z-logo
open-access-imgOpen Access
Engineered materials characterization report for the Yucca Mountain Site Characterization Project. Volume 2, Design data
Author(s) -
R.A. Van Konynenburg,
R.D. McCright,
Amitava Roy,
David Albert 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

The content you want is available to Zendy users.

Already have an account? Click here to sign in.
Having issues? You can contact us here
Accelerating Research

Address

John Eccles House
Robert Robinson Avenue,
Oxford Science Park, Oxford
OX4 4GP, United Kingdom