RD&D-Programme 2004 - SKB

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Newfound knowledge since RD&D 2001 Uppsala University has measured the thermal emittance of a small number of copper specimens taken from those parts of the canister which have undergone all the steps in the fabrication process, including the sealing weld. Despite the fact that the welds exhibited oxidation clearly visible to the eye, the emissivity in the infrared range was low (0.06–0.11). The values are not expected to change during the time it takes to achieve full water saturation in the buffer in the deposition hole. After full water saturation, the thermal emittance is of no importance. 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. 15.1.5 Hydrovariables The hydrovariables – i.e. water pressures, water flows and gas flows – are not relevant to describe initially, since the canister is assumed to be intact. 15.1.6 Mechanical stresses Conclusions in RD&D 2001 and its review Some activities are planned within the framework of the EU project SFS, in which SKB is also participating, see section 15.1.2. No direct viewpoints were offered in the review. 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. 15.1.7 Total radionuclide inventory Conclusions in RD&D 2001 and its review SKI has called for a validation of calculation models for certain nuclides (for example 36 Cl, 79 Se and 126 Sn) as well as an account of the importance of other burnups and fuel types, for example Mox fuel. SKI also requests an account of the total inventory of radionuclides as a function of time and space in all parts of the fuel assembly. Newfound knowledge since RD&D 2001 In SR 97, radionuclide inventories were calculated for burnups of 38 and 55 MWd/kgU for BWR fuel and 42 and 60 MWd/kgU for PWR fuel. The uncertainties in the calculations were discussed in /15-4/. In the calculations for SR 97, however, only inventories from BWR fuel with a burnup of 38 MWd/kgU were used. The differences in nuclide inventory with respect to burnup are often small. Figure 15-1 shows the inventory of radionuclides for different burnups (normalized to BWR 38 and corrected for decay heat). Table 15-2 shows a comparison of the calculated inventories of radionuclides in SR 97 in the Swiss Project Opalinus and the Belgian Safir-2. It is clear from the data that neither assumed burnup nor calculation tool has any decisive influence on the calculated inventory. RD&D-Programme 2004 165
7 6 BWR 55 MWd/tU PWR 42 MWd/tU PWR 60 MWd/tU 5 4 3 2 1 0 C-14 Ni-59 Nb-94 Np-237 U-238 Pu-239 Pu-240 Am-241 Cm-245 Tc-99 Sn-126 I-129 Cs-135 Figure 15-1. Inventory of radionuclides normalized to BWR 38 and corrected for decay heat 30 years after removal from reactor. Table 15-2. Comparison of calculated inventories (SKB’s values are interpolated). Nuclide Nagra SKB Safir PWR-48 PWR-48 PWR-45 14 C 6.40 10 10 4.20 10 10 1.93 10 10 36 Cl 1.10 10 9 1.16 10 9 2.75 10 9 60 Co 4.70 10 11 2.97 10 12 59 Ni 8.00 10 10 1.52 10 11 1.60 10 11 63 Ni 8.50 10 12 1.70 10 13 1.75 10 13 79 Se 3.38 10 9 2.04 10 10 85 Kr 1.70 10 14 3.20 10 13 90 Sr 1.40 10 15 1.36 10 15 1.06 10 15 99 Tc 7.00 10 11 6.75 10 11 6.29 10 11 129 I 1.70 10 9 1.73 10 9 1.61 10 9 135 Cs 2.50 10 10 2.19 10 10 2.17 10 10 137 Cs 2.20 10 15 2.27 10 15 1.62 10 15 230 Th 2.20 10 7 5.42 10 6 232 U 1.30 10 8 234 U 6.40 10 10 4.98 10 10 2.17 10 10 235 U 6.90 10 8 4.80 10 8 5.64 10 8 238 U 1.10 10 10 1.15 10 10 1.17 10 10 237 Np 2.00 10 10 2.05 10 10 1.97 10 10 238 Pu 1.50 10 14 1.65 10 14 1.21 10 14 239 Pu 1.40 10 13 1.30 10 13 1.34 10 13 240 Pu 2.30 10 13 1.74 10 13 2.17 10 13 241 Pu 9.40 10 14 1.09 10 15 5.86 10 14 242 Pu 1.10 10 11 1.48 10 11 1.11 10 11 241 Am 1.80 10 14 2.12 10 14 1.95 10 14 242 Cm 3.30 10 11 4.21 10 11 244 Cm 4.80 10 13 1.00 10 14 3.25 10 13 166 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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Page 109 and 110: Programme SKB keeps track of curren
Page 111 and 112: Judgement with regard to long-term
Page 113 and 114: Furthermore, it must not have an ad
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 and 152: At present, the computational time
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Page 155: 15.1.2 Geometry The deep repository
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
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 203 and 204: Conclusions in RD&D 2001 and its re
Page 205 and 206: 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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