Wall Thinning Evaluations
Even when local wall thinning in nuclear pressure vessels, piping, valves, or other components is well below the general minimum wall thickness required by ASME Code, continued operation may be justified by ASME-approved evaluation methodologies. Structural Integrity Associates, Inc. (SI) is a leader in wall-thinning evaluations for nuclear plants, including evaluation of mechanisms and rate of thinning, as well as familiarity with applicable ASME Code criteria. In fact, the evaluation methods in ASME Code Section XI Code Cases N-480, N-513, and N-597 were based on a SI report prepared for EPRI® (N-480) or developed by the Code committees using significant SI contributions. SI uses either the simplified analytical methods found in those three ASME Code cases, or more complex finite element models that determine local stress distributions in thinned components. In situations where there is local through-wall leakage, SI conducts fracture mechanics analyses to demonstrate sufficient margin against fracture. With its unique industry expertise, SI can complete wall thinning evaluations quickly, enabling rapid run/repair/replace decisions.
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