Container materials in environments of corroded spent nuclear fuel
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference19 articles.
1. Technology Status in Support of Refined Technical Baseline for the Spent Nuclear Fuel Project;Puigh,1995
2. Studies of the kinetics and mechanism of the oxidation of uranium by dry and moist air A model for determining the oxidation rate over a wide range of temperatures and water vapour pressures
3. The ignition of uranium
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1. Shielding and corrosion properties of the Alloy 709 as canister material for spent nuclear fuel dry casks;Defence Technology;2023-03
2. Corrosion behaviour of 304L stainless steel and 5754 aluminium alloy for intermediate-level radioactive waste containers;Materials and Corrosion;2016-01-25
3. Corrosion resistance of boron-bearing aluminum alloys and its increase after plasma electrolytic oxidation;Protection of Metals and Physical Chemistry of Surfaces;2014-11-05
4. Spent fuel transport cask thermal evaluation under normal and accident conditions;Nuclear Engineering and Design;2010-06
5. Nuclear Materials and Irradiation Effects;Handbook of Nuclear Engineering;2010
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