Erratum: “A Review of Corrosion of Titanium Grade 7 and Other Titanium Alloys in Nuclear Waste Repository Environments” (Vol. 61, No. 10, p. 987–1,003)

ABSTRACTA Titanium Grade 7 (Ti-7) drip shield is being considered for use in the potential nuclear waste repository at Yucca Mountain, Nevada. The purpose of the drip shield is to keep water from reaching the surfaces of the canisters containing nuclear waste. Among the species that may be expected to be present in the water are heavy metals. This paper explores the effects of five species, lead, mercury, cadmium, tin and sodium, on the dissolution rate of Ti-7. The results of these tests indicated that lead, mercury, cadmium and tin ions do not significantly accelerate the general corrosion of Ti-7 under the conditions studied. A highly concentrated solution of NaOH was found to cause significant dissolution of Ti-7. Such a solution is a reasonable approximation of possible service environments.

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AN EVALUATION OF HYDROGEN INDUCED CRACKING SUSCEPTIBILITY OF TITANIUM ALLOYS IN US HIGH-LEVEL NUCLEAR WASTE REPOSITORY ENVIRONMENTS

10.2172/884896 ◽

2006 ◽

Author(s):

G. De ◽

K. Mon ◽

G. Gordon ◽

D. Shoesmith ◽

F. Hua

Keyword(s):

Titanium Alloys ◽

Nuclear Waste ◽

Nuclear Waste Repository ◽

Hydrogen Induced Cracking ◽

High Level Nuclear Waste ◽

Waste Repository ◽

High Level

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MULTIPHASE FLOW, HYDROMECHANICS AND UNDERPRESSURED GROUNDWATER AT THE SITE OF A PROPOSED DEEP GEOLOGIC NUCLEAR WASTE REPOSITORY IN CANADA

10.1130/abs/2020am-350361 ◽

2020 ◽

Author(s):

Michael Plampin ◽

Keyword(s):

Multiphase Flow ◽

Nuclear Waste ◽

Nuclear Waste Repository ◽

Waste Repository

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Chemical, Physical and Engineering Characterization Of Candidate Backfill Clays and Clay Admixtures for a Nuclear Waste Respository-Part I

MRS Proceedings ◽

10.1557/proc-6-413 ◽

1981 ◽

Vol 6 ◽

Author(s):

Sudesh K. Singh

Keyword(s):

Nuclear Waste ◽

Morphological Changes ◽

Deionized Water ◽

Engineering Properties ◽

Nuclear Waste Repository ◽

Exchange Cation ◽

Mineral Components ◽

Waste Repository ◽

Mineralogical Compositions

ABSTRACTFourteen Canadian clays and clay admixtures were subjected to simulated nuclear waste repository environments. The present work is concerned with the montmorillonite-dominant materials only. The montmorillonite-dominant samples showed significant leaching on interaction with deionized water. On heating the samples at 200°C for 500 hours, montmorillomites lost intermicellar water completely and acquired cusp-like to cylindrical morphologies. The loss of water and the morphological changes in montmorillonites significantly altered the engineering characteristics. Permeability, shrinkage limits, compactability and shear strength varied in response to the dominant exchange cation in the structure of montmorillonites and the presence of other mineral components in the materials. The synthetic granite water reacted with montmorillonites and led to changes in chemical and mineralogical compositions, crystalline state and engineering properties.

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