RD&D-Programme 2004 - SKB

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13.3.2 Decision processes By gaining greater knowledge of political decision processes in complex issues, SKB hopes to obtain guidance on how to carry out consultations, conduct studies, plan and decide on the siting of a deep repository. 13.3.3 Psychosocial effects The research on psychosocial effects will find out how public opinion and attitudes are created and changed in the different phases of the deep repository project. Such knowledge will hopefully increase understanding between the stakeholders and contribute positively to the consultations. 13.3.4 Global changes Research on global changes is intended to increase our knowledge of what factors and changes in the world around us are of importance for the deep repository project and the community which is eventually chosen to host it. This knowledge can be valuable in making plans, conducting studies, carrying out consultations and making decisions leading up to an application for a permit to site a deep repository. 13.4 Alternative methods SKB’s research when it comes to alternatives to KBS-3 is concentrated on two methods: Partitioning and Transmutation (P&T) and Very Deep Holes (VDH). The programmes are described in greater detail in Chapter 23. The following sections provide only a brief sketch. 13.4.1 Partitioning and transmutation (P&T) SKB continues to support research on P&T. If this method becomes reality one day, it would be one way to reduce the content of long-lived radionuclides in the waste while extracting more energy in the bargain. Sweden does not have the resources to pursue such development work on its own; international cooperation would be required, or the commitment of a major power. If P&T is implemented in the future and plants for it are built in some country, and if their services are made available, we must ask what it would cost and what waste products we would get back. But so far everything is in the basic research stage, and SKB’s policy is to monitor international developments in the field. SKB supports research on Partitioning and Transmutation at the Royal Institute of Technology (KTH) in Stockholm, Uppsala University and Chalmers University of Technology (CTH) in Gothenburg. The researchers there are engaged in a number of EU projects, where they can participate in the international work in the field. The amount of funding given by SKB to this research in Sweden is sufficient to ensure adequate breadth and scope. To participate in the international development work, competent partners must be provided as well as facilities in the country where research is conducted at an acceptable level. A detailed account of SKB’s research programme in the field of Partitioning and Transmutation is provided in section 23.1. 13.4.2 Very Deep Holes (VDH) The idea of disposing of high-level waste in very deep holes has been around for more than 20 years, and SKB looked into the possibility of disposing of spent fuel in this manner in the early 1990s. Further studies have been conducted since then without any obvious advantages being found – rather the contrary. The conclusion in RD&D 2001 was that there was no evidence to suggest that VDH would increase safety or reduce the cost of disposing of the RD&D-Programme 2004 153
spent nuclear fuel. It was nevertheless decided that SKB would continue to keep track of developments in the field. One reason for this was so that the results and experience gained would also provide valuable geoscientific knowledge for a KBS-3 repository at a depth of about 500 metres. Data from investigations in boreholes several kilometres deep that have been published since SKB’s most recent literature reviews have been compiled and evaluated. The results are presented briefly in section 23.2. It can be concluded that nothing has emerged to change the judgement made in RD&D 2001, but it may nonetheless be worthwhile to continue to follow the geoscientific investigations of conditions at depths of several kilometres in the rock, for the same reason as before. 154 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
Page 93 and 94: Stages encapsulation plant 2003 200
Page 95 and 96: Figure 8-4. Possible location of a
Page 97 and 98: 9 Transportation of encapsulated fu
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Page 101 and 102: absorbs neutron radiation. The lid
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Page 105 and 106: een specified yet. Since the size o
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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: Table 13-3. Projects and experiment
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 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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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
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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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