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Fe-saponite growth on low-carbon and stainless steel in hydrothermal-bentonite experiments

Journal Article · · Journal of Nuclear Materials
 [1];  [1];  [2];  [3]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
  3. Tulane Univ., New Orleans, LA (United States). Dept. of Geology

Hydrothermal experiments on engineered barrier system (EBS) materials were conducted to characterize high temperature interactions between bentonite and candidate waste container steels (304SS, 316SS, low-C steel) for deep geological disposition of nuclear spent fuel. In this study, hydrothermal experiments were performed using Dickson reaction cells at temperatures and pressure of up to 300 °C and 15–16 MPa, respectively, for four to six weeks. Wyoming bentonite was saturated with a 1900 ppm K-Ca-Na-Cl solution in combination with stainless and low-C steel coupons. Authigenic Fe-saponite precipitated utilizing steel as a growth substrate with Fe being supplied by steel corrosion. Concurrent with Fe-saponite formation, sulfides precipitated from sulfide-bearing fluids, from pyrite dissolution, near the steel interface. Sulfide mineral formation is dependent on the steel substrate composition: stainless steel produced pentlandite ((Ni, Fe)9S8) and millerite (NiS), whereas low C steel generated pyrrhotite (Fe7S8). The presence of sulfides suggests highly reduced environments at the steel-clay barrier interface potentially influencing overall steel corrosion rates and (re)passivation mechanisms. Finally, results of this research show that nuclear waste steel container material may act as a substrate for mineral growth in response to corrosion during hydrothermal interactions with bentonite barriers.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Basic Energy Sciences (BES) (SC-22). Chemical Sciences, Geosciences & Biosciences Division; USDOE Office of Nuclear Energy (NE)
Grant/Contract Number:
AC05-00OR22725
OSTI ID:
1474633
Alternate ID(s):
OSTI ID: 1775995
OSTI ID: 22752337
OSTI ID: 1477468
OSTI ID: 1479985
Journal Information:
Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 511; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English

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Cited By (1)

Characteristics of Water Suction for a Korean Compacted Bentonite journal August 2019

Figures / Tables (4)