RD&D-Programme 2004 - SKB

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16-12 King F, 2002. Corrosion of copper in alkaline chloride environments. SKB TR-02-25, Svensk Kärnbränslehantering AB. 16-13 Fennel P A H, Graham A J, Smart N R, Sofield C J, 2001. Grain boundary corrosion of copper canister material. SKB TR-01-09, Svensk Kärnbränslehantering AB. 16-14 Bojinov M, Mäkelä K, 2003. Corrosion of copper in anoxic 1M NaCl solution. Posiva Working Report 2003-45, Posiva Oy, Finland. 16-15 Betova I, Bojinov M, Laitinen T, Mäkelä K, Snellman M, Werme L, 2004. Corrosion of copper in 1 m NaCl under strictly anoxic conditions. In Scientific Basis for Nuclear Waste Management XXVII, Materials Research Society Symposium Proceedings, Vol 807, pp 429–434. 16-16 Masurat P, Pedersen K, 2004. Microbial sulphide formation in compacted bentonite at the commencement of long-term disposal of high-level radioactive waste. In Scientific Basis for Nuclear Waste Management XXVII, Materials Research Society Symposium Proceedings, Vol 807, pp 805–810. 16-17 Taxén C, 2004. Atmospheric corrosion of copper 450 metres underground. Results from three years exposure in the Äspö HRL. In Scientific Basis for Nuclear Waste Management XXVII, Materials Research Society Symposium Proceedings, Vol 807, pp 423–428. Chapter 17 17-1 SKB, 1999. SR 97, Main Report, Volume I. Svensk Kärnbränslehantering AB. 17-2 Meier L P, Kahr G, 1999. Clays and Clay Minerals, 47(3), pp 386–388. 17-3 Müller-Vonmoos M, Kahr G, 1983. Mineralogische Untersuchungen von Wyoming Bentonit MX-80 und Montigel. NAGRA Technischer Bericht NTB 83-12, Wettingen, Switzerland. 17-4 Newman A C D, 1987. Chemistry of Clays and Clay Minerals. Monograph No 6. Mineralogical Society, London. ISBN 0-582-30114-9. 17-5 Hökmark H, Fälth B, 2003. Thermal dimensioning of the deep repository. Influence of canister spacing, canister power, rock thermal properties and nearfield design on the maximum canister surface temperature. SKB TR-03-09, Svensk Kärnbränslehantering AB. 17-6 Ageskog L, Jansson P, 1999. Heat propagation in and around the deep repository. Thermal calculations applied to three hypothetical sites: Aberg, Beberg and Ceberg. SKB TR-99-02, Svensk Kärnbränslehantering AB. 17-7 Claesson J, Probert T, 1996. Temperature field due to time-dependent heat sources in a large rectangular grid. Derivation of analytical solution. SKB TR-96-12, Svensk Kärnbränslehantering AB. 17-8 Börgesson L, Fredrikson A, Johannesson L-E, 1994. Heat conductivity of buffer materials. SKB TR-94-29, Svensk Kärnbränslehantering AB. 17-9 Harrington J F, Horseman S T, 2003. Gas migration in KBS-3 buffer bentonite. Sensitivity of test parameters to experimental boundary conditions. SKB TR-03-02, Svensk Kärnbränslehantering AB. 17-10 Johannesson L-E, Börgesson L, 2002. Äspö Hard Rock Laboratory. Laboratory tests on Friedland Clay. Friedland Clay as backfill material. Results of laboratory tests and swelling/compression calculations. SKB IPR-02-50, Svensk Kärnbränslehantering AB. 17-11 Börgesson L, Johannesson L-E, Hernelind J, 2004. Earthquake induced rock shear through a deposition hole. Effect on the canister and the buffer. SKB TR-04-02, Svensk Kärnbränslehantering AB. 17-12 Börgesson L, Johannesson L-E, Hernelind J, 2004. Earthquake induced rock shear through a deposition hole. Effect on the cansiter and buffer. In Scientific Basis for Nuclear Waste Management XXVII, Materials Research Society Symposium Proceedings, Vol 807, pp 521–526. 