RD&D-Programme 2004 - SKB

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Q3 Tunnel Crushed rock - bentonite Canister Bentonite Q2 Disturbed zone Damage (hole) Rock Deposition hole Fuel Q1 Bentonite Channel Canister wall Fracture zone Q4 Figure 14-4. Schematic view of the near-field, with the transport pathways used in SR 97. Figure 14-4 shows how the deposition holes and the backfill in the deposition tunnel were modelled in SR 97. In the model, four different flow paths, Q1–Q4, were used for the interface between near-field and far-field. To represent the barrier system through which radionuclides are transported, Comp23 makes use of an integrated finite difference method and the compartment concept. The far-field model The far field model for SR-Can is similar to the one used in SR 97. This model, Farf31, /14-8/ calculates the transport of dissolved radionuclides through fractured rock, the retention caused by interactions between the nuclides and the rock matrix, and radioactive chain decay. The biosphere model Radionuclide transport through the biosphere and doses to man were handled in SR 97 by the Proper sub-module Bio42. This module was based on nuclide- and ecosystem-specific dose conversion factors (EDFs), which convert nuclide releases to an ecosystem into doses. In SR 97, the EDFs for the six ecosystems considered (well, lake, river, peat, soil, coast) were calculated in a separate code /14-10/ using generic data for the ecosystem parameters. The different ecosystems were represented by compartment models where each compartment corresponded to a distinct part of an ecosystem. Figure 14-5 shows the example of a peat bog modelled as two compartments, representing nuclides dissolved in water and nuclides sorbed to organic and/or solid material, respectively. The nuclide exchange between the two compartments was modelled using ecosystem- and element-specific distribution coefficients (Kd). In the modelled peat bog, Figure 14-5, both nuclide inflow and outflow take place in the soluble phase and are therefore controlled by the water balance. Depending on the water exchange at the studied site, in- and outflow may take place to other ecosystem models, inflow may take place from release points from the geosphere’s streamtubes, or outflow of nuclides may take place from the model domain. However, in SR 97, only single ecosystems were considered with inflow only from release points from streamtubes. RD&D-Programme 2004 161
Inflow Nuclides in a soluble phase Outflow Nuclide flow between the phases Nuclides in a solid/organic phase Figure 14-5. Compartment model of a peat bog. In SR-Can the site will be better known and the basis for modelling the ecosystem and interactions between different ecosystems will be improved. Figure 14-6 shows how a downstream nuclide transport can be handled in the biosphere model if the water flow at the site is known. In the sketch, nuclides are assumed to enter a peat bog, which can be modelled as indicated in Figure 14-6, via the groundwater. The radionuclide outflow from this model is shown as inflow to, for instance, a running water model and later to a lake model etc. In contrast to the models used in SR 97, humans may be exposed to nuclides from all modelled ecosystems at the same time, for example to radionuclides from peat combustion, irrigation of agricultural land by stream water and consumption of aquatic foodstuff from a lake. The biosphere calculations in SR 97 were performed in a separate code and imported to the Proper package as probability distributions. In SR-Can, the biosphere transport calculation will be performed in the Matlab/Simulink version of the safety assessment code. Biosphere simulations can either be performed as part of a probabilistic computational chain or separately with nuclide releases taken from each realization of the near- and far-field modules. EDFs will also be calculated in SR-Can. As a complement to the compartment-based biosphere models used in SR 97, work is under way to implement so-called process models in the biosphere simulation tool, see section 20.4. These models are based on considerations of energy and nutrition balances and can also be used to generate input data to the compartment models. By using the Matlab/Simulink package for simulation, it is possible to use these models in combination with previously existing compartment models and thereby perform more complex simulations. Inflow from the far field model Peat bog Running water Lake Figure 14-6. Coupling of biosphere modules for radionuclide transport. 162 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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Page 111 and 112: Judgement with regard to long-term
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Page 115 and 116: Studies of equipment will be conduc
Page 117 and 118: A third type of seal is intended to
Page 119 and 120: 10.6.1 Requirements and premises In
Page 121 and 122: the long-term safety of the concept
Page 123 and 124: Newfound knowledge since RD&D 2001
Page 125 and 126: Conclusions in RD&D 2001 and its re
Page 127 and 128: 11.3 Execution - stepwise design Si
Page 129 and 130: Programme Design step D, which incl
Page 131 and 132: 12 Deep repository - monitoring SKB
Page 133 and 134: • Trigger levels for action. •
Page 135 and 136: Part III Safety assessment and rese
Page 137 and 138: As a complement to the numerical mo
Page 139 and 140: Table 13-2. Research on the initial
Page 141 and 142: 13.2.4 Backfill Together with Posiv
Page 143 and 144: Table 13-3. Projects and experiment
Page 145 and 146: spent nuclear fuel. It was neverthe
