RD&D-Programme 2004 - SKB

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As is evident from Figure 10, the work during the site investigation phase is iterative. The current stage is called initial site investigation and is projected to be completed in the spring of 2005. The goal of this phase is to verify the judgement that warranted the choices of candidate sites, i.e. that they have good prospects for meeting the requirements for a deep repository. Collected data concerning conditions on the site are compared with pre-established criteria. Furthermore, the possible configuration of a deep repository with regard to local conditions is studied, and preliminary evaluations are made of the safety of such a repository. Provided the results confirm the continued viability of the siting alternative, the second stage of the plan (called complete site investigation) is implemented. The purpose then is to gather information to a level that permits an application to be submitted. 2003 2004 2005 2006 2007 2008 Phases of site investigation Initial site investigation (ISI) and complete site investigation (CSI) Forsmark Oskarshamn Simpevarp Laxemar Site description V 1.1 Site description V 1.1 Data freeze 1 Site description V 1.2 Site description V 1.2 Site description V 1.1 Prioritization Oskarshamn Site description V 1.2 Site description V 2.1 Site description V 2.1 Site description V 2.2 prel. Site description V 2.2 prel. Site description V 2.2 approved Site description V 2.2 approved Phases of design D0 D1 D2 Forsmark Oskarshamn Simpevarp Laxemar Fazility description D0 Layout D1 Layout D1 Fazility description D1 Layout D1 Fazility description D1 Fazility description D1 Layout D2 Layout D2 Fazility description D2 prel. appr. Fazility description D2 prel. appr. Phases of safety assessment Planning methods SR-Can SR-Site Forsmark Oskarshamn Simpevarp Laxemar Safety evaluation Safety evaluation Safety evaluation Safety assessment SR-Site prel. appr. Safety assessment SR-Site prel. appr. Evaluation Evaluation Accounts RD&D 2004 Application encapsulation plant RD&D 2007 Application deep repository 2003 2004 2005 2006 2007 2008 Figure 10. Main activities during the site investigation phase and mutual links between them. 386 RD&D-Programme 2004
A4.2 Site investigations Site investigations are now being conducted in two municipalities, Oskarshamn and Östhammar. The work is divided into two stages: initial and complete site investigation. Following the initial stage, an evaluation is made which includes a preliminary safety evaluation where the findings are cross-checked against the requirements made on the rock. If it turns out that any site does not meet the requirements, the site investigation can be discontinued at this stage. SKB’s planning assumption is, however, that the site investigations will be completed in both municipalities. A4.2.1 Forsmark The site investigation in Forsmark pertains to an approximately 10 km 2 area extending southeast from the nuclear power plant down towards Kallrigafjärden. The area largely coincides with the extent of a so-called tectonic lens, which is a relatively well-preserved bedrock unit surrounded by zones of highly deformed bedrock. The main arguments for the choice of the area were that the bedrock is judged to be favourable, and that it has an advantageous location near the industrial area, SFR and the harbour. The area is situated in a coastal environment with high natural values, which imposes special requirements on both the site investigations and the development of a deep disposal solution on the site. The site investigation was initiated at the beginning of 2002. The organization and the activities were built up and reached full scope during the first year. The current status of the investigation can be summarized as follows: • Characterization of the area’s geological and ecological conditions on the surface has largely been completed. • Five deep cored boreholes (1,000 metres) and a number of shallower percussion boreholes (max. depth about 200 metres) have been completed for investigating the bedrock. • A comprehensive, preliminary site description (version 1.1) has been presented. • The consultation process for a possible deep repository in Forsmark has been commenced. • An active information and communication programme has been established for ongoing dialogue with nearby residents, the public, the municipality and other local stakeholders. The data that have been analyzed so far have led to a focusing of the investigations to the northwestern part of the area. It is not yet possible to make any reliable forecast of the final results. Among other things, the preliminary safety evaluation, based on data after the initial investigation stage, still remains to be done. At present, however, all signs indicate that the site investigation in Forsmark will be completed, and that this will be done in keeping with the timetable in Figure 10. Before the site investigation was initiated, a number of site-specific geoscientific issues were identified as being particularly important to clarify in order to judge the suitability of the site for a deep repository. Table 1 summarizes the current status of these key issues in terms of how well they are understood. Besides issues that are specific for the site, there are numerous factors that are generally important to clarify. These factors include the presence and frequency of dykes and fracture zones, the water flow in these zones and the intervening bedrock, and hydrochemical and thermal conditions. In the case of Forsmark, the general picture is that the bedrock near the surface is characterized by unexpectedly high water flow in distinct structures. This contrasts with conditions at greater depth, which are characterized by homogeneous, fracture-poor bedrock with unexpectedly low water flow. As far as hydrochemical and thermal conditions are concerned, the investigations have not revealed any surprises, which suggests favourable conditions at repository depth. RD&D-Programme 2004 387
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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
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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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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
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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 and 364: KBS-3H Basic Design Detailed engine
Page 365 and 366: Time horizon 2017 The current phase
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: Deep repository Year 2003 2004 2005
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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