last modified: 31-MAR-1988 | catalog | categories | new | search |

NEA-0951 NUCCON.

NUCCON, Nuclide Concentration and Activation in D-T Fusion Reactor

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1. NAME OR DESIGNATION OF PROGRAM:  NUCCON.
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2. COMPUTERS
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Program name Package id Status Status date
NUCCON NEA-0951/01 Tested 31-MAR-1988

Machines used:

Package ID Orig. computer Test computer
NEA-0951/01 SIEMENS 7880 IBM 3090
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3. DESCRIPTION OF PROGRAM OR FUNCTION

Basically, the program calculates the changes in the nuclide concentration and activation of given materials in a D-T fusion reactor under neutron irradiation. The user has to construct an activation chain, which is the model of the physical processes going on during an irradiation period.
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4. METHOD OF SOLUTION

The physical processes during an irradiation period can mathematically be described as a system of linear homogeneous differential equations of the first order. The program solves this system by the "matrix exponential method" (MATEXP).
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The max. number of nuclides of an activation chain is 50.
The max. number of energy groups of the neutron flux density is 100. The max. number of time steps considered during an irradiation period is 400.
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6. TYPICAL RUNNING TIME

The CPU time of the example run shown in the  report HMI-B 312 (activation chain: 49 nuclides, 100 energy group neutron flux, 7 time steps during the irradiation period), is 6.5 sec. on a Siemens computer, 7800 series.
NEA-0951/01
The test case included in this package was executed at  NEA-DB on an IBM 3090 computer in 35 seconds of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM

The user of the program NUCCON has to give the values of neutron flux density at the considered interval of the torus, the physical model (activation chain), the necessary cross-section values and the biological hazard potential values for the radioactive nuclides of the considered activation chain. On the other hand, there is no predetermined activation chain or cross-section library as in some other codes, so the user is free to construct and calculate his own model.
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8. RELATED AND AUXILIARY PROGRAMS:
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9. STATUS
Package ID Status date Status
NEA-0951/01 31-MAR-1988 Tested at NEADB
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10. REFERENCES

- J. Gruber, J. Schneider,
  HMI-B 212, "Transmutation und Aktivierung von Stainless Steel 316
  SS in einem thermischen Fusionsreaaktor-Blanket",
  Hahn-Meitner-Institut fuer Kernforschung Berlin Gmbh. (in German)
- J. Gruber, J. Schneider,
  "Hazardous Impurity Activity in Blanket Materials",
  Hahn-Meitner-Institut fuer Kernforschung Berlin Gmbh, Published
  in: Proceedings of the 8th Symposium on Engineering Problems of
  Fusion Research, 1979, San Francisco - (in English).
NEA-0951/01, included references:
- J. Gruber, B. Lehmann and J. Schneider:
  A Program for Calculating the Neutron Activation.
  HMI-B 312 (September 1979).
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11. MACHINE REQUIREMENTS

A maximum of 8 different data sets are used by the program. The required amount of high speed memory is less than 1024 kByte.
NEA 0951/01: The test case included in this package ran on an IBM3090 computer in 668K bytes of main storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0951/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  The operating system is BS 3000.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The
program has also been successfully run with a FORTRAN 77 compiler.
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15. NAME AND ESTABLISHMENT OF AUTHORS

         Joachim Schneider
         Hahn-Meitner-Institut fuer Kernforschung
         Berlin Gmbh, Glienicker Strasse 100
         D- 1000 Berlin 39
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16. MATERIAL AVAILABLE
NEA-0951/01
File name File description Records
NEA0951_01.001 Information file 78
NEA0951_01.002 FORTRAN source program 943
NEA0951_01.003 DATA for program control 2
NEA0951_01.004 DATA of the calculation range and chain 108
NEA0951_01.005 DATA of the interval and the flux density 3117
NEA0951_01.006 DATA of microscopic cross section 5214
NEA0951_01.007 Sample output from FT10F001 3324
NEA0951_01.008 Sample output from FT50F001 289
NEA0951_01.009 Sample output from FT60F001 2050
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17. CATEGORIES
  • X. Magnetic Fusion Research

Keywords: activation, fusion reactors, isotope production.