@inproceedings{aeae28a9fd3149b881a51271586c6ae5,
title = "Crack growth rate testing and large plate demonstration under chloride-induced stress corrosion cracking conditions in stainless steel canisters for storage of spent nuclear fuel",
abstract = "Stress corrosion cracking may occur when chloride-bearing salts deposit and deliquesce on the external surface of stainless steel spent nuclear fuel storage canisters at weld regions with high residual stresses. Although it has not yet been observed, this phenomenon leads to a confinement concern for these canisters due to its potential for radioactive materials breaching through the containment system boundary provided by the canister wall during extended storage. The tests for crack growth rate have been conducted on bolt-load compact tension specimens in a setup designed to allow initially dried salt deposits to deliquesce and infuse to the crack front under conditions relevant to the canister storage environments (e.g., temperature and humidity). The test and characterization protocols are performed to provide bounding conditions in which cracking will occur. The results after 2- and 6-month exposure are examined in relation to previous studies in condensed brine and compared with other experimental data in the open literature. The knowledge gained from bolt-load compact tension testing is being applied to a large plate cut from a mockup commercial spent nuclear fuel canister to demonstrate the crack growth behavior induced from starter cracks machined in regions where the welding residual stress is expected. All these tests are conducted to support the technical basis for ASME Boiler and Pressure Vessel Section XI Code Case N-860.",
keywords = "Canister, Chloride-induced stress corrosion cracking (CISCC), Code Case N-860, Crack growth rate (CGR), Deliquescence, Spent nuclear fuel (SNF), Welding residual stress (WRS)",
author = "Lam, {Poh Sang} and Duncan, {Andrew J.} and Ward, {Lisa N.} and Sindelar, {Robert L.} and Kim, {Yun Jae} and Jeong, {Jae Yoon} and Lee, {Hyun Jae} and Lee, {Myeong Woo}",
note = "Funding Information: This work at the Savannah River National Laboratory was sponsored by the Spent Fuel and Waste Science and Technology (SFWST) R&D Campaign, Office of Nuclear Energy under the U.S. Department of Energy, and by the Savannah River Nuclear Solutions, LLC under Contract No. DE-AC09-08SR22470 with the U.S. Department of Energy. Funding Information: The work at Korea University was supported by the International Nuclear Energy Research Initiative (I-NERI) United States - Republic of Korea, Project 2016-001-K: Flaw Stability and Stress Corrosion Cracking of Austenitic Stainless Steel Canisters for Long Term Storage and Transportation of LWR Used Fuel. Funding Information: This work at the Savannah River National Laboratory was sponsored by the Spent Fuel and Waste Science and Technology (SFWST) R&D Campaign, Office of Nuclear Energy under the U.S. Department of Energy, and by the Savannah River Nuclear Solutions, LLC under Contract No. DE-AC09-08SR22470 with the U.S. Department of Energy. The work at Korea University was supported by the International Nuclear Energy Research Initiative (I-NERI) United States-Republic of Korea, Project 2016-001-K: Flaw Stability and Stress Corrosion Cracking of Austenitic Stainless Steel Canisters for Long Term Storage and Transportation of LWR Used Fuel. Publisher Copyright: Copyright {\textcopyright} 2019 ASME.; ASME 2019 Pressure Vessels and Piping Conference, PVP 2019 ; Conference date: 14-07-2019 Through 19-07-2019",
year = "2019",
doi = "10.1115/PVP2019-94031",
language = "English",
series = "American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP",
publisher = "American Society of Mechanical Engineers (ASME)",
booktitle = "Materials and Fabrication",
}