RSICC CODE PACKAGE PSR-583
1. NAME AND TITLE
SQUIRT VER2: Code System to Predict Leakage Rate and Area of Crack Opening for Cracked Pipes in Nuclear Power Plants.
Nuclear Regulatory Commission.
3. CODING LANGUAGE AND COMPUTER
Microsoft Quick Basic and Visual Basic 6.0; Pentium (P00583PCX8600).
4. NATURE OF PROBLEM SOLVED
The SQUIRT (Seepage Quantification of Upsets In Reactor Tubes) software is predicts leakage rate and area of crack opening for cracked pipes in nuclear power plants. In all cases, the fluid in the piping system is assumed to be water at a given temperature and pressure. The development of the SQUIRT computer model enables licensing authorities and industry users to conduct leak‑rate evaluations for leak‑before‑break applications in a more efficient manner.
5. METHOD OF SOLUTION
The fracture mechanics analysis performed by SQUIRT is based on a modified version of the NRCPIPE computer program (Brust, 1987). The SQUIRT program uses a modified from of the Henry‑Fauske model for the thermal‑hydraulics analysis together with Elastic‑Plastic Fracture Mechanics using GE/EPRI and LBB.ENG2 methods for crack opening analysis.
6. RESTRICTIONS OR LIMITATIONS
The current version of SQUIRT does not have a transitional two-phase flow model to handle pipe cracks with depth (pipe wall thickness) to hydraulic-diameter ratios between 0.5 and 15. It can only predict leakage flow rates in very tight cracks (crack depth to hydraulic-diameter ratios greater than 15) or in orifice-type cracks (crack depth to hydraulic-diameter ratios less than 0.5).
7. TYPICAL RUNNING TIME
Run time requirements depend highly on the speed of PC but most runs require less than 2 minutes.
8. COMPUTER HARDWARE REQUIREMENTS
SQUIRT runs on Pentium computers.
9. COMPUTER SOFTWARE REQUIREMENTS
SQUIRT VER2 runs on Windows-based Pentium computers. Executables created with Microsoft Quick Basic and Visual Basic 6.0 are included in the package.
a) included documentation:
“SQUIRT: Seepage Quantification of Upsets In Reactor Tubes, User’s Manual, Windows Version 1.1,” Battelle Informal Report (March 24, 2003).
S. Rahman, N. Ghadiali, D. Paul, and G. Wilkowski, “Probabilistic Pipe Fracture Evaluations for Leak-Rate-Detection Applications,” NUREG/CR-6004 (April 1995).
b) background references:
S. Rahman and others, “Refinement and Evaluations of Crack-Opening-Area Analysis for Circumferential Through-Wall Cracks in Pipes,” NUREG/CR-6300 (April 1995).
D. D. Paul and others, “Evaluation and Refinement of Leak-Rate Estimation Models,” NUREG/CR-5128, Rev. 1 (June 1994).
11. CONTENTS OF CODE PACKAGE
Included in the package are the referenced documents in 10.a, executables, data files and test cases. Source files are not included.
12. DATE OF ABSTRACT
KEYWORDS: PIPE FRACTURE; THERMAL HYDRAULICS; PIPING