17-13 Hökmark H, 2004. Hydration of the bentonite buffer in a KBS-3 repository. International meeting on clays in natural and engineered barriers for radioactive waste confinement in Reims 2002. Applied Clay Science, (in press). 17-14 Hökmark H, 2003. Temperature buffer test – Comparison of modelling results/experimental findings: Causes of differences. Sitges workshop on large scale field tests in granite, November 12–14, 2003, University of Catalonia, Spain. 17-15 Goudarzi R, Börgesson L, Sandén T, Barcena I, 2004. Äspö Hard Rock Laboratory. Temperature buffer test. Sensors data report. Report No:1. SKB IPR-04-02, Svensk Kärnbränslehantering AB. 17-16 Karnland O, Muurinen A, Karlsson F, 2003. Bentonite swelling pressure in NaCl solutions – Experimentally determined data and model calculations. Sitges workshop on large scale field tests in granite. November 12–14, 2003. University of Catalonia, Spain. 17-17 Karnland O, Sellin P, Olsson S, 2004. Mineralogy and some Physical properties of San José bentonite – A natural analogue to buffer material exposed to saline groundwater. In Scientific Basis for Nuclear Waste Management XXVII, Materials Research Society Symposium Proceedings, Vol 807, pp 849–854. 17-18 Domènech C, Arcos D, Bruno J, Karnland O, 2004. Geochemical model of the granite-bentonitegroundwater at Äspö (Lot-experiment). In Scientific Basis for Nuclear Waste Management XXVII, Materials Research Society Symposium Proceedings, Vol 807, pp 855–860. RD&D-Programme 2004 343
17-19 Le Bell J C, 1978. Colloid chemical aspects of the “confined bentonite concept”. KBS TR 97, Svensk Kärnbränslehantering AB. 17-20 Karnland O, Sandén T, Johannesson L-E, Eriksen T E, Jansson M, Wold S, Pedersen K, Motamedi M, Rosborg B, 2000. Long term test of buffer material. Final Report on the pilot parcels. SKB TR-00-22, Svensk Kärnbränslehantering AB. 17-21 Molera M, Eriksen T, Jansson M, 2003. Anion diffusion pathways in bentonite clay compacted to different dry densities. Applied Clay Science 23, pp 69–76. 17-22 Jansson M, Eriksen T, 1998. CHEMLAB – In situ diffusion experiments using radioactive tracers. Radiochimica Acta, 82, pp 153–156. 17-23 Jansson M, Eriksen T, 2004. In situ anion diffusion experiments using radiotracers. Journal of Contaminant Hydrology 68, pp 183–192. 17-24 Jansson M, Eriksen T, Wold S, 2003. LOT – in situ diffusion experiments using radioactive tracers, Applied Clay Science, 23, pp 77–85. 17-25 Neretnieks I, 1979. Transport mechanisms and rates of transport of radionuclides in the geosphere as related to the Swedish KBS concept. Proceedings, International Atomic Energy Agency IAEA-SM- 243/108, July 2–6, pp 315–339. 17-26 Neretnieks I, 1982. Leach rates of high level waste and spent fuel – Limiting rates as determined by backfill and bedrock conditions. In Scientific Basis for Nuclear Waste Management V, Materials Research Society Symposium. Proceedings Vol 11, NorthHolland, New York, pp 559–568. 