RD&D-Programme 2004 - SKB

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Initially the extended consultations have mainly dealt with the scope of EIA. Preliminary scoping reports have been prepared as a basis for discussion. They deal with what the EIA work should cover and what investigations are planned as a basis for the EIS. Viewpoints and proposals that emerge will be taken into account in the planning of the continued EIA process. The intention is that final versions of the reports will be written during 2004. In the subsequent investigation phase, results from investigations and studies as well as proposals for facility design are presented at the consultation meetings, and the participants are given an opportunity to state their views. This phase continues for as long as investigations, facility design work and studies are pursued, i.e. until the end of 2005 for the encapsulation plant and until 2008 for the deep repository. Figure 4 illustrates the interaction between SKB and other parties in the consultation processes. When the necessary investigations have been completed, a preliminary EIS is compiled. Before the permit application is submitted, SKB intends to verify major conclusions with the concerned consultation parties. The consultation process is concluded when SKB submits permit applications with supporting EISs for licensing under the Nuclear Activities Act and the Environmental Code. A consultation report will be appended to each application. This report will contain a summary of the viewpoints offered and will tell how these viewpoints have been taken into consideration. In addition to the formal consultations, extensive information activities are aimed at municipalities, organizations and the public. These activities will continue to be pursued in parallel with the statutory consultation meetings. CONSULTATION PARTIES Oskarshamn EIA Forum Forsmark Consultation and EIA Group The citizens Local, regional and national actors/organizations Government agencies Other countries Viewpoints preliminary scoping report Viewpoints preliminary EIS Viewpoints preliminary EIS Preliminary scoping report Scoping report Preliminary EIS EIS encapsulation encapsulation Preliminary EIS deep repository EIS deep repository Figure 4. Interaction between SKB and other parties in the consultation processes. 368 RD&D-Programme 2004
A2.3 System design A2.3.1 Fundamental requirements, design premises At a general level, the premises for designing and engineering the management system for spent nuclear fuel are derived from Swedish laws and regulations, other requirements on safety, and SKB’s own and other parties’ requirements on technical feasibility and efficiency. These requirements are as a rule generally formulated and not directly applicable to optimization or more concrete design work. They therefore have to be translated into performance requirements on the system or its parts. Performance requirements mainly apply to safety and radiation protection, other environmental protection, construction and operation, and aspects that derive from international agreements. The design and execution of the facilities must be shown to fulfil all of these requirements under the design-basis stresses and loads. These stresses and loads are determined by analyzing the situations and processes that occur or might occur during construction and operation, and in the case of the deep repository after closure as well. They include e.g. static loads, deformations and movements, corrosion, etc. The work sequence in the waste programme, with regular accountings in the form of RD&D programmes and safety assessments, has entailed a gradual development of the system, accompanied by regular cross-checking with the requirements. In 2002, SKB submitted a status report on the work of preparing design premises, see Chapters 5 and 11 with references. The report covers the entire deep repository system and its parts, and also includes the sequence of derivations that has been gone through to arrive at a useful design basis from general requirements. The degree of precision and quantification provided by the report for the parameters, loads etc that govern design and execution corresponds to the status of the work at the time of the report. A2.3.2 System analysis and optimization The overall strategy for designing and optimizing a repository system according to the KBS-3 concept has been presented in many contexts, most recently in RD&D-Programme 2001. The principle is to gradually work out, in defined steps, an increasingly detailed design of the facilities, requisite infrastructure and technical supply systems. Execution of construction and operation are more precisely defined in the same way. As the design becomes increasingly detailed, decisions are made which narrow down the range of options, first for general system selection, then for technical solutions for facilities and subsystems, and finally for the details. This mode of working has been successfully applied in many industrial projects, including SFR, Clab and the NPPs. Decisions and choices during the course of the process are made systematically by producing possible alternatives and evaluating them against established requirements or other criteria with regard to: • Post-closure safety and performance. • Safety during construction and operation. • Environment. • Feasibility and efficiency. • Resource needs. Final choices of system and technology solutions will be made as late as possible to in order to take full advantage of technical advances and, in some cases, site-specific data as well. However, the decisions must not be delayed so much that the development of other parts of the system is held back or otherwise impaired by unclear premises. Striking a balance between the advantages of retaining freedom of choice on the one hand and the need to drive the design process towards the final goal at a reasonable pace on the other hand is a central consideration in SKB’s strategic planning. RD&D-Programme 2004 369
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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
Page 305 and 306: out in Cadarache, France. Hindas an
Page 307 and 308: Important results since 2001 includ
Page 309 and 310: Programme The goal of SKB’s resea
Page 311 and 312: 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: facilitated by the fact that the re
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 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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