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Corrosion interactions between stainless steel and lead vanado-iodoapatite nuclear waste form part I

Journal Article · · npj Materials Degradation
 [1];  [2];  [3];  [4];  [2];  [4]
  1. The Ohio State Univ., Columbus, OH (United States). Dept. of Materials Science and Engineering; The Ohio State University
  2. Rensselaer Polytechnic Inst., Troy, NY (United States). Dept. of Mechanical Aerospace and Nuclear Engineering
  3. Rensselaer Polytechnic Inst., Troy, NY (United States). Dept. of Mechanical Aerospace and Nuclear Engineering; Idaho National Lab. (INL), Idaho Falls, ID (United States). Materials and Fuel Complex
  4. The Ohio State Univ., Columbus, OH (United States). Dept. of Materials Science and Engineering
This study explores the corrosion interactions between a metallic canister material, stainless steel (SS) 316, and an I-bearing ceramic waste form, lead vanado-iodoapatite (I-APT, Pb9.85(VO4)6I1.7), in a chloride solution. Crevice corrosion of the SS in close proximity to the I-APT resulted in the development of an aggressive environment at the interface of the two materials, which was acidic and enriched in Cl anions. I-APT also corroded in the crevice region, primarily through ion-exchange between the I ions from the I-APT matrix and anions from the environment. The enrichment of Cl anions within the occluded crevice space as the result of SS crevice corrosion enhanced the corrosion of I-APT. The release of iodine from this apatite waste form could be accelerated owing to this mechanism. This is evidenced by a depletion of iodine from the I-APT matrix and a large amount of Cl-bearing precipitates on the surfaces of both SS and I-APT. On the other hand, the corrosion of I-APT leads to the precipitation of a V- and Pb-rich layer, which inhibits the localized corrosion of SS to an extent. This study advances the understanding of the near-field corrosion interactions between metallic canisters and ceramic waste forms.
Research Organization:
Energy Frontier Research Centers (EFRC) (United States). Center for Performance and Design of Nuclear Waste Forms and Containers (WastePD); The Ohio State Univ., Columbus, OH (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Basic Energy Sciences (BES)
Grant/Contract Number:
SC0016584
OSTI ID:
1666383
Journal Information:
npj Materials Degradation, Journal Name: npj Materials Degradation Journal Issue: 1 Vol. 4; ISSN 2397-2106
Publisher:
SpringerCopyright Statement
Country of Publication:
United States
Language:
English

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