RD&D-Programme 2004 - SKB

Chapter 14
14-1 SKB, 2004. Interim main report of the safety assessment SR-Can. SKB TR-04-11,
Svensk Kärnbränslehantering AB.
14-2 SKB, 1999. Deep repository for spent nuclear fuel. SR 97 – Post-closure safety. Main Report,
Volumes I and II. Svensk Kärnbränslehantering AB.
14-3 Posiva, 2003. Nuclear waste management of the Olkiluoto and Loviisa power plants: Programme for
research, development and technical design for 2004–2006. TKS-2003, Posiva Oy, Olkiluoto, Finland.
14-4 SKB, 2003. Planning report for the safety assessment SR-Can. SKB TR-03-08,
Svensk Kärnbränslehantering AB.
14-5 Hedin A, 2004. Integrated near field evolution model for an SNF repository. SKB R-04-36,
Svensk Kärnbränslehantering AB.
14-6 Hedin A, 2002. Integrated Analytic Radionuclide Transport Model for a Spent Nuclear Fuel Repository
in Saturated Fractured Rock. Nuclear Technology 138(2002):2 pp 179–205.
14-7 Romero L, 1995. The near-field transport in a repository for high-level nuclear waste. Ph.D. Thesis,
TRITA-KET R21, The Royal Institute of Technology.
14-8 Norman S, Kjellbert N, 1990. FARF31 – A far field radionuclide migration code for use in the Proper
package. SKB TR 90-01, Svensk Kärnbränslehantering AB.
14-9 Romero L, Thompson A, Moreno L, Neretnieks I, Widén H, Boghammar A, 1999. Comp23/
Nuctran User’s Guide. SKB TR-99-29, Svensk Kärnbränslehantering AB.
14-10 Bergström U, Nordlinder S, Aggeryd I, 1999. Models for dose assessments. Modules for various
biosphere types. SKB TR-99-14, Svensk Kärnbränslehantering AB.
Chapter 15
15-1 SKB, 2003. Plan 2003. Costs for management of the radioactive waste products from nuclear power
production. Svensk Kärnbränslehantering AB.
15-2 SKB, 1999. SR 97, Main Report, Volume I. Svensk Kärnbränslehantering AB.
15-3 Olander D, 2004. Thermal spike theory of a thermal diffusion of fission products due to alpha decay of
actinides in spent fuel (UO 2 ). SKB TR-04-17. Svensk Kärnbränslehantering AB.
15-4 Håkansson R, 1999. Beräkning av nuklidinnehåll, resteffekt, aktivitet samt doshastighet för utbränt
kärnbränsle. SKB R-99-74, Svensk Kärnbränslehantering AB.
15-5 Agrenius L, 2002. Criticality safety calculations of storage canisters. SKB TR-02-17,
Svensk Kärnbränslehantering AB.
15-6 Cui D, Low J, Lundström M, Spahiu K, 2004. Spent fuel leaching under anoxic conditions and
the effect of canister materials. In Scientific Basis for Nuclear Waste Management XXVII, Materials
Research Society Symposium Proceedings (V M Oversby and L O Werme eds), Vol 807, pp 89–94.
15-7 Spahiu K, Eklund U-B, Cui D, Lundström M, 2002. The influence of near field redox conditions
on spent fuel leaching. In Scientific Basis for Nuclear waste management XXV, Materials Research
Society Symposium Series, Vol 713 (B Peter McGrail and G Cragnolino eds), pp 633–638.
15-8 Cui D, Spahiu K, 2002. The reduction of U(VI) on corroded iron under anoxic groundwater conditions
Radiochimica Acta, 90, pp 1–6.
15-9 Spahiu K, Devoy J, Cui D, Lundström M, 2003. The reduction of U(VI) by near field hydrogen in
the presence of UO 2 (s). Presented at Migration 2003 Conference, Radiochimica Acta (in press).
15-10 Ollila K, Lindqvist K, 2003. Air oxidation tests with Gd-doped UO 2 . Preliminary dissolution
experiments with pre-oxidized Gd-doped UO 2+x . Posiva Report 2003-08, Posiva OY.
15-11 Ollila K, Albinsson Y, Oversby V, Cowper M, 2003. Dissolution rates of unirradiated UO 2 , UO 2
doped with 233 U, and spent fuel under normal atmospheric conditions and under reducing conditions
using an isotope dilution method. SKB TR-03-13, Svensk Kärnbränslehantering AB.
15-12 SKB, 1999. SR 97, Main Report, Volume II. Svensk Kärnbränslehantering AB.
15-13 Sellin P, 2001. SR 97: Hydromechanical evolution in a defective canister. In Scientific Basis for
Nuclear waste management XXVI, Materials Research Society Symposium Series, Vol 663,
(Hart K P and Lumpkin G R eds), pp 755–763.
15-14 Spahiu K, Werme L, Eklund U-B, 2000. The influence of near field hydrogen on actinide solubilities
and spent fuel leaching. Radiochimica Acta, 88, pp 507–511.
15-15 Guppy R M, Atkinson A, Valentine T M, 1989. Studies of the solubility of technetium under a range
of redox conditions. Harwell ARE-R 13467, DOE/RW/89/102.
15-16 Cui D, Eriksen T, 1996. Reduction of Tc(VII) and Np(V) in solution by ferrous iron.
A laboratory study of homogeneous and heterogeneous redox processes. SKB TR-96-03,
Svensk Kärnbränslehantering AB.
15-17 Spahiu K, Cui D, Lundström M, 2003. The fate of radiolytic oxidants during spent fuel leaching in
the presence of dissolved near field hydrogen. Presented at Migration 2003 Conference, Radiochimica
Acta (in press).
340 RD&D-Programme 2004