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

Poh Sang Lam, Andrew J. Duncan, Lisa N. Ward, Robert L. Sindelar, Yun Jae Kim, Jae Yoon Jeong, Hyun Jae Lee, Myeong Woo Lee

Research output: Chapter in Book/Report/Conference proceedingConference contribution

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.

Original languageEnglish
Title of host publicationMaterials and Fabrication
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Electronic)9780791858981
DOIs
Publication statusPublished - 2019 Jan 1
Externally publishedYes
EventASME 2019 Pressure Vessels and Piping Conference, PVP 2019 - San Antonio, United States
Duration: 2019 Jul 142019 Jul 19

Publication series

NameAmerican Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
Volume6B-2019
ISSN (Print)0277-027X

Conference

ConferenceASME 2019 Pressure Vessels and Piping Conference, PVP 2019
CountryUnited States
CitySan Antonio
Period19/7/1419/7/19

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Keywords

  • Canister
  • Chlorideinduced stress corrosion cracking (CISCC)
  • Code Case N-860
  • Crack growth rate (CGR)
  • Deliquescence
  • Spent nuclear fuel (SNF)
  • Welding residual stress (WRS)

ASJC Scopus subject areas

  • Mechanical Engineering

Cite this

Lam, P. S., Duncan, A. J., Ward, L. N., Sindelar, R. L., Kim, Y. J., Jeong, J. Y., Lee, H. J., & Lee, M. W. (2019). 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. In Materials and Fabrication (American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP; Vol. 6B-2019). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/PVP2019-94031