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NESC0898 OCTAVIA.

OCTAVIA, PWR Pressure Vessel Failure Probability for Routine Pressure Transients

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1. NAME OR DESIGNATION OF PROGRAM:  OCTAVIA.
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2. COMPUTERS
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Program name Package id Status Status date
OCTAVIA NESC0898/01 Tested 01-DEC-1981

Machines used:

Package ID Orig. computer Test computer
NESC0898/01 IBM 3033 IBM 3033
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3. DESCRIPTION OF PROBLEM OR FUNCTION

OCTAVIA (Operationally Caused Transients and Vessel Integrity Analysis) calculates the probability of pressure vessel failure from operationally-caused pressure transients which can occur in a pressurized water reactor (PWR). For specified vessel and operating environment characteristics the program computes the failure pressure at which the vessel will fail  for different-sized flaws existing in the beltline and the probability of vessel failure per reactor year due to the flaw. The  probabilities are summed over the various flaw sizes to obtain the total vessel failure probability. Sensitivity studies can be performed to investigate different vessel or operating characteristics in the same computer run.
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4. METHOD OF SOLUTION

The analysis approach involves calculation of vessel failure pressures using fracture mechanics methods and estimation of pressure-transient characteristics using historical nuclear data.
The pressure vessel is described by input data, such as vessel wall thickness, inside radius, copper and phosphorus content, residual stress, flaw sizes, fluence, and temperature. The failure pressure for a given flaw is calculated using linear-elastic and elastic-plastic methods. After obtaining the failure pressure for a  given flaw size, the probability evaluation is performed. The probabilities for the different flow sizes are then summed to obtain the total probability of pressure vessel failure from the various flaws which might exist in the vessel.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM

Maxima of -
   100 temperatures
    12 fluences
     8 flaw sizes
with the program's current dimensioning. Only failure oriented flaws in the vessel beltline are considered.
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6. TYPICAL RUNNING TIME

The sample problem requires approximately 7 CPU seconds for execution on an IBM370/195 or 3033.
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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
NESC0898/01 01-DEC-1981 Tested at NEADB
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10. REFERENCES

- J.G. Merkle, G.D. Whitman, and R.H. Bryan,
  An Evaluations of the HSST Program Intermediate Pressure Vessel
  Test in Terms of Light-Water-Reactor Pressure Vessel Safety,
  ORNL-TM-5090, November 1975.
NESC0898/01, included references:
- W.E. Vesely, E.K. Lynn and F.F. Goldberg:
  The OCTAVIA Computer Code: PWR Reactor Pressure Vessel Failure
  Probabilites due to Operationally Caused Pressure Transients.
  NUREG-0258 R1  (March 1978)
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11. MACHINE REQUIREMENTS

OCTAVIA requires approximately 170K bytes of  storage for execution of the sample problem on an IBM370/195 or 3033
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
NESC0898/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  OS/370.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

In
addition to use of the standard input and output units, the program  uses logical unit 10 for scratch storage. OCTAVIA graphical output is produced using proprietary CalComp plotter software. Subroutine LOGRID, which plots logarithmic-scaled grid lines, and the dummy MESSAG subroutine were supplied by NESC for completeness.
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15. NAME AND ESTABLISHMENT OF AUTHOR

             W.E. Vesely, E.K. Lynn, and F.F. Goldberg*
             Office of Nuclear Regulatory Research
             U.S. Nuclear Regulatory Commission
             Washingron, D.C. 20555
* Contact
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16. MATERIAL AVAILABLE
NESC0898/01
File name File description Records
NESC0898_01.001 INFORMATION 33
NESC0898_01.002 JOB CONTROL 62
NESC0898_01.003 OCTAVIA FORTRAN SOURCE 1247
NESC0898_01.004 DUMMY PLOTTING ROUTINES 24
NESC0898_01.005 SAMPLE PROBLEM INPUT 21
NESC0898_01.006 SAMPLE PROBLEM OUTPUT 661
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis

Keywords: failures, pressure vessels, probability, pwr reactors, reactor safety, reliability, transients.