NEA-0475 RASPA.
RASPA, Burnup with Fission Products Inventory, Gamma Spectra, Isotopic Power Density
NAME OR DESIGNATION OF PROGRAM, COMPUTER, NATURE OF PHYSICAL PROBLEM SOLVED, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, FEATURES, AUXILIARIES, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM OR MONITOR UNDER WHICH PROGRAM IS EXECUTED, ANY OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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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.
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.
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.
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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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).
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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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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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 |
Keywords: buildup, burnup, decay, fission products, gamma spectra, isotopes, radiation heat.