RD&D-Programme 2004 - SKB

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16.1.6 Material composition The choice of materials for the insert and the copper shell is based on the design premises. Conclusions in RD&D 2001 and its review No research programme was presented in RD&D 2001. The programme for canister design is presented in Chapter 5. Newfound knowledge since RD&D 2001 No new knowledge has been forthcoming. Programme The field is judged today not to require any further research, development or demonstration. New developments are being monitored and will be acted on when appropriate. 16.2 Canister processes 16.2.1 Overview of processes Some of the radiation that penetrates out to the canister is converted to thermal energy by attenuation in the canister materials. Heat transport takes place by conduction within the insert and canister and, to a large extent, by radiation between these two parts. The insert and the canister can be deformed mechanically by external loads. Furthermore, thermal expansion occurs, causing changes in the cavity between insert and canister. An important chemical process is external copper corrosion, but stress corrosion cracking (SCC) might also occur in both copper canister and cast iron insert. The materials could be altered by radiation. If water enters, the cast iron insert will corrode, accompanied by the formation of hydrogen gas and galvanic corrosion. Radionuclide transport in the canister cavity is dealt with in section 15.2.8. The research programme for the different processes in the canister is dealt with in the following sections. 16.2.2 Radiation attenuation/heat generation The physical processes concerned here (radioactive decay and absorption of radiation) are well-known and sufficient data are available for the safety assessment. Conclusions in RD&D 2001 and its review No research programme was presented in RD&D 2001. Newfound knowledge since RD&D 2001 No new knowledge has been forthcoming. Programme As was stated in RD&D 2001, the field is not judged to require any further research, development or demonstration. RD&D-Programme 2004 185
16.2.3 Heat transport No new knowledge has been forthcoming. The process is dealt with as in RD&D 2001, i.e. integrated with the temperature evolution of the fuel, see section 15.1.4. 16.2.4 Deformation of cast iron insert Deformation of the cast iron insert could theoretically occur in conjunction with large tectonic movements. Conclusions in RD&D 2001 and its review SKI says it is urgent that SKB carry out new calculations of the mechanical strength of the canister, where all components are reconsidered, such as: • Actually obtained material data from fabricated inserts. • Updated material data for bentonite. • Loads during glaciation (consistent with scenario selection). • Defined permissible defects (from the consequence analysis). • Failure criteria in connection with shear movements. Newfound knowledge since RD&D 2001 With updated material data for bentonite, earthquake-induced rock shear calculations have been carried out for the canister with insert /16-2/. The rock shear has been modelled and calculated with the finite element code Abaqus. A three-dimensional finite element mesh that models the buffer and the canister has been created and a number of calculations that simulate different rock shears have been performed. The rock shear is assumed to take place perpendicular to the canister axis either in the centre of the deposition hole or at the quarter point. The shear calculations have been driven to a total shear of 20 centimetres. The buffer has been modelled at four densities between 1,950 and 2,100 kg/m 3 at water saturation and at shear rates between 0.0001 and 1,000 mm/s. The results show that the influence of especially the density of the buffer and the location of the shear plane are very strong, but also that the shear rate and the magnitude of the shear displacement have a significant influence. At the two lower densities an eccentric shear plane is more dangerous, but at the two higher densities a centric shear is worst. At the conservative combination of a shear rate of 1 m/s, a shear displacement of 20 centimetres and a density of 2,100 kg/m 3 , the cast iron insert is strongly affected with a maximum plastic strain of 19 percent, but in the reference case with a buffer density of 2,000 kg/m 3 and a shear displacement of 10 centimetres, the plastic strain is reduced to 1.6 percent. Programme A large programme for probabilistic analysis of canister strength was started during 2003. In this programme we are obtaining material data from fabricated canisters. Pressure testing of canister sections is also included in the programme. According to the plans, this programme will be concluded during 2004. 16.2.5 Deformation of copper canister under external pressure Conclusions in RD&D 2001 and its review SKI recommends that SKB show how a simplification of the model for deformation of the copper canister affects the results. The simplification entails assuming plastic collapse instead of creep. 186 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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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 and 152: At present, the computational time
Page 153 and 154: Inflow Nuclides in a soluble phase
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 175: Newfound knowledge since RD&D 2001
Page 179 and 180: Programme The ongoing experiments w
Page 181 and 182: Newfound knowledge since RD&D 2001
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
Page 193 and 194: out when the buffer swells, but our
Page 195 and 196: These processes have been studied i
Page 199 and 200: • The gas injection phase will be
Page 205 and 206: 19 9 D=205 d=175 D=172 d=170 D=168
Page 207 and 208: • Tests of the wetting process cl
Page 211 and 212: Figure 17-4. Natural redox front in
Page 213 and 214: These phenomena have been studied b
Page 215 and 216: 17.2.24 Radionuclide transport - ad
Page 217 and 218: Programme SKB does not consider sor
Page 219 and 220: 18.1.6 Smectite content SKB, togeth
Page 221 and 222: Programme See section 18.2.2. 18.1.
Page 223 and 224: 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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