RSICC CODE PACKAGE PSR-391

1. NAME AND TITLE

PC-PRAISE: Piping Reliability Analysis Including Seismic Events.

Previous Versions Available:

PRAISE - C; CDC7600 (P00391/C7600/00)

2. CONTRIBUTORS

Argonne National Laboratory, Argonne, Illinois, Failure Analysis Associates, Inc., Menlo Park, California, Lawrence Livermore National Laboratory, Livermore, California through the Energy Science and Technology Software Center, Oak Ridge, Tennessee.

3. CODING LANGUAGE AND COMPUTER

FORTRAN (90%) BASIC (10%); IBM PC (P00391/IBMPC/00)

4. NATURE OF PROBLEM SOLVED

PC-PRAISE is a probabilistic fracture mechanics computer code developed for IBM or IBM compatible personal computers to estimate probabilities of leaks and breaks in nuclear power plant cooling piping. It iwas adapted from LLNL's PRAISE computer code.

5. METHOD OF SOLUTION

PC-PRAISE considers the initiation and/or growth of crack-like defects in piping weldments. The initiation analyses are based on the results of laboratory studies and field observations in austenitic piping material operating under boiling water reactor conditions. The considerable scatter in such results is quantified and incorporated into a probabilistic model. The crack growth analysis is based on (deterministic) fracture mechanics principles, in which some of the inputs (such as initial crack size) are considered to be random variables. Monte Carlo simulation, with stratified sampling on initial crack size, is used to generate weldment reliability results.

6. RESTRICTIONS OR LIMITATIONS

There is essentially no limitation with PC-PRAISE but for large numbers of replications used in the Monte Carlo simulation scheme, computation time may become prohibitive.

7. TYPICAL RUNNING TIME

Sample Problem 1 ran in 4.5 minutes on a Pentium II 266 Mhz running Windows 95 platform.

8. COMPUTER HARDWARE REQUIREMENTS

PC-PRAISE can be executed on any XT, 386, 486, or later personal computers. For reasonable running time, it is recommended that a 386/33 PC with a 387/33 math coprocessor at the minimum is to be used in order to gain reasonable running time.

9. COMPUTER SOFTWARE REQUIREMENTS

DOS 5.0 or higher.

10. REFERENCES

a) Included in package:

D.O. Harris, D.D. Dedhia, and S.C. Lu, "Theoretical and User's Manual for PC-PRAISE," NUREG/CR-5864 (July 1992).

b) Background references for PRAISE-C:

G.S. Holman and C.K. Chou, "Probability of Failure in BWR Reactor Coolant Piping Volume 1: Summary Report," NUREG/CR-4792 (UCID-20914) Vol. 1 (March 1989).

T. Lo, S.E. Bumpus, D.J. Chinn, R.W. Mensing, and G.S. Holman, "Probability of Failure in BWR Reactor Coolant Piping Volume 2: Pipe Failure Induced by Crack Growth and Failure of Intermediate Supports," NUREG/CR-4792 (UCID-20914) Vol. 2 (March 1989).

D.O. Harris, D.D. Dedhia, E.D. Eason, and S.D. Patterson, "Probability of Failure in BWR Reactor Coolant Piping, Volume 3: Probabilistic Treatment of Stress Corrosion Cracking in 304 and 316NG BWR Piping Weldments," NUREG/CR-4792 (UCID-20914) Vol. 3 (December 1986).

D.O. Harris, E.Y. Lim, D.D. Dedhia, H.H. Woo, and C.K. Chou, "Fracture Mechanics Models Developed for Piping Reliability Assessment in Light Water Reactors Piping Reliability Project," NUREG/CR-2301 (UCID-15490) (June 1982).

N. Storch, J. Chin, and K. Booth, "TV80LIB Graphics Library, LCSD 436 Rev. 0, February 3, 1981; E.Y. Lim, Probability of Pipe Fracture in a Primary Coolant Loop of a PWR Plant, Volume 9: PRAISE Computer Code User's Manual, Load Combination Program Project I Final Report," NUREG/CR-2189 (UCID-18967) (August 1981).

T. Lo and R.W. Mensing, Probability of Pipe Failure in the Reactor Coolant Loops of Combustion Engineering PWR Plants, Vol. 2: Pipe Failure Induced by Crack Growth, NUREG/CR-3663 (UCRL-53500) (September 1984).

11. CONTENTS OF CODE PACKAGE

Included are the reference document in (10.a) and one diskette which includes source, executable, sample problem input and output written as a self-extracting compressed DOS file.

12. DATE OF ABSTRACT

April 1999.

KEYWORDS: PIPE FRACTURE; LOCA