NEA-0912 ABLEIT-TRANS.

ABLEIT-TRANS, Isotope Concentration and Sensitivities on Cross-Sections Data

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES

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1. NAME OR DESIGNATION OF PROGRAM: ABLEIT-TRANS.

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2. COMPUTERS

To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.

Program name	Package id	Status	Status date
ABLEIT-TRANS	NEA-0912/01	Tested	09-APR-1987

Machines used:

Package ID	Orig. computer	Test computer
NEA-0912/01	CDC CYBER 175	CDC CYBER 740

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3. DESCRIPTION OF PROBLEM OR FUNCTION: Error propagation analysis for burnup calculation.

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4. METHOD OF SOLUTION

The probability density functions of the nuclide concentrations are characterized by their first four moments. These moments are calculated from the density functions of the statistically independent random data (nuclear cross sections and decay constants). The calculation uses Taylor series expansion for the nuclide concentrations up to a user-specified order n, constructed from generalized burnup equations. The derivatives are also used for the computation of sensitivity coefficients.

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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Only statistically independent random data are allowed. The maximum number of random data allowed is 28. The number of differential equations is limited to 580 (depending on available core storage).

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6. TYPICAL RUNNING TIME

The test problem (22 random data, maximum order of Taylor series n = 2) requires about 4 CP seconds for ABLEIT (calculation of derivatives) and about 20 CP seconds for TRANS (calculation of moments) on the CDC CYBER 175 (with FORTRAN FTN 5.1 compiler, OPT=2).

NEA-0912/01

NEA executed the test cases included in this package on a CDC CYBER 740 computer. Maximum CPU times required were 15.5 seconds (ABLEIT); 0.12 seconds (TRANS).

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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
NEA-0912/01	09-APR-1987	Tested at NEADB

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10. REFERENCES

- R.W. Zerressen:
  "Accuracy Considerations for Nuclear Data used in the Calculation
   of Actinides Decay during Irradiation"
  RWTH Aachen, Thesis, 1981 (in German).

NEA-0912/01, included references:

- K.W. Zerressen and H.D. Beims:
"ABLEIT-TRANS, Code Description". RWTH Aachen 1983

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11. MACHINE REQUIREMENTS:
About 150,000 octal words of main storage are required.

NEA-0912/01

To run the test cases of this package on a CDC CYBER-740 computer, main storage requirements are: 150,100 (octal) words (CM) for ABLEIT, and 65,200 (octal) words (CM) for TRANS.

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12. PROGRAMMING LANGUAGE(S) USED

Package ID	Computer language
NEA-0912/01	FORTRAN-IV

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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED: NOS 1.4

NEA-0912/01

NOS2.5.1 664/640 (CDC CYBER 740).

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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

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15. NAME AND ESTABLISHMENT OF AUTHOR

  R.W. Zerressen (*) and H.D. Beims
  Lehrauftrag Leistungsreaktoren
  RWTH Aachen
  Schinkelstr. 6
  D-5100 Aachen, Federal Republic of Germany

(*) present adress:
  KWU Offenbach

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16. MATERIAL AVAILABLE

NEA-0912/01

File name	File description	Records
NEA0912_01.001	Information file	46
NEA0912_01.002	JCL control information	19
NEA0912_01.003	ABLEIT source program	1789
NEA0912_01.004	TRANS source program	330
NEA0912_01.005	ABLEIT S.P. input TAPE7	108
NEA0912_01.006	ABLEIT S.P. input TAPE5	34
NEA0912_01.007	TRANS S.P. input TAPE5	5
NEA0912_01.008	ABLEIT S.P. OUTPUT	560
NEA0912_01.009	TRANS S.P. OUTPUT	424

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17. CATEGORIES

D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics
P. General Mathematical and Computing System Routines

Keywords: actinides, burnup, cross sections, errors, isotope production, sensitivity analysis.