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NEA-0475 RASPA.

RASPA, Burnup with Fission Products Inventory, Gamma Spectra, Isotopic Power Density

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1. NAME OR DESIGNATION OF PROGRAM:  RASPA.
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2. COMPUTERS
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Program name Package id Status Status date
RASPA NEA-0475/01 Tested 01-MAY-1979

Machines used:

Package ID Orig. computer Test computer
NEA-0475/01 CDC 7600 CDC 7600
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3. NATURE OF PHYSICAL PROBLEM SOLVED

The program calculates the build-up, decay and burnup of fissionable isotopes and their fission products. It calculates for variable time steps the concentrations,  the decay heat, the total burnup, the gamma spectrum in any energy groups and the power density of the isotopes.
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4. METHOD OF SOLUTION

The time dependent variations of the concentrations are described by a system of linear ordinary differential equations of first order with constant coefficients (if the flux is held constant). This system is especially easily solved  in the case of a triangular matrix of the coefficients. Such a triangular form is attainable by:
(1) Restriction to reactions of the following kind:
    (a) fission
    (b) (n,gamma) reaction (capture)
    (c) beta decay
    (d) gamma decay of the excited states of the nuclei
(2) Arrangement of the isotopes in a special order.
This means neglecting reactions of the kind (n,alpha), (n,2n), emission of neutrons (formation of delayed neutrons) and similar processes which are in general of less importance.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The code is zero- dimensional. The data of a reactor core or a zone of it must be represented by adequate average values.
Further restrictions are

- only reactions as indicated in section 4 are taken into account.
- number of fissionable isotopes lower or equal to 15
- number of fission products and fissionable isotopes lower or equal   to 600
- number of gamma energy groups lower or equal to 20.
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6. TYPICAL RUNNING TIME

The running time depends mainly on the number  of power steps. For a typical case with 10 power steps the time will be 5 minutes.
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7. UNUSUAL FEATURES

UNUSUAL FEATURES OF THE PROGRAM. A number of auxiliary routines evaluate the main results for various aspects.
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8. RELATED OR AUXILIARY PROGRAMS

RELATED AND AUXILIARY PROGRAMS.
- A routine which condenses the results (decay heat) of the main   program for various core zones.
- A routine which integrates the decay heat.
- A routine which performs an uncertainty analysis using a special   Monte Carlo technique.
- A plotter routine (CALCOMP microfilm plotter).
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9. STATUS
Package ID Status date Status
NEA-0475/01 01-MAY-1979 Tested at NEADB
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10. REFERENCES
NEA-0475/01, included references:
- G. Groenefeld:
  The Decay Heat of Fission Products and Actinides of the SNR-300
  INTERATOM, Technischer Bericht ITB 76/08 (January 1976)
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11. MACHINE REQUIREMENTS:  CDC CYBER 172.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0475/01 FORTRAN-IV
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13. OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED:  SCOPE 3.4.
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14. ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

Some auxiliary routines which are used at INTERATOM only. They can be replaced by dummy or corresponding routines of the user.
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15. NAME AND ESTABLISHMENT OF AUTHOR

    G. Groenefeld
    INTERATOM
    D-5060 Bergisch Gladbach 1
    Germany, F.R.
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16. MATERIAL AVAILABLE
NEA-0475/01
File name File description Records
NEA0475_01.001 SOURCE PROGRAM 5992
NEA0475_01.002 LIBRARY DATA 9205
NEA0475_01.003 SAMPLE PROBLEM INPUT DATA (CASE 1) 78
NEA0475_01.004 SAMPLE PROBLEM INPUT DATA (CASE 2) 26
NEA0475_01.005 SAMPLE PROBLEM INPUT DATA (CASE 3) 117
NEA0475_01.006 SAMPLE PROBLEM PRINTED OUTPUT (CASE 1) 4782
NEA0475_01.007 SAMPLE PROBLEM PRINTED OUTPUT (CASE 2) 40
NEA0475_01.008 SAMPLE PROBLEM PRINTED OUTPUT (CASE 3) 19761
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: buildup, burnup, decay, fission products, gamma spectra, isotopes, radiation heat.