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NESC0223 GAD-2.

GAD-2, Fuel Cycle Depletion Calculation with Partial Refueling and Fuel Recycling

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1. NAME OR DESIGNATION OF PROGRAM:  GAD-2.
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2. COMPUTERS
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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.
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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.
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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.
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6. TYPICAL RUNNING TIME:  1 to 3 minutes are required.
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7. UNUSUAL FEATURES OF THE PROGRAM

This program is useful in studying  the approach to equilibrium fuel cycle.
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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).
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9. STATUS
Package ID Status date Status
NESC0223/01 01-OCT-1966 Tested at NEADB
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10. REFERENCES
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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11. MACHINE REQUIREMENTS:  32k IBM7044, 3 tapes (input, output, system).
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0223/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  IBM 7040/7044 operating system (16/32k), version ix.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

                 F. W. Todt
                 Gulf General Atomic Incorporated
                 P. O. Box 608
                 San Diego, California 92112
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16. MATERIAL AVAILABLE
NESC0223/01
File name File description Records
NESC0223_01.001 SOURCE & DATA FORTRAN 4 3360
NESC0223_01.002 OUTPUT 1948
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: depletion, fuel cycle.