NESC0223 GAD-2.
GAD-2, Fuel Cycle Depletion Calculation with Partial Refueling and Fuel Recycling
NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, 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 OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, OTHER RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| GAD-2 | NESC0223/01 | Tested | 01-OCT-1966 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NESC0223/01 | IBM 7044 | IBM 7044 |
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3. NATURE OF PHYSICAL PROBLEM SOLVED
This infinite-medium depletion program performs fuel cycle calculations on reactors employing partial refueling. The burnup of up to 12 discrete fuel compositions (regions or stages of irradiation) may be followed simultaneously. The burnup calculation may be interrupted periodically to remove the contents and to refuel one or more regions. Fuel may be partially or completely recycled.
This infinite-medium depletion program performs fuel cycle calculations on reactors employing partial refueling. The burnup of up to 12 discrete fuel compositions (regions or stages of irradiation) may be followed simultaneously. The burnup calculation may be interrupted periodically to remove the contents and to refuel one or more regions. Fuel may be partially or completely recycled.
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4. METHOD OF SOLUTION
All regions are assumed to be subjected to the same neutron flux and the depletion calculations are performed with a series of short time-steps. After each time-step the flux amplitude is renormalized to the power and the spectrum may be recalculated after a specified series of these steps.
All regions are assumed to be subjected to the same neutron flux and the depletion calculations are performed with a series of short time-steps. After each time-step the flux amplitude is renormalized to the power and the spectrum may be recalculated after a specified series of these steps.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
Maximum number of energy groups = 15
Maximum number of fuel compositions or regions = 12
Maximum number of nuclides per region = 35
Maximum number of moderator nuclides with thermal transfer matrix = 3.
2 fixed heavy nuclide chains are always present.
Maximum number of energy groups = 15
Maximum number of fuel compositions or regions = 12
Maximum number of nuclides per region = 35
Maximum number of moderator nuclides with thermal transfer matrix = 3.
2 fixed heavy nuclide chains are always present.
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8. RELATED AND AUXILIARY PROGRAMS
This code is a simplified version of the GAD code (GA-4150) which runs about 4 times longer but contains variable shielding factors, control searches, and cost calculations. Cards may be punched at each time-step in a format acceptable to the WAMPUM fuel cycle cost code (ACC abstract 224).
This code is a simplified version of the GAD code (GA-4150) which runs about 4 times longer but contains variable shielding factors, control searches, and cost calculations. Cards may be punched at each time-step in a format acceptable to the WAMPUM fuel cycle cost code (ACC abstract 224).
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NESC0223/01, included references:
- F.W. Todt:Revised GAD - An Infinite Medium Depletion Program for Reactor
Fuel Cycle Analysis
GA-6635 (November 10, 1965).
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NESC0223/01
| File name | File description | Records |
|---|---|---|
| NESC0223_01.001 | SOURCE & DATA FORTRAN 4 | 3360 |
| NESC0223_01.002 | OUTPUT | 1948 |
Keywords: depletion, fuel cycle.