Open AccessEngineered materials characterization report for the Yucca Mountain Site Characterization Project. Volume 2, Design data
Author(s) -
R.A. Van Konynenburg,
R.D. McCright,
Ananya Roy,
David F. Jones
Publication year - 1995
Language(s) - English
Resource type - Reports
DOI - 10.2172/114021
Subject(s) - corrosion , radioactive waste , waste management , spent nuclear fuel , allowance (engineering) , plutonium , waste disposal , characterization (materials science) , high level waste , hazardous waste , environmental science , materials science , metallurgy , engineering , chemistry , mechanical engineering , nuclear chemistry , nanotechnology
This is Volume 2 of the Engineered Materials Characterization Report which presents the design data for candidate materials needed in fabricating different components for both large and medium multi-purpose canister (MPC) disposal containers, waste packages for containing uncanistered spent fuel (UCF), and defense high-level waste (HLW) glass disposal containers. The UCF waste package consists of a disposal container with a basket therein. It is assumed that the waste packages will incorporate all-metallic multibarrier disposal containers to accommodate medium and large MPCs, ULCF, and HLW glass canisters. Unless otherwise specified, the disposal container designs incorporate an outer corrosion-allowance metal barrier over an inner corrosion-resistant metal barrier. The corrosion-allowance barrier, which will be thicker than the inner corrosion-resistant barrier, is designed to undergo corrosion-induced degradation at a very low rate, thus providing the inner barrier protection from the near-field environment for a prolonged service period