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The Battelle Integrity of Nuclear Piping (BINP) Program Final Report Summary and Implications of Results (NUREG/CR-6837, Vol. 1)

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Publication Information
Abstract

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NUREG/CR-6837, Vol. 1 (PDF - 1.37 MB)

Publication Information

Manuscript Completed: September 2003
Date Published: June 2005

Prepared by
P.Scott¹, R.Olson¹, J.Bockbrader¹, M.Wilson¹, B.Gruen¹,
R.Morbitzer¹, Y.Yang¹, C.Williams¹, F.Brust¹, L.Fredette¹,
N.Ghadiali¹

G.Wilkowski², D.Rudland², Z.Feng², R.Wolterman²

¹Battelle
505 King Avenue
Columbus, OH 43201

Subcontractor:
²Engineering Mechanics Corporation of Columbus
3518 Riverside Drive
Suite 202
Columbus, OH 43221-1735

C. Greene, NRC Project Manager

Prepared for
Division of Engineering Technology
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
NRC Job Code W6775

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Abstract

Over the past 15 to 20 years significant research has been conducted to further the understanding of the fracture behavior of piping systems in commercial nuclear power plants. While the results from these prior programs have advanced the state-of-the-art understanding, a number of key technical issues remained to be resolved.

The BINP program was developed to address what were perceived to be the most critical of these unresolved issues. The program was structured as a series of independent tasks, each focused on one of these issues.

After the research was completed, it was have as significant effect on leak-beforebreak or in-service flaw evaluation criteria as was originally thought. However, one of the areas where significant benefit can be realized for both LBB and in-service flaw evaluations is by using nonlinear stress analysis instead of elastic analysis in the flaw assessments. The additional margin gained by accounting for the energy dissipated by plastic deformation can be significant.

Another important advance was the preliminary development of the technical basis for a flaw evaluation criteria for Class 2, 3, and balance of plant piping.