Dissolution behaviour of spent nuclear fuel at highly alkaline conditions: Phenomenological synthesis report

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Dissolution behaviour of spent nuclear fuel at highly alkaline conditions : Phenomenological synthesis report. / Lemmens, Karel; Cachoir, Christelle; Mennecart, Thierry.

Studiecentrum voor Kernenergie, 2019. 103 p. (SCK•CEN Reports; No. ER-0505).

Research output: Report/bookER - External reportpeer-review

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@book{9cf87d49ff854625b17c86d61511f071,
title = "Dissolution behaviour of spent nuclear fuel at highly alkaline conditions: Phenomenological synthesis report",
abstract = "This report gives a summary of literature data pertaining to the dissolution behaviour of spent nuclear fuel in generic geological disposal conditions, with special attention to the highly alkaline systems that are dominated by the presence of Ordinary Portland Cement (OPC). It contains a description of the spent fuel alteration and dissolution mechanisms, leading to the release of radionuclides. The report focuses on the release of radionuclides that are incorporated in the UO2 matrix. Both results found in the open literature and results generated in the framework of the Belgian R&D programme are presented. The available information shows that the dissolution behaviour of spent fuel in a system dominated by the presence of OPC (contact with high pH cement water) is similar to the dissolution expected in other conditions (contact with near-neutral pH ground waters), both in terms of mechanisms and in terms of the resulting dissolution rate.",
keywords = "spent fuel, dissolution, supercontainer, cement, phenomenology",
author = "Karel Lemmens and Christelle Cachoir and Thierry Mennecart",
note = "Score=2",
year = "2019",
month = jan,
day = "1",
language = "English",
series = "SCK•CEN Reports",
publisher = "Studiecentrum voor Kernenergie",
number = "ER-0505",

}

RIS - Download

TY - BOOK

T1 - Dissolution behaviour of spent nuclear fuel at highly alkaline conditions

T2 - Phenomenological synthesis report

AU - Lemmens, Karel

AU - Cachoir, Christelle

AU - Mennecart, Thierry

N1 - Score=2

PY - 2019/1/1

Y1 - 2019/1/1

N2 - This report gives a summary of literature data pertaining to the dissolution behaviour of spent nuclear fuel in generic geological disposal conditions, with special attention to the highly alkaline systems that are dominated by the presence of Ordinary Portland Cement (OPC). It contains a description of the spent fuel alteration and dissolution mechanisms, leading to the release of radionuclides. The report focuses on the release of radionuclides that are incorporated in the UO2 matrix. Both results found in the open literature and results generated in the framework of the Belgian R&D programme are presented. The available information shows that the dissolution behaviour of spent fuel in a system dominated by the presence of OPC (contact with high pH cement water) is similar to the dissolution expected in other conditions (contact with near-neutral pH ground waters), both in terms of mechanisms and in terms of the resulting dissolution rate.

AB - This report gives a summary of literature data pertaining to the dissolution behaviour of spent nuclear fuel in generic geological disposal conditions, with special attention to the highly alkaline systems that are dominated by the presence of Ordinary Portland Cement (OPC). It contains a description of the spent fuel alteration and dissolution mechanisms, leading to the release of radionuclides. The report focuses on the release of radionuclides that are incorporated in the UO2 matrix. Both results found in the open literature and results generated in the framework of the Belgian R&D programme are presented. The available information shows that the dissolution behaviour of spent fuel in a system dominated by the presence of OPC (contact with high pH cement water) is similar to the dissolution expected in other conditions (contact with near-neutral pH ground waters), both in terms of mechanisms and in terms of the resulting dissolution rate.

KW - spent fuel

KW - dissolution

KW - supercontainer

KW - cement

KW - phenomenology

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/32826546

M3 - ER - External report

T3 - SCK•CEN Reports

BT - Dissolution behaviour of spent nuclear fuel at highly alkaline conditions

PB - Studiecentrum voor Kernenergie

ER -

ID: 4859474