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NEA-1340 INVENT-STUDSVIK.

INVENT-STUDSVIK, Fission Products Abundances in U235, U238, Pu239 Samples

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1. NAME OR DESIGNATION OF PROGRAM:  INVENT-STUDSVIK.
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2. COMPUTERS
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Program name Package id Status Status date
INVENT-STUDSVIK NEA-1340/01 Tested 18-MAY-1993

Machines used:

Package ID Orig. computer Test computer
NEA-1340/01 DEC VAX 8200 DEC VAX 6000
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3. DESCRIPTION OF PROGRAM OR FUNCTION

The program calculates the abundances of all fission products in samples containing U-235, U-238, and Pu-239.
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4. METHOD OF SOLUTION

The code takes into account transfer between mass chains not only by neutron capture but also the emission of delayed neutrons, which is an important mode of decay far from stability. In recent years the code has been improved, notably by using double precision for many of the variables.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  Moderate storage space is required.
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6. TYPICAL RUNNING TIME

95 s for one case on a VAX-8200 computer (if  print-out of individual nuclides is not required).
NEA-1340/01
NEA-DB ran the test case of FPCONV+INVENT on a DEC VAX 6000-510 computer in 40 seconds of CPU time.
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7. UNUSUAL FEATURES OF THE PROGRAM

The program carries out a comprehensive error analysis. The abundance of each nuclide, and its uncertainty, is evaluated. An analysis of the origin of the error (initial amounts, yields, half-lives, delayed-neutron branching ratios, capture cross sections) is performed.
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8. RELATED AND AUXILIARY PROGRAMS

A special program - FPCONV - is used to convert the formatted data library into an unformatted file  used as input for IVENT.
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9. STATUS
Package ID Status date Status
NEA-1340/01 18-MAY-1993 Tested at NEADB
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10. REFERENCES:
NEA-1340/01, included references:
- B. Duchemin and C. Nordborg:
  Decay Heat Calculation - An International Nuclear Code Comparison
  NEACRP-319 "L", NEANDC-275 "U" (April 1990).
- G. Rudstam:
  Uncertainty of Decay Heat Calculations Originating from Errors in
  the Nuclear Data and the Yields of Individual Fission Products
  Reprint from "Journal of Radioanalytical Chemistry" Vol. 55 No. 1
  pp. 79-99 (1980).
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11. MACHINE REQUIREMENTS:  No special requirements.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1340/01 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
NEA-1340/01
VMS V5.4.2 (VAX 6000).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

Name of original program version (1979)
          Gosta Rudstam
          University of Uppsala
          The Studsvik Neutron Research Laboratory
          S-611 82 Nykoeping, Suede
The program has subsquently been considerably extended and improved.
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16. MATERIAL AVAILABLE
NEA-1340/01
File name File description Records
NEA1340_01.001 Information file 49
NEA1340_01.002 Command file to run FPCONV and INVENT 9
NEA1340_01.003 FPCONV.FOR FORTRAN source program 774
NEA1340_01.004 FPINDATA.DAT Steering parameters 3
NEA1340_01.005 FPLIBIN.DAT Formatted library 4173
NEA1340_01.006 FPUTDATA.DAT Results file from FPCONV 1000
NEA1340_01.007 INVENT.FOR FORTRAN source program 3340
NEA1340_01.008 INVCOMMON.FOR Common statements for INVENT 49
NEA1340_01.009 INVINDATA.DAT Steering parameters 9
NEA1340_01.010 INVUTDATA.DAT Results file 3045
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17. CATEGORIES
  • D. Depletion, Fuel Management, Cost Analysis, and Power Plant Economics

Keywords: fission products, plutonium 239, uranium 235, uranium 238.