last modified: 28-APR-1994 | catalog | categories | new | search |

PSR-0190 ADENA.

ADENA, Fission Products Beta Spectra and Gamma Spectra in 19 Group from U235 Pu239 Mixture

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1. NAME OR DESIGNATION OF PROGRAM:  ADENA.
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2. COMPUTERS
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Program name Package id Status Status date
ADENA PSR-0190/01 Tested 18-MAY-1984
ADENA PSR-0190/02 Tested 28-APR-1994

Machines used:

Package ID Orig. computer Test computer
PSR-0190/01 CDC CYBER 740 CDC CYBER 740
PSR-0190/02 IBM 3033 DEC VAX 6000
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3. DESCRIPTION OF PROBLEM OR FUNCTION

ADENA calculates approximately  fission-product beta and gamma decay energies and spectra in 19 or fewer energy groups from a mixture of U-235 and Pu-239 fuels. The calculation uses aggregate, adjusted data derived from a combination of several experiments and summation results based on the ENDF/B-V fission product file.
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4. METHOD OF SOLUTION

An absorption correction for U-235 and Pu-239 fuel mixtures is applied in the spectra calculation. The energies are calculated for finite, user-defined irradiation times. For long  irradiation times, the effect of neutron absorption is accounted for.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME:  14 CPU seconds on CDC CYBER 740 for test case execution.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
PSR-0190/01 18-MAY-1984 Tested at NEADB
PSR-0190/02 28-APR-1994 Tested at NEADB
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10. REFERENCES:
PSR-0190/01, included references:
- D.C. George, R.J. LaBauve and T.R. England:
  Application of Adjusted Data in Calculating Fission Product Decay
  Energies and Spectra
  LA-9362-MS (June 1982).
PSR-0190/02, included references:
- D.C. George, R.J. LaBauve and T.R. England:
  Application of Adjusted Data in Calculating Fission Product Decay
  Energies and Spectra
  LA-9362-MS (June 1982).
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11. MACHINE REQUIREMENTS:  65,200 octal words of CDC CYBER 740 main storage.
PSR-0190/02
NEA-DB implemented the program on a DEC VAX-6000 computer.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
PSR-0190/01 FORTRAN-IV
PSR-0190/02 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  NOS 1.4(CYB740).
PSR-0190/02
For the test implementation at NEA-DB, the VAX ran under VMS V.5.5-2. The source code was compiled with the FORTRAN-77  compiler V.5.5-98.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

Contributed by: Radiation Safety Information Computational Center
                Oak Ridge National Laboratory
                Oak Ridge, Tennessee, U.S.A.
Developed by:   Los Alamos National Laboratory, Los Alamos, New Mexico, USA
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16. MATERIAL AVAILABLE
PSR-0190/01
File name File description Records
PSR0190_01.002 ADENA INFORMATION 48
PSR0190_01.004 ADENA SOURCE (COMPILER READY FORM) 1291
PSR0190_01.005 ADENA TEST CASE INPUT DATA 4
PSR0190_01.006 ADENA TEST CASE PRINTED OUTPUT 46
PSR-0190/02
File name File description Records
PSR0190_02.001 Information file 103
PSR0190_02.002 Source code ADENA for IBM computers 1429
PSR0190_02.003 JCL file for IBM version 14
PSR0190_02.004 Source code for CDC machines 1288
PSR0190_02.005 Source code for VAX 1430
PSR0190_02.006 Input file 4
PSR0190_02.007 Output file 50
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17. CATEGORIES
  • B. Spectrum Calculations, Generation of Group Constants and Cell Problems
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: beta spectra, fission products, fission spectra, gamma spectra, plutonium 239, spectra, uranium 235.