Selection of candidate container materials for the conceptual waste package design for a potential high level nuclear waste repository at Yucca Mountain | Zendy

R.A. Van Konynenburg | Zendy; William Halsey | Zendy; R.D. McCright | Zendy; W.L. Clarke | Zendy; G.E. Gdowski | Zendy

Open Access

Selection of candidate container materials for the conceptual waste package design for a potential high level nuclear waste repository at Yucca Mountain

Author(s) -

R.A. Van Konynenburg,

William Halsey,

R.D. McCright,

W.L. Clarke,

G.E. Gdowski

Publication year - 1993

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/138910

Subject(s) - conceptual design , radioactive waste , container (type theory) , material selection , high level waste , site selection , plan (archaeology) , selection (genetic algorithm) , waste management , engineering , computer science , materials science , geology , mechanical engineering , paleontology , artificial intelligence , political science , law , composite material

Preliminary selection criteria have been developed, peer-reviewed, and applied to a field of 41 candidate materials to choose three alloys for further consideration during the advanced conceptual design phase of waste package development for a potential high level nuclear waste repository at Yucca Mountain, Nevada. These three alloys are titanium grade 12, Alloy C-4, and Alloy 825. These selections are specific to the particular conceptual design outlined in the Site Characterization Plan. Other design concepts that may be considered in the advanced conceptual design phase may favor other materials choices

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