RD&D-Programme 2004 - SKB

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Programme Decay heat measurements with the new measurement equipment will be conducted in campaigns. The first measurement campaign on Clab fuel has been initiated. A special database has been established for storage and handling of the large quantities of measurement data. An estimated 15–20 fuel assemblies will be measured each year at Clab. In parallel with the calorimetric measurements, gamma measurements will be performed on the same fuel assemblies. The intention is that the calculated decay heat output can be verified by gamma measurement alone at the time of encapsulation, since calorimetric measurement is a time-consuming and complicated process. The results from each campaign will be evaluated carefully, in close cooperation with both Swedish companies and Oak Ridge National Laboratory (ORNL) in the USA. Since November 2000, SKB has had a cooperation agreement in this area with UT-Battelle, which operates ORNL. An action plan will be prepared to describe what it would entail for the encapsulation process if the verifying measurement of fuel done just before encapsulation were to show large discrepancies in relation to the figures submitted by the nuclear power plant when the fuel was transferred to Clab. It should be noted that encapsulation will continue for a long time after the nuclear power plants have been shut down. The plans of the nuclear power utilities include changes that may affect the fuel’s geometry and source terms. This may affect the facilities and the transportation system. An inquiry has been initiated to develop a long-term strategy for SKB. 8.1.2 Design and application Design of the encapsulation plant is proceeding in steps. The ongoing design step corresponds to the level of detail required in an application for a permit to build a plant. The design of an encapsulation plant at Clab has previously been carried out to this stage /8-2/. The ongoing design process is thus a revision where experience from the Canister Laboratory, changes in the regulatory framework and technical progress are being incorporated in the design. Design is taking place in close cooperation with SKB’s Finnish counterpart Posiva. In order to design the plant, SKB has started a project and contracted a consultant for plant and process design. Design is supplying supporting material for the system part in the preliminary safety report as well as certain references to the report’s general section. Work on the general section is being pursued separately. All safety-related supporting material will also be reviewed independently by an organization with experience from similar nuclear assignments. In parallel with the design of the encapsulation plant, an environmental impact statement (EIS) is being prepared in a process called environmental impact assessment (EIA), an important part of which is consultation with affected parties. In addition to a preliminary safety report and an environmental impact statement, a safety assessment of the long-term safety of the deep repository and a system analysis of KBS-3 will also be appended to the application for a permit to build the encapsulation plant. This is shown in Figure 8-3. 98 RD&D-Programme 2004
Stages encapsulation plant 2003 2004 2005 2006 Application for encapsulation plant Initiation/ procurement Layout D Compilation 2007 2008 Regulatory review and main documents 2009 Application for Permit for encapsulation deep repository plant Facility design Layout and system documents stage D Final design stage D Compilation documents Layout och system documents stage C Procurement documentation Procurement of rock excavation and earthmoving work Preliminary safety report Environmental impact assessment (EIA) System analysis Early consultation Preliminary safety report PSR with reference reports Extended consultation EIS System analysis for encapsulation plant Canister development Canister and welding development Choice of welding method Canister account Continued testing of chosen method Long-term safety assessment SR-Can interim report SR-Can final report Qualification of NDT welding and fabrication Programme for qualification Preparations for qualification 2003 2004 2005 2006 2007 2008 2009 Figure 8-3. Timetable for encapsulation plant. 8.2 Encapsulation plant at deep repository SKB has previously conducted a feasibility study of a standalone encapsulation plant, separate from Clab /8-3/. The plant was then assumed to be situated near the surface part of the deep repository. A prerequisite for siting the encapsulation plant at Forsmark is naturally that the deep repository is also sited there. The primary technical difference between the planned encapsulation plant at Clab and a standalone plant at the deep repository is the way in which the fuel is handled and prepared prior to encapsulation. Fuel reception at the encapsulation plant at the deep repository takes place dry, i.e. no pools are used. The technical solution for fuel reception has been reviewed by two independent international companies with experience of dry handling of fuel assemblies. The existing Clab facility is used for verification measurements, sorting and drying of the fuel before it is transported to the encapsulation plant. This means that parts of Clab must be rebuilt and provided with new equipment. The technical prospects for being able to build an encapsulation plant co-sited with the deep repository are good. Following is a short process description for this siting. The fuel assemblies to be encapsulated are moved from the storage pools via the fuel elevator into Clab’s component pool, where a verifying gamma measurement can be performed. The fuel assemblies have to pass a number of detectors that measure the radiation from the fuel. The fuel is then placed in a transfer canister which, when full, is moved to the service pool. From there the fuel is lifted over to a transport cask. RD&D-Programme 2004 99
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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
Page 41 and 42: Diameter 1,050 Diameter 949 Diamete
Page 43 and 44: Conclusions in RD&D 2001 and its re
Page 45 and 46: Figure 5-3. Graphite shapes in cast
Page 47 and 48: Figure 5-5. Positions for test bars
Page 49 and 50: Programme The development project c
Page 51 and 52: Programme Trial fabrication of all
Page 53 and 54: The technology and procedures for c
Page 55 and 56: A method and equipment based on las
Page 57 and 58: Spacer plate Defect A Defect B Chan
Page 59 and 60: Newfound knowledge since RD&D 2001
Page 61 and 62: 2004 2005 Process model welding met
Page 65 and 66: 6.2.2 The welding process In parall
Page 67 and 68: Figure 6-9. Lid weld L028. Section
Page 69 and 70: Tensile test bars have been taken o
Page 73 and 74: 6.3.3 The welding process The param
Page 75 and 76: A limitation in the evaluation of t
Page 77 and 78: Nondestructive testing methods such
Page 79 and 80: a b Through-transmission Reflection
Page 81 and 82: simulation program, and the body of
Page 83 and 84: SKB has devised a quality system fo
Page 87 and 88: 8 Canister - encapsulation The desi
Page 89 and 90: Figure 8-2. Work stations in the en
Page 91: The filled canister transport casks
Page 95 and 96: Figure 8-4. Possible location of a
Page 97 and 98: 9 Transportation of encapsulated fu
Page 99 and 100: 9.3 SKB’s transportation system -
Page 101 and 102: absorbs neutron radiation. The lid
Page 103 and 104: Applicable international and Swedis
Page 105 and 106: een specified yet. Since the size o
Page 107 and 108: • Methods exist for full-face dri
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 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
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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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Newfound knowledge since RD&D 2001
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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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Conclusions in RD&D 2001 and its re
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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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Conclusions in RD&D 2001 and its re
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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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