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