Chemical interactions in the near-field of a repository for spent nuclear fuel - A modelling study.

Heikki Kumpulainen; Jarmo Lehikoinen; Arto Muurinen

doi:10.1557/PROC-608-123

Chemical interactions in the near-field of a repository for spent nuclear fuel - A modelling study.

Heikki Kumpulainen
, Jarmo Lehikoinen
, Arto Muurinen

VTT Technical Research Centre of Finland

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

2 Citations (Scopus)

Abstract

The near-field chemistry of the repository for spent nuclear fuel arising from interactions between the groundwater, compacted bentonite clay, canister and the spent fuel was calculated using a three-successive-closed-systems approach. The calculations were performed for fresh granitic and saline groundwaters using the thermodynamic computer codes, HYDRAQL/CE and EQ3/6. The effects of water chemistry inside the canister as well as water radiolysis on fuel dissolution were taken into consideration. The groundwater and the three barriers of the near-field were accounted for by this approach, with particular emphasis given to the pH, Eh and actinide solubilities.

Original language	English
Title of host publication	Symposium QQ — Scientific Basis for Nuclear Waste Management XXIII
Editors	D.W. Shoesmith, R.W. Smith
Publisher	Materials Research Society
Pages	123-128
ISBN (Print)	1-55899-516-1
DOIs	https://doi.org/10.1557/PROC-608-123
Publication status	Published - 2000
MoE publication type	A4 Article in a conference publication
Event	23rd International Symposium on the Scientific Basis for Nuclear Waste Management: (1999 MRS Fall Meeting) - Boston, United States Duration: 29 Nov 1999 → 3 Dec 1999

Publication series

Series	Materials Research Society Symposia Proceedings
Volume	608
ISSN	0272-9172

Conference

Conference	23rd International Symposium on the Scientific Basis for Nuclear Waste Management
Country/Territory	United States
City	Boston
Period	29/11/99 → 3/12/99

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

SDG 12 Responsible Consumption and Production

Keywords

nuclear waste management
near-field chemistry
spent nuclear fuel
bentonite
canister

Access to Document

10.1557/PROC-608-123

Cite this

Kumpulainen, Heikki ; Lehikoinen, Jarmo ; Muurinen, Arto. / Chemical interactions in the near-field of a repository for spent nuclear fuel - A modelling study. Symposium QQ — Scientific Basis for Nuclear Waste Management XXIII. editor / D.W. Shoesmith ; R.W. Smith. Materials Research Society, 2000. pp. 123-128 (Materials Research Society Symposia Proceedings, Vol. 608).

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title = "Chemical interactions in the near-field of a repository for spent nuclear fuel - A modelling study.",

abstract = "The near-field chemistry of the repository for spent nuclear fuel arising from interactions between the groundwater, compacted bentonite clay, canister and the spent fuel was calculated using a three-successive-closed-systems approach. The calculations were performed for fresh granitic and saline groundwaters using the thermodynamic computer codes, HYDRAQL/CE and EQ3/6. The effects of water chemistry inside the canister as well as water radiolysis on fuel dissolution were taken into consideration. The groundwater and the three barriers of the near-field were accounted for by this approach, with particular emphasis given to the pH, Eh and actinide solubilities.",

keywords = "nuclear waste management, near-field chemistry, spent nuclear fuel, bentonite, canister",

author = "Heikki Kumpulainen and Jarmo Lehikoinen and Arto Muurinen",

note = "Based on poster. Poster record deleted. Project code: K9SU00119; 23rd International Symposium on the Scientific Basis for Nuclear Waste Management : (1999 MRS Fall Meeting) ; Conference date: 29-11-1999 Through 03-12-1999",

year = "2000",

doi = "10.1557/PROC-608-123",

language = "English",

isbn = "1-55899-516-1",

series = "Materials Research Society Symposia Proceedings",

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editor = "D.W. Shoesmith and R.W. Smith",

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Kumpulainen, H, Lehikoinen, J & Muurinen, A 2000, Chemical interactions in the near-field of a repository for spent nuclear fuel - A modelling study. in DW Shoesmith & RW Smith (eds), Symposium QQ — Scientific Basis for Nuclear Waste Management XXIII. Materials Research Society, Materials Research Society Symposia Proceedings, vol. 608, pp. 123-128, 23rd International Symposium on the Scientific Basis for Nuclear Waste Management, Boston, United States, 29/11/99. https://doi.org/10.1557/PROC-608-123

Chemical interactions in the near-field of a repository for spent nuclear fuel - A modelling study. / Kumpulainen, Heikki; Lehikoinen, Jarmo; Muurinen, Arto.
Symposium QQ — Scientific Basis for Nuclear Waste Management XXIII. ed. / D.W. Shoesmith; R.W. Smith. Materials Research Society, 2000. p. 123-128 (Materials Research Society Symposia Proceedings, Vol. 608).

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Scientific › peer-review

TY - GEN

T1 - Chemical interactions in the near-field of a repository for spent nuclear fuel - A modelling study.

AU - Kumpulainen, Heikki

AU - Lehikoinen, Jarmo

AU - Muurinen, Arto

N1 - Based on poster. Poster record deleted. Project code: K9SU00119

PY - 2000

Y1 - 2000

N2 - The near-field chemistry of the repository for spent nuclear fuel arising from interactions between the groundwater, compacted bentonite clay, canister and the spent fuel was calculated using a three-successive-closed-systems approach. The calculations were performed for fresh granitic and saline groundwaters using the thermodynamic computer codes, HYDRAQL/CE and EQ3/6. The effects of water chemistry inside the canister as well as water radiolysis on fuel dissolution were taken into consideration. The groundwater and the three barriers of the near-field were accounted for by this approach, with particular emphasis given to the pH, Eh and actinide solubilities.

AB - The near-field chemistry of the repository for spent nuclear fuel arising from interactions between the groundwater, compacted bentonite clay, canister and the spent fuel was calculated using a three-successive-closed-systems approach. The calculations were performed for fresh granitic and saline groundwaters using the thermodynamic computer codes, HYDRAQL/CE and EQ3/6. The effects of water chemistry inside the canister as well as water radiolysis on fuel dissolution were taken into consideration. The groundwater and the three barriers of the near-field were accounted for by this approach, with particular emphasis given to the pH, Eh and actinide solubilities.

KW - nuclear waste management

KW - near-field chemistry

KW - spent nuclear fuel

KW - bentonite

KW - canister

U2 - 10.1557/PROC-608-123

DO - 10.1557/PROC-608-123

M3 - Conference article in proceedings

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SP - 123

EP - 128

BT - Symposium QQ — Scientific Basis for Nuclear Waste Management XXIII

A2 - Shoesmith, D.W.

A2 - Smith, R.W.

PB - Materials Research Society

T2 - 23rd International Symposium on the Scientific Basis for Nuclear Waste Management

Y2 - 29 November 1999 through 3 December 1999

ER -

Kumpulainen H, Lehikoinen J, Muurinen A. Chemical interactions in the near-field of a repository for spent nuclear fuel - A modelling study. In Shoesmith DW, Smith RW, editors, Symposium QQ — Scientific Basis for Nuclear Waste Management XXIII. Materials Research Society. 2000. p. 123-128. (Materials Research Society Symposia Proceedings, Vol. 608). doi: 10.1557/PROC-608-123

Chemical interactions in the near-field of a repository for spent nuclear fuel - A modelling study.

Abstract

Publication series

Conference

UN SDGs

Keywords

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