Stress Corrosion Cracking of Spent Nuclear Fuel Dry Storage Canisters

Stress Corrosion Cracking of Spent Nuclear Fuel Dry Storage Canisters

Greg Oberson, Materials Engineer U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research

Meeting with Fuel Cycle and Materials Administration September 16-19, 2013

Outline

? Background ? NRC activities

- Regulatory approach - Research programs ? Industry activities ? Summary

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BACKGROUND

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Summary of Issue

? Most spent nuclear fuel dry storage canisters in the U.S are fabricated from austenitic stainless steel

? Canisters in vented overpacks may be exposed to airborne chloride salts or other atmospheric species

? Deliquescence of salts at high relative humidity (RH) could create corrosive brine on canister surface

? Stress corrosion cracking (SCC) could initiate at stressed locations such as welds

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Conceptual Scenario

Airflow through vents

Overpack

Canister

Salt or other airborne species

Species on surface

Deliquescent brine

Weld

Canister wall

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