1983
DOI: 10.1179/cmq.1983.22.1.125
|View full text |Cite
|
Sign up to set email alerts
|

The Corrosion Behaviour of Copper Under Simulated Nuclear Waste Repository Conditions

Help me understand this report

Search citation statements

Order By: Relevance

Paper Sections

Select...
5

Citation Types

0
24
0

Year Published

2014
2014
2023
2023

Publication Types

Select...
6

Relationship

0
6

Authors

Journals

citations
Cited by 9 publications
(24 citation statements)
references
References 5 publications
0
24
0
Order By: Relevance
“…Under these conditions, corrosion will lead to the formation of oxide layers on the Cu surface. [ 12,13 ] Presently available information indicates that the maximum depth of container corrosion due to O 2 consumption will be limited to 298 µm, as calculated using mass balance, conservatively assuming the corrosion product to be Cu 2 O only. Additionally, oxidants produced by H 2 O radiolysis could result in a further 10–30 µm penetration of the Cu coating.…”
Section: Introductionmentioning
confidence: 99%
“…Under these conditions, corrosion will lead to the formation of oxide layers on the Cu surface. [ 12,13 ] Presently available information indicates that the maximum depth of container corrosion due to O 2 consumption will be limited to 298 µm, as calculated using mass balance, conservatively assuming the corrosion product to be Cu 2 O only. Additionally, oxidants produced by H 2 O radiolysis could result in a further 10–30 µm penetration of the Cu coating.…”
Section: Introductionmentioning
confidence: 99%
“…Since copper is the only absolute barrier preventing the release of radionuclides in the case of Swedish/Finnish, Canadian, and other world's high‐level radioactive waste disposal programs (including Taiwan, Korea, Japan, and Switzerland), the corrosion of copper has been studied extensively in various environments and conditions simulating various times after emplacement. [ 1–11 ]…”
Section: Introductionmentioning
confidence: 99%
“…[ 2 ] Upon sealing, a limited amount of air becomes trapped in the repository, in the low‐permeability groundwater‐saturated bentonite surrounding the container. [ 1 ] This O 2 is then consumed by various reactions and also by corrosion of the copper container. The time for the predicted O 2 concentration to decrease to 1% of the initial level ranged between 10 and 300 years in deep geological repository (DGR) in granite rock [ 2 ] and 40 and additional 30 years in the case of DGR in opalinus clay.…”
Section: Introductionmentioning
confidence: 99%
See 1 more Smart Citation
“…The primary corrosion mechanism expected to affect copper canisters in a KBS-3-type repository for spent nuclear fuel is general corrosion. [1][2][3][4] Corrosion, of course, will not be perfectly uniform and some degree of localisation is expected. The manner in which this localised attack has been treated in canister lifetime assessments has changed over the years as our understanding of the nature of the near-field environment and of the associated corrosion processes has developed.…”
Section: Introductionmentioning
confidence: 99%