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NEA-1679 PVIS-4

PVIS-4, Pressure vessel irradiation, source preparation

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1. NAME OR DESIGNATION OF PROGRAM:  PVIS-4 (Pressure Vessel Irradiation Source).
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2. COMPUTERS
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Program name Package id Status Status date
PVIS-4 NEA-1679/01 Tested 20-JUN-2003

Machines used:

Package ID Orig. computer Test computer
NEA-1679/01 HP 9000,DEC ALPHA W.S. DEC ALPHA W.S.
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3. DESCRIPTION OF PROGRAM OR FUNCTION

The program prepares a fixed neutron source distribution in radial, (r,theta), (r,z) or (r,theta,z) geometry for ANISN, DORT or TORT. The user can input the source distribution in some relatively compact form (typically a few variables defining the spectrum, 10 values for the axial source distribution and, for the horizontal distribution, the values at the center and corners of each of the outermost fuel bundles and the average value for each interior bundle). The program then creates the required source arrays, such as 96*, 97* and 98* arrays for DORT.
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4. METHODS

Each required operation is performed by a separate module (a set of subprograms).
HORIHX or HORISQ takes a source distribution in the transverse plane, given at the center and corners of each fuel bundle in hexagonal or square geometry, and transforms it into (r,theta) or radial geometry. In the latter case, the output distribution may be averaged in the azimuthal direction or azimuthal maxima may be obtained.

FOUR takes an axial distribution, specified as a histogram, and approximates this with a Fourier series. This is then used to obtain a histogram distribution for a different axial mesh.

SQPIN takes a 3-D pinwise distribution in square geometry and transforms it into a radial, (r,theta), (r,z) or (r,theta,z) distribution.

FISPEC calculates a groupwise energy spectrum from any of several different functional forms. Several components with different forms may be combined into one spectrum.

COMBI combines the space and energy distributions prepared by the other modules and presents the result in a format appropriate for the SN programs in the DOORS system.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

At present a reactor core of hexagonal fuel bundles must have 30- or 60-degree symmetry, a core of square bundles must have 45- or 90-degree symmetry (except if the sqpin option is used). Other core geometries are not supported for the input distribution.
Only cylindrical geometry is supported for the output source distribution.
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6. TYPICAL RUNNING TIME:  A few seconds.
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7. UNUSUAL FEATURES

The modularity of the program makes it relatively easy to add new input or output formats or capabilities.
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8. RELATED OR AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
NEA-1679/01 20-JUN-2003 Tested at NEADB
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10. REFERENCES
NEA-1679/01, included references:
- Frej Wasastjerna:
PVIS-4 - A Program Intended to Prepare a Fixed Fission Source
for Pressure Vessel Irradiation Calculations with ANISN, DORT or TORT in
Hexagonal or Square Geometry. VTT Energy Technical Report RFD-2/99 (1999)
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11. HARDWARE REQUIREMENTS:  Developed on an HP 9000/780 but highly portable.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-1679/01 FORTRAN-77
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13. SOFTWARE REQUIREMENTS:  Unix.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

Frej Wasastjerna
VTT Processes
P.O. Box 1608
FIN-02044 VTT
FINLAND

e-mail: frej.wasastjerna@vtt.fi
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16. MATERIAL AVAILABLE
NEA-1679/01
PVIS4v2.doc Technical report
Source programs
Test problems, input data
Test problems, output data
Scripts to run test problems
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17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • L. Data Preparation

Keywords: irradiation, pressure vessels, source, three-dimensional, two-dimensional.