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

Heikki Kumpulainen, Jarmo Lehikoinen, Arto Muurinen

Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-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 languageEnglish
Title of host publicationSymposium QQ — Scientific Basis for Nuclear Waste Management XXIII
EditorsD.W. Shoesmith, R.W. Smith
PublisherMaterials Research Society
Pages123-128
ISBN (Print)1-55899-516-1
DOIs
Publication statusPublished - 2000
MoE publication typeA4 Article in a conference publication
Event23rd International Symposium on the Scientific Basis for Nuclear Waste Management: (1999 MRS Fall Meeting) - Boston, United States
Duration: 29 Nov 19993 Dec 1999

Publication series

SeriesMaterials Research Society Symposia Proceedings
Volume608
ISSN0272-9172

Conference

Conference23rd International Symposium on the Scientific Basis for Nuclear Waste Management
Country/TerritoryUnited States
CityBoston
Period29/11/993/12/99

Keywords

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

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