RD&D-Programme 2004 - SKB

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A1 Introduction 361 A1.1 Background 361 A1.2 Points of departure 362 A2 Programme for spent nuclear fuel 363 A2.1 Overview 363 A2.2 Consultations and environmental impact statement 367 A2.3 System design 369 A2.3.1 Fundamental requirements, design premises 369 A2.3.2 System analysis and optimization 369 A2.3.3 Long-term safety 371 A2.3.4 Horizontal deposition, KBS-3H 373 A3 Encapsulation 376 A3.1 Overview 376 A3.2 Facility design 380 A3.2.1 Encapsulation plant 380 A3.2.2 Canister fabrication 380 A3.3 Canister development 380 A3.3.1 Sealing 380 A3.3.2 Canister components 381 A3.3.3 Fabrication 382 A3.4 Safety assessment 382 A3.5 Qualification 383 A4 Deep disposal 383 A4.1 Overview 383 A4.2 Site investigations 387 A4.2.1 Forsmark 387 A4.2.2 Oskarshamn 388 A4.3 Facility design 389 A4.4 Technology development 394 A4.5 Safety assessment 398 A4.6 Evaluation and site selection 398 A4.6.1 Siting factors 399 A4.6.2 Site selection 400 A4.6.3 Alternative scenarios 400 A5 Programme for low- and intermediate-level waste (LILW) 401 A5.1 Current situation 401 A5.2 Plan 401 A5.2.1 Final disposal – short-lived waste 402 A5.2.2 Interim storage – core components 402 A5.2.3 Extensions at SFR 403 A5.2.4 Final repository for other long-lived waste 403 A6 Management, quality and competence 404 A6.1 Organization and management system 404 A6.2 Meeting future competence needs 405 360 RD&D-Programme 2004
A1 Introduction A1.1 Background The political framework for the current stage of the spent nuclear fuel programme was established by the Government decision in November 2001 regarding SKB’s integrated account of method and site selection (RD&D-K), followed by the concerned municipalities’ decision processes regarding whether or not to participate, completed in April 2002. With the external framework in place, but still with a great deal of planning flexibility within this framework, SKB decided to carry out a review and revision of its programmes and plans. Attention was first directed towards the site investigation phase, i.e. the stage up until the permit applications for the encapsulation plant and the deep repository have been approved. However, in view of the many links, in terms of timing and activities, to longer-term planning and to other parts of the programme, the review was extended to include all of SKB’s activities. The regulatory review of RD&D-Programme 2001 occasioned additional programme revisions. In the review statement regarding RD&D-Programme 2001 which SKI submitted to the Government in March 2002, the Inspectorate called for a document from SKB that would explain more clearly SKB’s plans for the remainder of the spent nuclear fuel programme. As a reason for this request, SKI said that the authorities concerned need to know which regulatory reviews are anticipated over the next ten years and how they depend on each other. This was considered above all necessary for the authorities’ own planning, but also to describe in other contexts how SKB will achieve the goal of a safe final disposal of the nuclear waste. In its review statement on RD&D-Programme 2001, SSI had previously offered similar viewpoints but had given reasons that more emphasized the need to clarify links between SKB’s RD&D activities and the implementation of the nuclear fuel programme so as to better be able to judge whether the research and development described by SKB is appropriate and adequate. In its statement to the Government, SKI recommended that SKB be required to compile the requested material and present it no later than in connection with SKB RD&D-Programme 2004. Based on this, the Government stated in a decision from December 2002 that they “assume that SKB is conducting a dialogue with concerned authorities and municipalities and that an account of SKB’s timetable with associated plan of action concerning a safe final disposal of the nuclear waste will be included in RD&D-Programme 2004”. As has emerged from subsequent consultations and on other occasions, SKB essentially shared the opinions of the authorities regarding the need for clearer plans of action. Against this background, SKB began the work of clarifying and updating its own short- and long-term planning and compiling the material requested by the regulatory authorities. A milestone was passed in the spring of 2003, when the board of SKB decided to revise the timetable for the spent nuclear fuel programme. A similar revision has since been done of the programme for management of low- and intermediate-level waste (LILW). The revised plans have been presented on different consultation occasions. This includes the aforementioned timetable for the whole deep repository project, as well as the planning for encapsulation, the remaining site investigations, and coming system and safety assessments. Figure 1 shows the main features of the long-term plan which SKB is now following. This appendix is the requested plan of action. It presents and comments on SKB’s planning for a safety final disposal of the nuclear waste and other radioactive waste from the Swedish nuclear power plants. The focus lies on the implementation of the spent nuclear fuel programme and the period up to 2008, including timetables, interim goals and links between the different parts of the programme. The LILW programme is described schematically. With regard to ongoing or planned research and development work aimed at making implementation possible, reference is made to the main report. RD&D-Programme 2004 361
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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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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
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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 345 and 346: 23-10 NEA, 2002. Accelerator-driven
Page 347: SKB’s master plan Appendix A
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 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
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PMMA POD Posiva Prism Proper Protot
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ISSN 1404-0344 CM Digitaltryck AB,
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