Shielding and corrosion properties of the Alloy 709 as canister material for spent nuclear fuel dry casks
Author:
Publisher
Elsevier BV
Subject
Metals and Alloys,Mechanical Engineering,Ceramics and Composites,Computational Mechanics
Reference41 articles.
1. Radioactive waste management;Tsoulfanidis;Nucl Technol,1991
2. Impact of specialty glass and concrete on gamma shielding in multi-layered PWR dry casks”;Waly;Prog Nucl Energy,2017
3. Shielding properties of alloy 709 advanced austenitic stainless Steel as candidate canister Material in spent fuel dry casks;Alsmadi;Int J Phys Res,2020
4. Shielding properties of 316 stainless steel with multi-layered barriers for spent fuel drycasks”;Alsmadi;Int J Phys Res,2021
5. Evaluation of radioactive material leakage through the fuel cladding as result of diffusion processes during the long-term storage of spent nuclear fuel;Alyokhina;Journal of King Saud University — Engineering Sciences,2021
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