One of the potential failure modes of the drip shield (DS), the waste package (WP) outer barrier, and the stainless structural material is the initiation and propagation of stress corrosion cracking (SCC) induced by the WP environment and various types of stresses that can develop in the DSs or the WPs. For the current design of the DS and WP, however, the DS will be excluded from the SCC evaluation because stresses that are relevant to SCC are insignificant in the DS. The major sources of stresses in the DS are loadings due to backfill and earthquakes. These stresses will not induce SCC because the stress caused by backfill is generally compressive stress and the stress caused by earthquakes is temporary in nature. The 316NG stainless stee...
Cracking of fuel claddings is a serious concern when selecting candidate alloys for the development ...
Six alloys have been selected as candidate container materials for the storage of high-level nuclear...
The US Department of Energy is characterizing a potential repository site for nuclear waste in Yucca...
Stress corrosion cracking is one of the most common corrosion-related causes for premature breach of...
The waste package design for the License Application is a double-wall waste package underneath a pro...
A stress corrosion cracking (SCC) model has been adapted for performance prediction of high level ra...
The repository design includes a drip shield (BSC 2004 [DIRS 168489]) that provides protection for t...
This paper provides an update on research addressing the effects of material condition and applied s...
The current design of waste package containers include outer barrier using corrosion allowable mater...
Laboratory tests were conducted to investigate the stress corrosion cracking (SCC) of 304L stainless...
This analyses and models report (AMR) was conducted in response to written work direction (CRWMS M a...
As described in the License Application Design Selection Report, the recommended waste, package desi...
As directed by ''Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste ...
The objective of this research is to determine the effects of material condition and applied stress ...
Susceptibility to stress corrosion cracking (SCC) of candidate materials for the inner container of ...
Cracking of fuel claddings is a serious concern when selecting candidate alloys for the development ...
Six alloys have been selected as candidate container materials for the storage of high-level nuclear...
The US Department of Energy is characterizing a potential repository site for nuclear waste in Yucca...
Stress corrosion cracking is one of the most common corrosion-related causes for premature breach of...
The waste package design for the License Application is a double-wall waste package underneath a pro...
A stress corrosion cracking (SCC) model has been adapted for performance prediction of high level ra...
The repository design includes a drip shield (BSC 2004 [DIRS 168489]) that provides protection for t...
This paper provides an update on research addressing the effects of material condition and applied s...
The current design of waste package containers include outer barrier using corrosion allowable mater...
Laboratory tests were conducted to investigate the stress corrosion cracking (SCC) of 304L stainless...
This analyses and models report (AMR) was conducted in response to written work direction (CRWMS M a...
As described in the License Application Design Selection Report, the recommended waste, package desi...
As directed by ''Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste ...
The objective of this research is to determine the effects of material condition and applied stress ...
Susceptibility to stress corrosion cracking (SCC) of candidate materials for the inner container of ...
Cracking of fuel claddings is a serious concern when selecting candidate alloys for the development ...
Six alloys have been selected as candidate container materials for the storage of high-level nuclear...
The US Department of Energy is characterizing a potential repository site for nuclear waste in Yucca...