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IAEA0868 FAPCO.

FAPCO, Evaluation of Flaws in Nuclear Power Plant Component Structures

NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROBLEM OR FUNCTION, METHOD OF SOLUTION, RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM, TYPICAL RUNNING TIME, UNUSUAL FEATURES OF THE PROGRAM, RELATED AND AUXILIARY PROGRAMS, STATUS, REFERENCES, MACHINE REQUIREMENTS, LANGUAGE, OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHOR, MATERIAL, CATEGORIES
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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.