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NEA-1620 RODBURN.

RODBURN, Power Profiles and Isotopics in PWR, BWR Fuel Rods

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1. NAME OR DESIGNATION OF PROGRAM:  RODBURN
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2. COMPUTERS
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No item

Machines used:

No specified machine
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3. DESCRIPTION OF PROGRAM OR FUNCTION

RODBURN calculates the power generation density profile in the radial and axial directions and fast neutron flux, and concentrations of fission product isotopes and fissile materials of a single rod irradiated in PWR, BWR and Halden BWR.  RODBURN gives an output file which can be read by FEMAXI-V.
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4. METHODS

RODBURN uses ORIGEN1 library, RABBLE library and other libraries.  First, resonance integral is calculated.  Then, three group constants are selected and simplified neutronics analysis is performed along the designated power history and rod geometries.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:  None
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6. TYPICAL RUNNING TIME:  Less than 1 minute in the sample case by SUN workstation.
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7. UNUSUAL FEATURES:  None
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8. RELATED OR AUXILIARY PROGRAMS

A fuel rod analysis code FEMAXI-V (ver.1) is also released concurrently.  RODBURN can give FEMAXI-V the result file, so that FEMAXI-V can read it as one of calculation conditions to determine the power generation density and fast flux in the axial and radial directions of rod.
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9. STATUS
No status
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10. REFERENCES

   
Masaaki Uchida and Hiroaki Saito
RODBURN : A Code for Calculating Power Distribution in
Fuel Rods
JAERI-M 93-108 (1993) (in japanese)
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11. HARDWARE REQUIREMENTS:  SUN and its compatible workstations, and IBM PC/AT.
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. SOFTWARE REQUIREMENTS:  UNIX: Solaris 2.5.1, MS-DOS, Windows 95,98.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

See the installation guide document telling the hint to install and compile.
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15. NAME AND ESTABLISHMENT OF AUTHORS

     Suzuki MOTOE
     Japan Atomic Energy Research Institute
     Department of Reactor Safety Research
     Tokai Research Establishment
     Tokai-mura, Ibaraki-ken 319-1195
     JAPAN
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16. MATERIAL AVAILABLE
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17. CATEGORIES

Keywords: axial, boiling water reactor, fast neutrons, fission products, neutron cross sections, pressurized water reactor.