM OR FUNCTION
FASVER2 solves the two-group two dimensional (x-y geometry) stationary diffusion equation of reactor physics. It is designed for the octant geometry of a typical PWR core with reflector. The adjoint equation may also be solved.
FASVER4 performs the same calculations as FASVER2, but for one quadrant geometry of a PWR core.
FASVER2 solves the two-group two dimensional (x-y geometry) stationary diffusion equation of reactor physics. It is designed for the octant geometry of a typical PWR core with reflector. The adjoint equation may also be solved.
FASVER4 performs the same calculations as FASVER2, but for one quadrant geometry of a PWR core.
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4. METHOD OF SOLUTION
The diffusion equation is solved using the finite differences method. Each group equation is discretized on a different mesh. The thermal flux is defined on a mesh that is three times smaller than that for the fast flux. The fission density is defined on the coarse fast flux mesh. SOR acceleration is used for the inner iterations. The SOR parameters may be evaluated in advance using the eigenvalue of the homogeneous part of the respective finite difference group equation. Alternatively the SOR parameters may be inserted externally. If an eigenvalue problem is solved, Chebyshev polynomials are used to accelerate the outer iterations.
Fuel elements are considered to be quadratic, and group constants (i.e. cross sections) assumed constant over each fuel element with discontinuities between different fuel elements.
The diffusion equation is solved using the finite differences method. Each group equation is discretized on a different mesh. The thermal flux is defined on a mesh that is three times smaller than that for the fast flux. The fission density is defined on the coarse fast flux mesh. SOR acceleration is used for the inner iterations. The SOR parameters may be evaluated in advance using the eigenvalue of the homogeneous part of the respective finite difference group equation. Alternatively the SOR parameters may be inserted externally. If an eigenvalue problem is solved, Chebyshev polynomials are used to accelerate the outer iterations.
Fuel elements are considered to be quadratic, and group constants (i.e. cross sections) assumed constant over each fuel element with discontinuities between different fuel elements.
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6. TYPICAL RUNNING TIME
About 50 secs. on CYBER 172 for a typical PWR core with about 7000 thermal mesh points to achieve a relative accuracy of 10**-3.
About 50 secs. on CYBER 172 for a typical PWR core with about 7000 thermal mesh points to achieve a relative accuracy of 10**-3.
IAEA0835/02
NEA-DB executed the test cases included in this package on an IBM 3081 computer. Required CPU times were: 1 min. 13 secs. for test case 1, and 1 min. 53 secs. for test case 2.[ top ]
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10. REFERENCES
- M. Ravnik, S. Slavic,
"FASVER2 - Description of a Fortran Program for 2-D Two Group
Diffusion Calculation of Power Density in PWR Core"
IJS-DP-1698 (1979).
- M. Ravnik, S. Slavic,
"FASVER2 - Description of a Fortran Program for 2-D Two Group
Diffusion Calculation of Power Density in PWR Core"
IJS-DP-1698 (1979).
IAEA0835/02, included references:
- M. Ravnik and S. Slavic:FASVER4 - Fortran Program for Diffusion Calculations of PWR Core
in Quadrant Symmetry.
IJS-DP-4263 (January 1986)
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IAEA0835/02
To run the test cases included in this package on an IBM 3081 computer, 828K bytes of main storage were required.[ top ]
IAEA0835/02
MVS/SP (IBM 3081).[ top ]
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IAEA0835/02
| File name | File description | Records |
|---|---|---|
| IAEA0835_02.001 | Information file | 62 |
| IAEA0835_02.002 | FASVER-4 source (fortran) | 3960 |
| IAEA0835_02.003 | Dummy routines (elapsed time, time and date) | 14 |
| IAEA0835_02.004 | JCL to run sample cases | 65 |
| IAEA0835_02.005 | Sample case 1 input | 87 |
| IAEA0835_02.006 | Sample case 1 output (unit 2) | 2144 |
| IAEA0835_02.007 | Sample case 1 output (unit 6) | 70 |
| IAEA0835_02.008 | Sample case 2 input | 166 |
| IAEA0835_02.009 | Sample case 2 output (unit 2) | 3553 |
| IAEA0835_02.010 | Sample case 2 output (unit 6) | 55 |
Keywords: diffusion equations, pwr reactors, two-dimensional, two-group.