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NEA-0982 FRETA-B.

FRETA-B, LWR Fuel Rod Bundle Behaviour During LOCA

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1. NAME OR DESIGNATION OF PROGRAM:  FRETA-B.
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2. COMPUTERS
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Program name Package id Status Status date
FRETA-B NEA-0982/02 Tested 05-MAY-1992

Machines used:

Package ID Orig. computer Test computer
NEA-0982/02 FACOM M-780 IBM 3090
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3. DESCRIPTION OF PROGRAM OR FUNCTION

FRETA-B analyzes the behaviour  of LWR fuel rods under accident conditions, espcially loss-of- coolant accident. The program treats thermal (radiative heat transfer) and mechanical (contact due to ballooning) interactions between multiple rods in a bundle.
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4. METHOD OF SOLUTION

The method of weighted residuals is used for heat conduction in each rod. The finite element method is used for most other models. No iterations are performed for transient calculations.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The maximum number of fuel rods is 17; the maximum number of axial segments is 9. Azimuthal nodes are fixed at 4.
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6. TYPICAL RUNNING TIME:  The sample problems runs on FACOM M-380 in 2.4 minutes.
NEA-0982/02
NEADB executed the test case included in this package in 46 seconds of CPU time.
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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-0982/02 05-MAY-1992 Tested at NEADB
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10. REFERENCES

- M. Uchida:
"Application of a Two-Dimensional Ballooning Model to Out-Pile and     In-Pile Simulation Experiments"
  Nucl. Eng. Des. 77 (1984) 37-47
- M. Uchida, J. Nakamura, and N. Otsubo:
  "FRETA-B: A Computer Code for the Analysis of Fuel Rod Bundle
  Behavior Under Accident Conditions"
  JAERI-M 9495 (1981)
NEA-0982/02, included references:
- M. Uchida and N. Otsubo:
  Models of Multi-Rod Code FRETA-B for Transient Fuel Behaviour
  Analysis (Final Version)
  JAERI 1293  (November 1984)
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11. MACHINE REQUIREMENTS:  Work disks and a plotter.
NEA-0982/02
Execution of the test case on an IBM 3090 required about 1800K bytes of main storage.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0982/02 FORTRAN-77
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
NEA-0982/02
MVS/DFP with compiler VS FORTRAN LEVEL 2.5.0 (IBM3090).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHORS

         M. Uchida
         Division of Nuclear Safety Research
         Japan Atomic Energy Research Institute
         Tokai-mura, Japan
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16. MATERIAL AVAILABLE
NEA-0982/02
File name File description Records
NEA0982_02.001 Information file 102
NEA0982_02.002 JCL example for compilation, linkage, run 129
NEA0982_02.003 FRETA-B FORTRAN source 12977
NEA0982_02.004 Sample case input data 94
NEA0982_02.005 Sample case printed output (by the author) 3532
NEA0982_02.006 Sample case printed output (by NEA/DB) 3510
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: LWR reactors, accidents, fuel rods, loss-of-coolant accident, rod bundles.