A review of corrosion considerations of container materials relevant to underground disposal of HLW in Belgium

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

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A review of corrosion considerations of container materials relevant to underground disposal of HLW in Belgium. / Kursten, Bruno; Druyts, Frank.

Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX. Warrendale, United States, 2006. p. 805-812.

Research output: Contribution to report/book/conference proceedingsIn-proceedings paper

Harvard

Kursten, B & Druyts, F 2006, A review of corrosion considerations of container materials relevant to underground disposal of HLW in Belgium. in Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX. Warrendale, United States, pp. 805-812, MRS 2005. 29th International Symposium on the Scientific Basis for Nuclear Waste Management, Gent, Belgium, 2005-09-12.

APA

Kursten, B., & Druyts, F. (2006). A review of corrosion considerations of container materials relevant to underground disposal of HLW in Belgium. In Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX (pp. 805-812). Warrendale, United States.

Vancouver

Kursten B, Druyts F. A review of corrosion considerations of container materials relevant to underground disposal of HLW in Belgium. In Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX. Warrendale, United States. 2006. p. 805-812

Author

Kursten, Bruno ; Druyts, Frank. / A review of corrosion considerations of container materials relevant to underground disposal of HLW in Belgium. Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX. Warrendale, United States, 2006. pp. 805-812

Bibtex - Download

@inproceedings{68374065b7c146f6950583b90eeda270,
title = "A review of corrosion considerations of container materials relevant to underground disposal of HLW in Belgium",
abstract = "The underground formation that is currently being considered in Belgium for the permanent disposal of vitrified HLW and spent fuel is an argillaceous sediment (viz. Boom Clay layer), which is located in the northeast of Belgium and extending under the Mol-Dessel nuclear site at a depth between 180 and 280 meter. The corrosion resistance of the metallic container is an important aspect within the disposal concept as it has to provide a high integrity, i.e. no through-the-wall corrosion should occur, at least for the duration of the thermal phase (500 years for HLW and 2000 years for spent fuel). An extensive corrosion evaluation programme was started in the mid 1980's. The main objective is to evaluate the long-term corrosion performance of a broad range of candidate container materials. In addition, the influence of several parameters, such as temperature, oxygen content, groundwater composition (chloride, sulphate and thiosulphate), γ-radiation, ... are investigated. The experimental approach consisted of in situ experiments (performed in the underground research facility, HADES), electrochemical experiments, immersion experiments and a large scale demonstration test (OPHELIE). Degradation modes considered include general corrosion, localised corrosion (pitting) and stress corrosion cracking.",
keywords = "localised corrosion, pitting, Ni-alloy, Ti-alloy, review, radioactive waste, disposal, clay, uniform corrosion, carbon steel, stainless steel",
author = "Bruno Kursten and Frank Druyts",
note = "Score = 1",
year = "2006",
month = "6",
language = "English",
isbn = "978-1-55899-889-6",
pages = "805--812",
booktitle = "Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX",

}

RIS - Download

TY - GEN

T1 - A review of corrosion considerations of container materials relevant to underground disposal of HLW in Belgium

AU - Kursten, Bruno

AU - Druyts, Frank

N1 - Score = 1

PY - 2006/6

Y1 - 2006/6

N2 - The underground formation that is currently being considered in Belgium for the permanent disposal of vitrified HLW and spent fuel is an argillaceous sediment (viz. Boom Clay layer), which is located in the northeast of Belgium and extending under the Mol-Dessel nuclear site at a depth between 180 and 280 meter. The corrosion resistance of the metallic container is an important aspect within the disposal concept as it has to provide a high integrity, i.e. no through-the-wall corrosion should occur, at least for the duration of the thermal phase (500 years for HLW and 2000 years for spent fuel). An extensive corrosion evaluation programme was started in the mid 1980's. The main objective is to evaluate the long-term corrosion performance of a broad range of candidate container materials. In addition, the influence of several parameters, such as temperature, oxygen content, groundwater composition (chloride, sulphate and thiosulphate), γ-radiation, ... are investigated. The experimental approach consisted of in situ experiments (performed in the underground research facility, HADES), electrochemical experiments, immersion experiments and a large scale demonstration test (OPHELIE). Degradation modes considered include general corrosion, localised corrosion (pitting) and stress corrosion cracking.

AB - The underground formation that is currently being considered in Belgium for the permanent disposal of vitrified HLW and spent fuel is an argillaceous sediment (viz. Boom Clay layer), which is located in the northeast of Belgium and extending under the Mol-Dessel nuclear site at a depth between 180 and 280 meter. The corrosion resistance of the metallic container is an important aspect within the disposal concept as it has to provide a high integrity, i.e. no through-the-wall corrosion should occur, at least for the duration of the thermal phase (500 years for HLW and 2000 years for spent fuel). An extensive corrosion evaluation programme was started in the mid 1980's. The main objective is to evaluate the long-term corrosion performance of a broad range of candidate container materials. In addition, the influence of several parameters, such as temperature, oxygen content, groundwater composition (chloride, sulphate and thiosulphate), γ-radiation, ... are investigated. The experimental approach consisted of in situ experiments (performed in the underground research facility, HADES), electrochemical experiments, immersion experiments and a large scale demonstration test (OPHELIE). Degradation modes considered include general corrosion, localised corrosion (pitting) and stress corrosion cracking.

KW - localised corrosion

KW - pitting

KW - Ni-alloy

KW - Ti-alloy

KW - review

KW - radioactive waste

KW - disposal

KW - clay

KW - uniform corrosion

KW - carbon steel

KW - stainless steel

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_30898

UR - http://knowledgecentre.sckcen.be/so2/bibref/3536

M3 - In-proceedings paper

SN - 978-1-55899-889-6

SP - 805

EP - 812

BT - Symposium Proceedings. Scientific Basis for Nuclear Waste Management XXIX

CY - Warrendale, United States

ER -

ID: 87642