RD&D-Programme 2004 - SKB

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10-13 Kalbantner P, 2004. Friläggning av en kapsel i full skala. SKB Report, Svensk Kärnbränslehantering AB, (in manuscript). 10-14 SKB, 1992. Project on Alternative Systems Study (PASS). Final report. Svensk Kärnbränslehantering AB. 10-15 SKB, 2000. Förvarsalternativet djupa borrhål. Innehåll och omfattning av FUD-program som krävs för jämförelse med KBS-3-metoden. SKB R-00-28, Svensk Kärnbränslehantering AB. 10-16 SKB, 2000. Systemanalys. Val av strategi och system för omhändertagande av använt kärnbränsle. SKB R-00-32, Svensk Kärnbränslehantering AB. 10-17 Sandstedt H, Pers K, Birgersson L, Ageskog L, Munier R, 2001. Project Jade. Comparison of repository systems. Executive summary of results. SKB TR-01-17, Svensk Kärnbränslehantering AB. 10-18 SKB, 2001. Forsknings-, utvecklings- och demonstrationsprogram för ett KBS-3-förvar med horisontell deponering. SKB R-01-55, Svensk Kärnbränslehantering AB. Chapter 11 11-1 SKB 2004. Deep repository. Underground design premises. Edition D1.1. SKB R-04-60, Svensk Kärnbränslehantering AB. 11-2 SKB, 2004. Preliminary site description Forsmark area – version 1.1. SKB R-04-15, Svensk Kärnbränslehantering AB. 11-3 SKB, 2003. Plan 2003. Costs for management of the radioactive waste products from nuclear power production. Svensk Kärnbränslehantering AB. 11-4 SKB, 2002. Övergripande konstruktionsförutsättningar för djupförvaret i KBS-3-systemet. SKB R-02-44, Svensk Kärnbränslehantering AB. 11-5 Posiva, 2003. Definition of System Requirements for KBS-3H. Deposition of Spent Nuclear Fuel. Working Report 2002-58. Posiva Oy, Finland. 11-6 SKB, 2001. Djupförvar för använt kärnbränsle. Anläggningsbeskrivning – Layout E. Rak ramp med två driftområden. SKB R-01-57, Svensk Kärnbränslehantering AB. 11-7 SKB, 2002. Djupförvar för använt kärnbränsle. Anläggningsbeskrivning – Layout E. Spiralramp med ett driftområde. SKB R-02-18, Svensk Kärnbränslehantering AB. 11-8 SKB, 2002. Djupförvar för använt kärnbränsle. Anläggningsbeskrivning – Layout E. Schaktalternativ med ett driftområde. SKB R-02-19, Svensk Kärnbränslehantering AB. 11-9 Bäckblom G, Christiansson R, Hedin A, Norman F, Lagerstedt L, 2003. Utredning rörande tillträdesvägar till djupförvarets deponeringsområden. Schakt eller ramp? SKB R-03-11, Svensk Kärnbränslehantering AB. Chapter 12 12-1 Bäckblom G, Almén K-E, 2004. Monitoring during the stepwise implementation of the Swedish deep repository for spent fuel. SKB R-04-13, Svensk Kärnbränslehantering AB. 12-2 EU, 2004. Thematic Network on the Role of Monitoring in a Phased Approach to Geological Disposal of Radioactive Waste. Final report to the European Commission Contract FIKW-CT-2001-20130. 12-3 SKB, 2001. Site Investigations. Site investigations – Investigation methods and general execution programme. SKB TR-01-29, Svensk Kärnbränslehantering AB. 12-4 SKB, 2001. Program för platsundersökningar vid Forsmark. SKB R-01-42, Svensk Kärnbränslehantering AB. 12-5 SKB, 2001. Geovetenskapligt program för platsundersökning vid Simpevarp. SKB R-01-44, Svensk Kärnbränslehantering AB. 12-6 Euratom Treaty IAEA, 1988. Advisory group meeting on safeguards for final disposal of nuclear material in waste and spent fuel (AGM-660). STR-243 (Revised) IAEA, Vienna, December. 12-7 IAEA, 1998. SAGOR. Reference Volume for Safeguards for the Final Disposal of Spent Fuel in Geologic Repositories (SAGOR Activities). Report K/NSP-659. 12-8 IAEA, 1997 (corrected), Model protocol additional to the agreement(s) between state(s) and the International Atomic Energy Agency for the application of safeguards. International Atomic Energy Agency, Infcirc/540/. (http://www.iaea.org/Publications/Documents/Infcircs). 12-9 IAEA, 2003. Report on the experts meeting on interface issues and interaction between safeguards and radioactive waste management in the context of geological repositories. STR-38, IAEA, Vienna. Chapter 13 13-1 SKB, 2004. Interim main report of the safety assessment SR-Can. SKB TR-04-11, Svensk Kärnbränslehantering AB. 13-2 SKB, 1999. SR 97 Processes in the repository evolution. Background report to SR 97. Svensk Kärnbränslehantering AB. 13-3 SKB, 2003. Planning report for the safety assessment SR-Can. SKB TR-03-08, Svensk Kärnbränslehantering AB, pp 54–55. RD&D-Programme 2004 339
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
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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
Page 277 and 278: 20.9 International work and dissemi
Page 279 and 280: 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: 6-4 Claesson S, 2004. Elektronstrå
Page 331 and 332: 15-42 Ekeroth E, Jonsson M, 2003. O
Page 333 and 334: 17-19 Le Bell J C, 1978. Colloid ch
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
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In step D2, the facility descriptio
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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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