17-27 Ochs M, Talerico C, 2004. Data and uncertainty assessment. Migration parameters for the bentonite buffer in the KBS-3 concept. SKB TR-04-18, Svensk Kärnbränslehantering AB. 17-28 Wold S, 2003. On diffusion of organic colloids in compacted bentonite. Doctoral Thesis, Department of Nuclear Chemistry, Royal Institute of Technology, Stockholm. Chapter 18 18-1 Gunnarsson D, Börgesson L, Keto P, Tolppanen P, Hansen J, 2004. Backfilling and closure of the deep repository. Assessment of backfill concepts. SKB R-04-53, Svensk Kärnbränslehantering AB. 18-2 Gunnarsson D, Börgesson L, Hökmark H, Johannesson L-E, Sandén T, 2001. Äspö Hard Rock Laboratory. Report on the installation of the Backfill and Plug Test. SKB IPR-01-17, Svensk Kärnbränslehantering AB. 18-3 Börgesson L, Johannesson L-E, Gunnarsson D, 2003. Influence of soil structure heterogeneities on the behaviour of backfill materials based on bentonite and crushed rock. Journal of Applied Clay Science 23. 18-4 Gunnarsson D, 2002. Äspö Hard Rock Laboratory. Backfill production for Prototype Repository. SKB IPR-02-20, Svensk Kärnbränslehantering AB. 18-5 Johannesson L-E, Börgesson L, 2002. Äspö Hard Rock Laboratory. Laboratory tests on Friedland clay. SKB IPR-02-50, Svensk Kärnbränslehantering AB. 18-6 Pusch R, Gunnarsson D, 2001. Field compaction tests on Friedland clay at Äspö Hard Rock Laboratory. SKB IPR-01-36, Svensk Kärnbränslehantering AB. 18-7 Martin C D, Christiansson R, Söderhäll J, 2001. Rock stability considerations for siting and constructing a KBS-3 repository. Based on experiences from Äspö HRL, AECL’s URL, tunnelling and mining. SKB TR-01-38, Svensk Kärnbränslehantering AB. 18-8 Martin D, Cho N, 2001. Contribution to Workshop on Rock-Backfill interaction. Äspö Hard Rock Laboratory. 18-9 Glamheden R, Hökmark H, Cristiansson R, 2001. Preliminary Results from 3DEC Modelling of a Deposition Tunnel in a KBS-3 type Repository. Proceedings from Workshop on Backfill Requirements for a KBS-3 type Repository. Äspö Hard Rock Laboratory. 18-10 Larsson H, Kenne A, Edelsvärd Ch, 1997. Främmande material i djupförvaret. Tillförsel och fördelning i deponeringsområdena för kapslar. SKB PR D-97-06, Svensk Kärnbränslehantering AB. 18-11 Jones C, Christiansson Å, Wiborgh M, 1999. Främmande material i ett djupförvar för använt kärnbränsle. SKB R-99-72, Svensk Kärnbränslehantering AB. Chapter 19 19-1 Hökmark H, Fälth B, 2003. Thermal dimensioning of the deep repository. Influence of canister spacing, canister power, rock thermal properties and nearfield design on the maximum canister surface temperature. SKB TR-03-09, Svensk Kärnbränslehantering AB. 19-2 Sundberg J, 2002. Determination of thermal properties at Äspö HRL. Comparison and evaluation of methods and methodologies for borehole KA2599 G01. SKB R-02-27, Svensk Kärnbränslehantering AB. 19-3 Sundberg J, Kukkonen I, Hälldahl L, 2003. Comparison of thermal properties measured by different methods. SKB R-03-18, Svensk Kärnbränslehantering AB. 344 RD&D-Programme 2004
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Technical Report TR-04-21 RD&D-Prog
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Preface SKB, Svensk Kärnbränsleha
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welding and nondestructive testing
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Alternative methods. SKB is followi
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5.5 Nondestructive testing of canis
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15 Fuel 163 15.1 Initial state in f
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18.1.10 Swelling pressure 229 18.1.