Page 147 and 148: concepts or whose descriptions requ
Page 149 and 150: 14.2.2 Radionuclide transport and d
Page 151: At present, the computational time
Page 155 and 156: 15.1.2 Geometry The deep repository
Page 157 and 158: 7 6 BWR 55 MWd/tU PWR 42 MWd/tU PWR
Page 159 and 160: 15.1.11 Gas composition Conclusions
Page 161 and 162: 15.2.5 Heat transport Dealt with in
Page 163 and 164: simulating the repository environme
Page 165 and 166: 238 U 237 Np 239 Pu Concentration,
Page 167 and 168: The catalytic effect of uranium dio
Page 169 and 170: oxidant consumption in the bulk sol
Page 171 and 172: The influence of hydrogen peroxide
Page 173 and 174: A research programme to study cast
Page 177 and 178: 16.2.3 Heat transport No new knowle
Page 179 and 180: Programme The ongoing experiments w
Page 183 and 184: Programme Short-term tests aimed at
Page 185 and 186: Swelling properties The buffer must
Page 189 and 190: have been performed for some ten co
Page 191 and 192: 17.1.13 Impurity levels Bentonite i
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Page 195 and 196: These processes have been studied i
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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
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These reports describe dominant fun
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Glacial Permafrost Permafrost Borea
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Shoreline displacement has an isost
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The hydromechanical modellings that
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model that includes these factors a
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The salinity of the sea, inland sea
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• Public opinion and attitudes -
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Socioeconomic impact • Local deve
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Previously existing material is bei
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• The driving forces behind the d
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• Very effective methods for tran
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• A subcritical nuclear reactor w
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out in Cadarache, France. Hindas an
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Important results since 2001 includ
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Programme The goal of SKB’s resea
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Kasam says that disposal in Very De
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24 Decommissioning The facilities c
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SKB is responsible for management a
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25 Low- and intermediate-level wast
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25.2.1 Repository for short-lived L
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Programme Work on the design of the
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observation is that isosaccharinic
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stored so that the material can be
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6-4 Claesson S, 2004. Elektronstrå
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Chapter 14 14-1 SKB, 2004. Interim
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15-42 Ekeroth E, Jonsson M, 2003. O
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17-19 Le Bell J C, 1978. Colloid ch
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19-29 Hudson J (ed), 2002. Strategy
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19-77 Bath A, Milodowski A, Ruotsal
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20-19 Kautsky U (ed), 2001. The bio
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20-73 Blomqvist P, Jansson P-E, Esp
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20-119 Berggren J, Kyläkorpi L, 20
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23-10 NEA, 2002. Accelerator-driven
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SKB’s master plan Appendix A
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A1 Introduction A1.1 Background The
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generations unnecessarily. Another
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Encapsulation plant 2003 2004 2005
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facilitated by the fact that the re
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A2.3 System design A2.3.1 Fundament
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The system analyses will be largely
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Two safety reports will therefore b
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KBS-3H Basic Design Detailed engine
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Time horizon 2017 The current phase
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2003 2004 2005 2006 2007 2008 Phase
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In the subsequent phase, verificati
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The canister development work will
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Deep repository Year 2003 2004 2005
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A4.2 Site investigations Site inves
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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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RD&D-Programme 2004 - SKB

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