A stress corrosion cracking (SCC) model has been adapted for performance prediction of high level radioactive-waste packages to be emplaced in the proposed Yucca Mountain repository. For waste packages of the proposed Yucca Mountain repository, the outer barrier material is the highly corrosion-resistant Alloy UNS-N06022 (Alloy 22), the environment is represented by aqueous brine films present on the surface of the waste package from dripping or deliquescence of soluble salts present in any surface deposits, and the tensile stress is principally from weld induced residual stress. SCC has historically been separated into ''initiation'' and ''propagation'' phases. Initiation of SCC will not occur on a smooth surface if the surface stress is b...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
Susceptibility to stress corrosion cracking (SCC) of candidate materials for the inner container of ...
Containment of spent nuclear fuel and vitrified forms of high level nuclear waste require use of mat...
Stress corrosion cracking is one of the most common corrosion-related causes for premature breach of...
Six alloys have been selected as candidate container materials for the storage of high-level nuclear...
One of the potential failure modes of the drip shield (DS), the waste package (WP) outer barrier, an...
The present plan for disposal of high-level radioactive waste in the US is to seal it in containers ...
This paper provides an update on research addressing the effects of material condition and applied s...
The US Department of Energy is characterizing a potential repository site for nuclear waste in Yucca...
The objective of this research is to determine the effects of material condition and applied stress ...
The waste package design for the License Application is a double-wall waste package underneath a pro...
Cortest Columbus Technologies, Inc. (CC Technologies) investigated the long-term performance of cont...
There exists a paramount need for improved understanding the behavior of high-level nuclear waste co...
Laboratory tests were conducted to investigate the stress corrosion cracking (SCC) of 304L stainless...
Preliminary results are presented from the long-term corrosion test program of candidate materials f...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
Susceptibility to stress corrosion cracking (SCC) of candidate materials for the inner container of ...
Containment of spent nuclear fuel and vitrified forms of high level nuclear waste require use of mat...
Stress corrosion cracking is one of the most common corrosion-related causes for premature breach of...
Six alloys have been selected as candidate container materials for the storage of high-level nuclear...
One of the potential failure modes of the drip shield (DS), the waste package (WP) outer barrier, an...
The present plan for disposal of high-level radioactive waste in the US is to seal it in containers ...
This paper provides an update on research addressing the effects of material condition and applied s...
The US Department of Energy is characterizing a potential repository site for nuclear waste in Yucca...
The objective of this research is to determine the effects of material condition and applied stress ...
The waste package design for the License Application is a double-wall waste package underneath a pro...
Cortest Columbus Technologies, Inc. (CC Technologies) investigated the long-term performance of cont...
There exists a paramount need for improved understanding the behavior of high-level nuclear waste co...
Laboratory tests were conducted to investigate the stress corrosion cracking (SCC) of 304L stainless...
Preliminary results are presented from the long-term corrosion test program of candidate materials f...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
Susceptibility to stress corrosion cracking (SCC) of candidate materials for the inner container of ...
Containment of spent nuclear fuel and vitrified forms of high level nuclear waste require use of mat...