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Part I SKB’s programme and plan o
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Nuclear power plant Clab m/s Sigyn
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Figure 1-2. The Äspö HRL consists
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Figure 1-4. Interior from the Canis
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Siting SKB’s main alternative is
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Transport tunnel KBS-3V Deposition
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2.1 Nuclear fuel programme In Swede
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Encapsulation plant 2003 2004 2005
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2.2 LILW programme Parts of the sys
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environment. The barriers can also
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this cooperation entails that the o
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4 Overview - technology development
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4.7 Design of the deep repository T
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Diameter 1,050 Diameter 949 Diamete
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Conclusions in RD&D 2001 and its re
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Figure 5-3. Graphite shapes in cast
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Figure 5-5. Positions for test bars
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Programme The development project c
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Programme Trial fabrication of all
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The technology and procedures for c
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A method and equipment based on las
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Spacer plate Defect A Defect B Chan
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Newfound knowledge since RD&D 2001
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2004 2005 Process model welding met
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6.2.2 The welding process In parall
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Figure 6-9. Lid weld L028. Section
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Tensile test bars have been taken o
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6.3.3 The welding process The param
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A limitation in the evaluation of t
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Nondestructive testing methods such
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a b Through-transmission Reflection
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simulation program, and the body of
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SKB has devised a quality system fo
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8 Canister - encapsulation The desi
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Figure 8-2. Work stations in the en
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The filled canister transport casks
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Stages encapsulation plant 2003 200
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Figure 8-4. Possible location of a
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9 Transportation of encapsulated fu
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9.3 SKB’s transportation system -
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absorbs neutron radiation. The lid
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Applicable international and Swedis
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een specified yet. Since the size o
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• Methods exist for full-face dri
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Programme SKB keeps track of curren
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Judgement with regard to long-term
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Furthermore, it must not have an ad
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Studies of equipment will be conduc
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A third type of seal is intended to
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10.6.1 Requirements and premises In
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the long-term safety of the concept
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11.3 Execution - stepwise design Si
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Programme Design step D, which incl
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12 Deep repository - monitoring SKB
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• Trigger levels for action. •
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Part III Safety assessment and rese
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As a complement to the numerical mo
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Table 13-2. Research on the initial
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13.2.4 Backfill Together with Posiv
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Table 13-3. Projects and experiment
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spent nuclear fuel. It was neverthe
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concepts or whose descriptions requ
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14.2.2 Radionuclide transport and d
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At present, the computational time
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Inflow Nuclides in a soluble phase
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15.1.2 Geometry The deep repository
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7 6 BWR 55 MWd/tU PWR 42 MWd/tU PWR
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15.1.11 Gas composition Conclusions
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15.2.5 Heat transport Dealt with in
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simulating the repository environme
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238 U 237 Np 239 Pu Concentration,
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The catalytic effect of uranium dio
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oxidant consumption in the bulk sol
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The influence of hydrogen peroxide
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A research programme to study cast
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16.2.3 Heat transport No new knowle
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Programme The ongoing experiments w
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Programme Short-term tests aimed at
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Swelling properties The buffer must
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have been performed for some ten co
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17.1.13 Impurity levels Bentonite i
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out when the buffer swells, but our
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These processes have been studied i
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• The gas injection phase will be
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19 9 D=205 d=175 D=172 d=170 D=168
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• Tests of the wetting process cl
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Figure 17-4. Natural redox front in
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These phenomena have been studied b
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17.2.24 Radionuclide transport - ad
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Programme SKB does not consider sor
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18.1.6 Smectite content SKB, togeth
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Programme See section 18.2.2. 18.1.
