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Modelling experimental results on radiolytic processes at the spent fuel water interface. II. Radionuclides release
KTH, School of Chemical Science and Engineering (CHE), Chemistry, Nuclear Chemistry (closed 20110630).
2006 (English)In: Mater Res Soc Symp Proc, 2006, 537-546 p.Conference paper (Refereed)
Abstract [en]

Experimental and modelling efforts in the last decade in the frame of nuclear waste management field have been focused on studying the role of the UO2 surfaces in poising the redox state of solid/water systems as well as the radionuclides release behaviour. For this purpose, an experimental programme was developed consisting on dissolution experiments with PWR spent fuel fragments in an anoxic environment and by using different solution compositions. Some of the collected data has been previously published [1], specifically those data concerning radiolysis products and dissolution of the matrix. The results and the modelling tasks indicated an overall balance of the generated radiolytic species and that uranium dissolution was controlled by the oxidation of the spent fuel matrix in 10mM bicarbonate solutions while in the tests carried out at lower or without carbonate concentrations uranium in the aqueous phase was governed by the precipitation of schoepite. This paper is the continuation of a series accounting for the data and modelling work related to investigating the release behaviour of minor radionuclides from the spent fuel. Uranium concentrations as a function of time showed an initial increase until reaching a steady stale, indicating a matrix dissolution control. The same behaviour is observed for neptunium, caesium, strontium, technetium and molybdenum indicating a congruent release of these elements with the major component of the fuel matrix. On the other hand, no clear tendency is observed for plutonium data where additional solubility limiting mechanisms may apply. Kinetic modelling of the trace elements: caesium, strontium, technetium and molybdenum is based on the congruent release of these elements with the major component of the fuel matrix. Rate constants have been determined. Kinetic modelling of neptunium data took also into account the. subsequent precipitation as Np(IV) hydroxide. Finally, measured Pu concentrations may be explained by the precipitation of Pu(IV) and/or Pu(III) solid phases.

Place, publisher, year, edition, pages
2006. 537-546 p.
, Materials Research Society Symposium Proceedings, ISSN 0272-9172 ; 932
Keyword [en]
Dissolution, Precipitation (chemical), Radioactive waste disposal, Radioisotopes, Radiolysis, Spent fuels, Kinetic modeling, Limiting mechanisms, Matrix dissolution control, Spent fuel matrix, Interfaces (materials)
National Category
Energy Engineering
URN: urn:nbn:se:kth:diva-156325ISI: 000239003700063ScopusID: 2-s2.0-33746101448ISBN: 1558998896ISBN: 9781558998896OAI: diva2:766840
29th International Symposium on the Scientific Basis for Nuclear Waste Management XXIX, 12-16 September 2005, Ghent, Belgium

QC 20141128

Available from: 2014-11-28 Created: 2014-11-26 Last updated: 2014-11-28Bibliographically approved

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Eriksen, Trygve E.
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