Hydrogen gas production during corrosion of copper by water

Hultquist, Gunnar; Graham, M. J.; Szakálos, Peter; Sproule, G. I.; Rosengren, Anders; Gråsjö, L.

doi:10.1016/j.corsci.2010.09.037

Cited by 51 publications

(66 citation statements)

References 13 publications

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“…The O 2 anion sublattice is body-centered cubic (BCC) and splits into two diamond structures when the ionic coordination is considered: Each O 2 anion is tetrahedrally coordinated by four Cu + cations, while each Cu + cation is linearly coordinated by two anions (7). All the Cu + ions taken together constitute a face-centered cubic (FCC) cation sublattice in Cu 2 O.…”

Section: Crystal Structuresmentioning

confidence: 99%

“…For some applications, where the system is driven out of equilibrium, the knowledge of the structure and properties of stable as well as metastable compounds is necessary for for understanding, predicting, and controlling the behavior of copper. Although Cu 2 O and CuOH have been detected as products of copper corrosion under anoxic conditions 4,[6][7][8] , some circumstances of such corrosion behavior are still unclear 9,10 .…”

Section: Introductionmentioning

confidence: 99%

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Physical and chemical properties of Cu(i) compounds with O and/or H

Korzhavyi

2017

Dalton Trans.

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Section: Crystal Structuresmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Physical and chemical properties of Cu(i) compounds with O and/or H

Korzhavyi

2017

Dalton Trans.

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“…Corrosion of copper under anaerobic conditions has been debated quite vigorously during the past decade [76][77][78][79]. There is still a controversy on this issue, but ongoing experiments will hopefully resolve this.…”

Section: Copper Canistermentioning

confidence: 99%

Radiation Effects on Materials Used in Geological Repositories for Spent Nuclear Fuel

Jönsson

2012

ISRN Materials Science

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Safe long-term storage of radioactive waste from nuclear power plants is one of the main concerns for the nuclear industry as well as for governments in countries relying on electricity produced by nuclear power. A repository for spent nuclear fuel must be safe for extremely long time periods (at least 100 000 years). In order to ascertain the long-term safety of a repository, extensive safety analysis must be performed. One of the critical issues in a safety analysis is the long-term integrity of the barrier materials used in the repository. Ionizing radiation from the spent nuclear constitutes one of the many parameters that need to be accounted for. In this paper, the effects of ionizing radiation on the integrity of different materials used in a granitic deep geological repository for spent nuclear fuel designed according to the Swedish KBS-3 model are discussed. The discussion is primarily focused on radiationinduced processes at the interface between groundwater and solid materials. The materials that are discussed are the spent nuclear fuel (based on UO 2 ), the copper-covered iron canister, and bentonite clay. The latter two constitute the engineered barriers of the repository.

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“…In this context, appropriate selection of the material for the corrosion-resistant layer of containers is of paramount importance. Containment periods from 500 to 10 6 years are required depending on the selected container material and host rock. Different backfill materials have been proposed for filling and sealing the repository tunnels.…”

Section: Introductionmentioning

confidence: 99%

“…However, copper thermodynamical immunity has been challenged. 10 Corrosion-resistant materials such as stainless steels, nickel-based alloys and titanium alloys may be used in the two types of repositories. 8,9 The degradation processes that limit the containers lifetime include general corrosion, localised corrosion, stress corrosion cracking (SCC), hydrogen-assisted cracking and microbiologically influenced corrosion.…”

mentioning

confidence: 99%

Crevice corrosion of nickel-based alloys considered as engineering barriers of geological repositories

Carranza

Rodríguez

2017

npj Mater Degrad

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Nickel-based alloys are considered among other candidate materials as engineering barriers of geological repositories due to their excellent corrosion resistance. These alloys possess unique advantages: they may be used in saturated and unsaturated repositories, hosted by practically any rock type, while also compatible with any (or no) backfill, and have minimal impact in other barriers. Alloy-22 (UNS N06022) has been the most studied of this class of alloys for its potential application in the proposed repositories (namely Yucca Mountain, USA). Crevice corrosion is however an important and often unintended degradation process that may limit the waste container lifetime if a nickel-based alloy is selected. Alloy susceptibility to crevice corrosion is influenced by environmental and metallurgical variables. This review gives an account of the current knowledge regarding crevice corrosion of nickel-based alloys as candidate materials for the corrosion-resistant layer of high-level nuclear waste containers. Although there is a significant amount of research supporting the use of nickel-based alloys for this application, the effect of the different variables on crevice corrosion resistance is described. Special focus is given to the current criterion for crevice corrosion occurrence in repository environments, recent works and criticisms. The presently established criterion appears robust for ruling out crevice corrosion in saturated repositories; however, the development of a less conservative criterion for crevice corrosion occurrence is necessary to use these alloys in unsaturated repositories.

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Hydrogen gas production during corrosion of copper by water

Abstract: Hydrogen gas production during corrosion of copper by water Hultquist, G.; Graham, M. J.; Szakalos, P.; Sproule, G.I.; Rosengren, A.; Gråsjö, L.Contact us / Contactez nous: nparc.cisti@nrc-cnrc.gc.ca.

Cited by 51 publications

References 13 publications

Physical and chemical properties of Cu(i) compounds with O and/or H

Physical and chemical properties of Cu(i) compounds with O and/or H

Radiation Effects on Materials Used in Geological Repositories for Spent Nuclear Fuel

Crevice corrosion of nickel-based alloys considered as engineering barriers of geological repositories

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