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The wetting of the backfill from th
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ackfill must have a compression mod
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Programme See section 17.2.17. 18.2
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18.2.23 Radionuclide transport - so
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10 -5 I-129 Release rate (moles/yea
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and the rock matrix, is also crucia
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A thermal model will be constructed
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In a continuation of the super-regi
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A thorough overview has been done o
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The authorities are of the opinion
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19.2.11 Advection/mixing - groundwa
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a so-called Markov-directed Random
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Diffusion measurements in the labor
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Uranium series analyses from clay-
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19.2.18 Microbial processes Conclus
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19.2.20 Colloid formation - colloid
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19.2.23 Methane ice formation Concl
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19.2.26 Integrated modelling - radi
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development that has taken place ha
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20.2 Review of RD&D 2001 Following
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work will continue, particularly in
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2 In Sea (mol) 3 Water Sea (mol/m 3
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The above work will be pursued in c
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certain substances, such as uranium
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In connection with the Safe project
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20.9 International work and dissemi
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the underlying material are current
Page 281 and 282: These reports describe dominant fun
Page 283 and 284: Glacial Permafrost Permafrost Borea
Page 285 and 286: Shoreline displacement has an isost
Page 287 and 288: The hydromechanical modellings that
Page 289 and 290: model that includes these factors a
Page 291 and 292: The salinity of the sea, inland sea
Page 293 and 294: • Public opinion and attitudes -
Page 295 and 296: Socioeconomic impact • Local deve
Page 297 and 298: Previously existing material is bei
Page 299 and 300: • The driving forces behind the d
Page 301 and 302: • Very effective methods for tran
Page 303 and 304: • A subcritical nuclear reactor w
Page 305 and 306: out in Cadarache, France. Hindas an
Page 307 and 308: Important results since 2001 includ
Page 309 and 310: Programme The goal of SKB’s resea
Page 311 and 312: Kasam says that disposal in Very De
Page 313 and 314: 24 Decommissioning The facilities c
Page 315 and 316: SKB is responsible for management a
Page 317 and 318: 25 Low- and intermediate-level wast
Page 319 and 320: 25.2.1 Repository for short-lived L
Page 321 and 322: Programme Work on the design of the
Page 323 and 324: observation is that isosaccharinic
Page 325 and 326: stored so that the material can be
Page 327 and 328: 6-4 Claesson S, 2004. Elektronstrå
Page 329 and 330: Chapter 14 14-1 SKB, 2004. Interim
Page 331: 15-42 Ekeroth E, Jonsson M, 2003. O
Page 335 and 336: 19-29 Hudson J (ed), 2002. Strategy
Page 337 and 338: 19-77 Bath A, Milodowski A, Ruotsal
Page 339 and 340: 20-19 Kautsky U (ed), 2001. The bio
Page 341 and 342: 20-73 Blomqvist P, Jansson P-E, Esp
Page 343 and 344: 20-119 Berggren J, Kyläkorpi L, 20
Page 345 and 346: 23-10 NEA, 2002. Accelerator-driven
Page 347 and 348: SKB’s master plan Appendix A
Page 349 and 350: A1 Introduction A1.1 Background The
Page 351 and 352: generations unnecessarily. Another
Page 353 and 354: Encapsulation plant 2003 2004 2005
Page 355 and 356: facilitated by the fact that the re
Page 357 and 358: A2.3 System design A2.3.1 Fundament
Page 359 and 360: The system analyses will be largely
Page 361 and 362: Two safety reports will therefore b
Page 363 and 364: KBS-3H Basic Design Detailed engine
Page 365 and 366: Time horizon 2017 The current phase
Page 367 and 368: 2003 2004 2005 2006 2007 2008 Phase
Page 369 and 370: In the subsequent phase, verificati
Page 371 and 372: The canister development work will
Page 373 and 374: Deep repository Year 2003 2004 2005
Page 375 and 376: A4.2 Site investigations Site inves
Page 377 and 378: Already in the feasibility study, l
Page 379 and 380: In step D2, the facility descriptio
Page 381 and 382: Table 4. Current situation and prel
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2003 2004 2005 2006 2007 2008 Desig
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Table 5. Continued. Technology issu
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A4.6.1 Siting factors Before priori
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A possible alternative scenario is
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of the NPPs starts, however, long-l
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Between now and 2008, an organizati
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Appendix B Abbreviations Abaqus ACL
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GIA Gis Goldsim Hindas HMC HPF HRL
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PMMA POD Posiva Prism Proper Protot
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ISSN 1404-0344 CM Digitaltryck AB,
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