RD&D-Programme 2004 - SKB

15-18 Loida A, Grambow B, Geckeis H, 2001. Spent Fuel corrosion behaviour in salt solution in the
presence of hydrogen overpressure. Proceedings of the ICEM 01 Conference, Bruges, Belgium.
15-19 Albinsson Y, Jensen A Ö, Oversby V, Werme L, 2003. Leaching of spent fuel under anaerobic and
reducing conditions. In Scientific Basis for Nuclear waste management XXVI, Materials Research
Society Symposium Series, Vol 757, (Finch R J and Bullen DB eds), pp 407–413.
15-20 Poinssot C (ed), 2003. Spent fuel stability under repository conditions. EU-Project SFS, 2 nd Annual
Report.
15-21 Bruno J, Cera E, Eriksen T E, Grivé M, Ripoll S, 2004. Modelling experimental results on
radiolytic processes at the spent fuel water interface. Radiolysis products and U release. In Scientific
Basis for Nuclear Waste Management XXVII, Materials Research Society Symposium Proceedings
(V M Oversby and L O Werme eds), Vol 807, pp 397–402.
15-22 Pastina B, Isabey J, Hickel B, 1999. The influence of water chemistry on the radiolysis of primary
coolant water in pressurized water reactors. Journal of Nuclear Materials, 264, pp 309–318.
15-23 Pastina B, LaVerne J A, 2001. Effect of molecular hydrogen on hydrogen peroxide in water
radiolysis. Journal of Physical Chemistry A, 105, pp 9316–9322.
15-24 Eriksen T, 1996. Radiolysis of water within a ruptured fuel element. SKB PR U-96-29,
Svensk Kärnbränslehantering AB.
15-25 Christensen H, 1998. Calculations simulating spent fuel leaching experiments. Nuclear Technology
124, pp 165–174.
15-26 Jonsson M, Nielsen F, Ekeroth E, Eriksen T, 2004. Modeling of the effects of radiolysis on
UO 2 -dissolution employing recent experimental data. In Scientific Basis for Nuclear Waste
Management XXVII, Materials Research Society Symposium Proceedings (V M Oversby and
L O Werme eds), Vol 807, pp 385–390.
15-27 Liu L, Neretnieks I, 2002. The effect of hydrogen on the oxidative dissolution of spent fuel. Nuclear
Technology, 138, pp 69–77.
15-28 King F, Quinn M J, Miller N H, 1999. The effect of hydrogen and gamma radiation on the oxidation
of UO 2 in 0.1 mol·dm –3 NaCl solution. SKB TR-99-27, Svensk Kärnbränslehantering AB.
15-29 Sunder S, Boyer G D, Miller N H, 1990. XPS studies of UO 2 oxidation by alpha radiolysis of water
at 100°C. Journal of Nuclear Materials, 175, pp 163–169.
15-30 LaVerne J A, Tandon L, 2003. H 2 production in the radiolysis of water on UO 2 and other oxides.
Journal of Physical Chemistry B, 107, pp 13623–13628.
15-31 Cui D, Spahiu K, 2001. On the interaction between uranyl carbonate and UO 2 (s) in anaerobic aqueous
solution. Journal of Nuclear Science and Technology, Supplement 3, pp 500–503.
15-32 Imizu Y, Tanabe K, Hattori H, 1979. Selective formation of trans-butene and methyl-butene in
deuteration of butadiene derivatives over thorium oxide catalyst. Journal of Catalysis, 56, pp 303–314.
15-33 Haschke J M, Allen T H, Stakebake J L, 1996. Reaction kinetics of plutonium with oxygen, water
and humid air. Journal of Alloys and Compounds, 243, pp 23–35.
15-34 Devoy J, Haschke J, Cui D, Spahiu K, 2004. Behaviour of uranium dioxide: Chemistry and catalysis
in the UO 2 -water system. In Scientific Basis for Nuclear Waste Management XXVII, Materials
Research Society Symposium Proceedings (V M Oversby and L O Werme eds), Vol 807, pp 41–46.
15-35 Cui D, Low J, Sjöstedt C J, Spahiu K, 2003. On Mo-Ru-Tc-Pd-Rh alloy particles extracted from
spent fuel and their leaching behavior under repository conditions. Presented at Migration 2003
Conference, Radiochimica Acta (in press).
15-36 Forsyth R S, 1997. The SKB spent fuel corrosion programme. An evaluation of results from
the experimental programme performed in the Studsvik Hot Cell Laboratory. SKB TR 97-25,
Svensk Kärnbränslehantering AB.
15-37 Cui D, Devoy J, Spahiu K, 2003. The surface precipitation during the UO 2 leaching process. In
Scientific Basis for Nuclear waste management XXVI, Materials Research Society Symposium Series,
Vol 757, (Finch R J and Bullen D B eds), pp 359–364.
15-38 Werme L O, Spahiu K, 1998. Direct disposal of spent nuclear fuel: comparison between experimental
and modelled actinide solubilities in natural waters. Journal of Alloys and Compounds. 271–273,
pp 194–200.
15-39 Röllin S, Spahiu K, Eklund U-B, 2001. Determination of dissolution rates of spent fuel in carbonate
solutions under different redox conditions with a flow-through experiment. Journal of Nuclear
Materials, 297, pp 231–243.
15-40 Cui D, Spahiu K, Wersin P, 2003. Redox reactions of iron and uranium in simulated cement pore
water under anoxic conditions. In Scientific Basis for Nuclear waste management XXVI, Materials
Research Society Symposium Series, Vol 757 (Finch R J and Bullen D B eds), pp 427–432.
15-41 Bruno J, Cera E, Grive M, Duro L, Eriksen T, 2003. Experimental determination and chemical
modelling of the radiolytic processes at the spent fuel water interface. Experiments carried
out in carbonate solutions in absence and presence of chloride. SKB TR-03-03,
Svensk Kärnbränslehantering AB.
RD&D-Programme 2004 341