RD&D-Programme 2004 - SKB

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A3 Encapsulation A3.1 Overview Development of the technology for encapsulation is in an intensive phase. The work is now focused on the supporting material for the permit application for the encapsulation plant. After a permit has been granted, the focus will shift to construction, commissioning and trial operation. According to SKB’s timetable, it should be possible to obtain a licence for operation of the encapsulation plant by 2017. The basic requirements on encapsulation are that the canisters to be deposited must be leaktight, possess long-term corrosion resistance in the environment existing in the deep repository, and be able to withstand the loads predicted to arise after deposition. They must be functionally unaffected by the handling chain from sealing to deposition. The work of deriving quantitative requirements regarding material quality and dimensions, as well as tolerances in fabrication and sealing, from these basic requirements has been under way for a long time. Figure 6 is a simplified illustration of the flow in the encapsulation process. There are different methods for fabrication of the canister’s components. In cooperation with suppliers, SKB has refined and tested several methods on a full scale. This work will be pursued further in order to arrive at a finished industrial-scale fabrication process. A key component in the production process is sealing, which takes place directly after fuel assemblies have been placed in the canister. Sealing consists of welding a copper lid on the copper tube that comprises the canister’s outer shell. Extensive development work is required in order to be able to weld with sufficiently high reliability in the relevant materials and thicknesses. SKB is developing two methods – EBW (electron beam welding) and FSW (friction stir welding). In parallel with the development of fabrication and sealing methods, techniques are being developed for quality inspection by means of nondestructive testing. In order to ensure that the quality goals are achieved, a quality assurance system is being developed. The system stipulates quality requirements and how they are to be satisfied and documented. It includes procedures and quality plans, as well as requirements on testing methods and associated acceptance criteria. Methods and suppliers for fabrication, sealing and inspection will be qualified, and a dialogue is being held with SKI regarding the forms for this qualification. Even though the production process is being developed towards the goal of very high reliability, the risk that canisters that fail to satisfy the specifications will nevertheless occasionally be produced and pass the inspection system must be taken into consideration. This risk must be quantified and taken into account in the safety assessments. This quantification will be based on trial production and statistical evaluation of the resulting quality. The risk that a canister will fail to satisfy the specifications is dependent on the reliability of both the welding process and the quality control system. Clab Supplier A Spent nuclear fuel Canister factory Canisters Encapsulation plant Encapsulated nuclear fuel Deep repository Supplier B Figure 6. Overview of the production process. 376 RD&D-Programme 2004
Time horizon 2017 The current phase in the implementation of encapsulation is dominated by development and testing of technology and processes, which will gradually phase into qualification of established systems and procedures. Within a time horizon of 2017, the programme will also undergo design, construction and commissioning phases, after which an operating phase will commence in 2017. Figure 7 shows an implementation plan for encapsulation, up to the start of operation. Encapsulation 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 Encapsulation plant Layout D Main documents Design basis Documentation PSR Construction Rock works SSR Buildings, installations, process equipment Commissioning Components, systems, trial operation Consultations, EIA Early Extended, EIA System analyses Sysdjup Sysinka Safety assessments SR-Site SR-Can Canister development Sealing welding EBW and FSW Verification and demo Sealing welding chosen method Training of personnel Sealing Fabrication methods Fabrication technology Development of methods and design Production system – canisters Fabrication of canisters according to verified method Fabrication of inserts and copper tubes Qualification Programme – NDT, fabrication methods Preparations for qualification Procedures for qualification Genomförande Canister factory Siting, design Construction, installations Commissioning Milestones Permit application encapsulation plant Permit encapsulation plant Operating licence application Initial operation Operating licence 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 Figure 7. Plan for encapsulation, 2003–2018. RD&D-Programme 2004 377
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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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11.3 Execution - stepwise design Si
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Programme Design step D, which incl
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12 Deep repository - monitoring SKB
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• Trigger levels for action. •
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Part III Safety assessment and rese
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As a complement to the numerical mo
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Table 13-2. Research on the initial
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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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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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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
Page 313 and 314: 24 Decommissioning The facilities c
Page 315 and 316: SKB is responsible for management a
Page 317 and 318: 25 Low- and intermediate-level wast
Page 319 and 320: 25.2.1 Repository for short-lived L
Page 321 and 322: Programme Work on the design of the
Page 323 and 324: observation is that isosaccharinic
Page 325 and 326: stored so that the material can be
Page 327 and 328: 6-4 Claesson S, 2004. Elektronstrå
Page 329 and 330: Chapter 14 14-1 SKB, 2004. Interim
Page 331 and 332: 15-42 Ekeroth E, Jonsson M, 2003. O
Page 333 and 334: 17-19 Le Bell J C, 1978. Colloid ch
Page 335 and 336: 19-29 Hudson J (ed), 2002. Strategy
Page 337 and 338: 19-77 Bath A, Milodowski A, Ruotsal
Page 339 and 340: 20-19 Kautsky U (ed), 2001. The bio
Page 341 and 342: 20-73 Blomqvist P, Jansson P-E, Esp
Page 343 and 344: 20-119 Berggren J, Kyläkorpi L, 20
Page 345 and 346: 23-10 NEA, 2002. Accelerator-driven
Page 347 and 348: SKB’s master plan Appendix A
Page 349 and 350: A1 Introduction A1.1 Background The
Page 351 and 352: generations unnecessarily. Another
Page 353 and 354: Encapsulation plant 2003 2004 2005
Page 355 and 356: facilitated by the fact that the re
Page 357 and 358: A2.3 System design A2.3.1 Fundament
Page 359 and 360: The system analyses will be largely
Page 361 and 362: Two safety reports will therefore b
Page 363: KBS-3H Basic Design Detailed engine
Page 367 and 368: 2003 2004 2005 2006 2007 2008 Phase
Page 369 and 370: In the subsequent phase, verificati
Page 371 and 372: The canister development work will
Page 373 and 374: Deep repository Year 2003 2004 2005
Page 375 and 376: A4.2 Site investigations Site inves
Page 377 and 378: Already in the feasibility study, l
Page 379 and 380: In step D2, the facility descriptio
Page 381 and 382: Table 4. Current situation and prel
Page 383 and 384: 2003 2004 2005 2006 2007 2008 Desig
Page 385 and 386: Table 5. Continued. Technology issu
Page 387 and 388: A4.6.1 Siting factors Before priori
Page 389 and 390: A possible alternative scenario is
Page 391 and 392: of the NPPs starts, however, long-l
Page 393 and 394: Between now and 2008, an organizati
Page 395 and 396: Appendix B Abbreviations Abaqus ACL
Page 397 and 398: GIA Gis Goldsim Hindas HMC HPF HRL
Page 399 and 400: PMMA POD Posiva Prism Proper Protot
Page 401: ISSN 1404-0344 CM Digitaltryck AB,
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RD&D-Programme 2004 - SKB

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