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IAEA0868 FAPCO.

FAPCO, Evaluation of Flaws in Nuclear Power Plant Component Structures

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1. NAME OR DESIGNATION OF PROGRAM:  FAPCO.
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2. COMPUTERS
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Program name Package id Status Status date
FAPCO IAEA0868/01 Tested 09-NOV-1983

Machines used:

Package ID Orig. computer Test computer
IAEA0868/01 CDC CYBER 740 CDC CYBER 740
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3. DESCRIPTION OF PROBLEM OR FUNCTION

FAPCO evaluates flaws in structures, especially those detected during in-service inspection of nuclear power plant components. FAPCO determines the end-of-life  flaw size, critical flaw sizes for normal and abnormal reactor operation conditions, and finally determines whether the flaw is acceptable or not for continued service.
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4. METHOD OF SOLUTION

The evaluation procedures of FAPCO generally follow those described in Appendix A of ASME Code Section XI.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME

NEA-DB executed the two test cases included
in the package on CDC CYBER 740 in less than 5 CPU seconds.
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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
IAEA0868/01 09-NOV-1983 Tested at NEADB
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10. REFERENCES

- ASME Boiler and Pressure Vessel Code, Section XI,
"Rules for Inservice Inspection of Nuclear Power Plant Components"     1977 ed., Summer 1977 Addenda.
- "Computational Method to Perform the Flaw Evaluation Procedure
  as Specified in the ASME Code, Section XI, Appendix A"
  EPRI NP-1181, Part 1, September 1979.
- "Flaw Evaluation Procedures, Background and Application of ASME
   Section XI, Appendix A"
   EPRI NP-719-SR, August 1978.
IAEA0868/01, included references:
- Kim Yil and Sohn Gap-Heon:
  Flaw Analysis Program by Code, User's Manual.
  KAERI/TR-40/83  (December 1982)
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11. MACHINE REQUIREMENTS

Main storage requirements on CDC CYBER 740 are 44,600 octal words.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
IAEA0868/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
NOS (CDC CYBER 740).
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR

Mechanics Materials Science Division
Safety Research Department
Nuclear Safety Center
Korea Advanced Energy Research Institute
P. O. Box 7
Cheong Ryang,
Seoul, Korea
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16. MATERIAL AVAILABLE
IAEA0868/01
File name File description Records
IAEA0868_01.003 FAPCO INFORMATION FILE 42
IAEA0868_01.004 FAPCO SOURCE (FORTRAN-4) 1586
IAEA0868_01.005 FAPCO JCL CARDS 23
IAEA0868_01.006 FAPCO INPUT DATA FOR TEST CASE 1 246
IAEA0868_01.007 FAPCO INPUT DATA FOR TEST CASE 2 246
IAEA0868_01.008 FAPCO PRINTED OUTPUT OF TEST CASE 1 283
IAEA0868_01.009 FAPCO PRINTED OUTPUT OF TEST CASE 2 279
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis
  • Q. Materials.

Keywords: cracking, fracture properties, materials, mechanical properties, mechanical structures, reactor safety, ruptures.