last modified: 19-MAY-1983 | catalog | categories | new | search |

NEA-0904 PRECIP-2.

PRECIP-2, Zircaloy Cladding Oxidation Simulation for LWR under LOCA Conditions

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1. NAME OR DESIGNATION OF PROGRAM:  PRECIP-2.
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2. COMPUTERS
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Program name Package id Status Status date
PRECIP-2 NEA-0904/01 Tested 19-MAY-1983

Machines used:

Package ID Orig. computer Test computer
NEA-0904/01 IBM 370/168 IBM 370/168
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3. DESCRIPTION OF PROBLEM OR FUNCTION

PRECIP-2 simulates zircaloy cladding oxidation under LOCA conditions of LWR's. The code calculates oxygen concentration distribution across the cladding wall by solving the diffusion equation with moving boundary conditions, taking into account the structure change of the beta- phase, i.e. alpha precipitation during the cooling period. The code  also predicts total oxygen uptake, thicknesses of alpha, beta and oxide layers.
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4. METHOD OF SOLUTION

The finite difference method is used to solve both diffusion equations and the heat transfer equation with moving  boundary conditions.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

The maximum number of radial nodes in the cladding is 1000. The calculation is done in cylindrical coordinates.
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6. TYPICAL RUNNING TIME:  The sample case runs in 42 seconds on the FACOM M-200.
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7. UNUSUAL FEATURES: UNUSUAL FEATURES OF THE PROGRAM
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8. RELATED OR AUXILIARY PROGRAMS: RELATED AND AUXILIARY PROGRAMS
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9. STATUS
Package ID Status date Status
NEA-0904/01 19-MAY-1983 Tested at NEADB
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10. REFERENCES

- S. Malang:
  "SIMTRAN I - A Computer Code for the Simultaneous Calculation of
   Temperature Profiles in Zircaloy During Exposure to High
   Temperature Oxidizing Environments"
   ORNL-5083, November l975
NEA-0904/01, included references:
- M. Suzuki, S. Kawasaki and T. Furuta:
  Computer Code PRECIP-2 for the Calculation of Zr-Steam Reaction
  Comparison of Calculation and Experiment.  JAERI-M 7720 (May 1978)
- M. Suzuki and S. Kawasaki:
  Development of Computer Code PRECIP-2 for Calculation of Zr-Steam
  Reaction - Comparison of Calculation with Experiments in
  Temperature Transient.  Reprint from 'Journal of NUCLEAR SCIENCE
  and TECHNOLOGY' Vol. 17, No. 4, pp. 291-300, April 1980
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11. HARDWARE REQUIREMENTS: MACHINE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NEA-0904/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  FACOM M-200, OS-4,F4.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHOR

M. Suzuki, S. Kawasaki and T. Furuta
Division of Nuclear Safety Research
Tokai Research Establishment
Japan Atomic Energy Research Institute
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16. MATERIAL AVAILABLE
NEA-0904/01
File name File description Records
NEA0904_01.003 PRECIP-2 INFORMATION FILE 91
NEA0904_01.004 PRECIP-2 SOURCE (FORTRAN-4) 4046
NEA0904_01.005 INFILQ SUBROUTINE (ASSEMBLER) 98
NEA0904_01.006 PRECIP-2 JCL 19
NEA0904_01.007 PRECIP-2 INPUT DATA FOR TEST CASE 26
NEA0904_01.008 PRECIP-2 OUTPUT OF TEST CASE 652
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis
  • Q. Materials.

Keywords: LWR reactors, cladding, diffusion, loss-of-coolant accident, simulation, zircaloy.