RD&D-Programme 2004 - SKB

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The important milestones are: • Applying for a permit for siting and construction of the encapsulation plant. • Obtaining a permit for siting and construction. • Applying for a licence for operation of the encapsulation plant. • Obtaining an operating licence. Once a decision has been made on the siting of the encapsulation plant, the following phases are detailed design, construction, installation and commissioning. During the commissioning period, SKB intends to apply for a licence for operation of the encapsulation plant. Time horizon 2008 During the next few years, efforts will be focused on gathering supporting material for an application for a permit for siting and construction of the encapsulation plant, assembling this application and submitting it to the authorities – according to the timetable, in mid-2006. The application will be for a co-siting with Clab. The alternative siting is Forsmark. A prerequisite for siting the encapsulation plant at Forsmark is that the deep repository is also sited there, but even in this case co-siting the encapsulation plant with Clab is SKB’s main alternative. In order for the application to be submitted, the development work must have come so far that encapsulation can be shown to be feasible with safety and reasonable efficiency. Figure 8 shows the implementation plan for this, and also indicates mutual links between activities and important accounting occasions. The main activities during the period are as follows, with the addition of activities besides the technical development work that are required before a permit application can be submitted: • Establish acceptance criteria for canister components and sealing welds. • Refine welding methods for sealing of canisters and choose a main alternative. • Refine and verify methods for nondestructive testing of fabrication and sealing of canisters. • Draw up a plan for qualification. • Fabricate and seal copper canisters on a scale and with a quality that can serve as a basis for the safety assessment that is to accompany the application. • Produce a revised system analysis in which an account of alternative methods for disposal of spent nuclear fuel is given ample space. • Produce a safety assessment (SR-Can) including revisions of methodology and taking into account new findings from the development work regarding encapsulation. • Design an encapsulation plant co-sited at Clab to a level that can serve as a basis for the facility description that is to be included in the application. • Produce supporting material for an encapsulation plant sited at Forsmark to a level that permits a comparison, in accordance with the requirements of the Environmental Code, with the applied-for co-siting with Clab. • Carry out statutory consultations. • Produce an environmental impact statement. • Assemble the application. 378 RD&D-Programme 2004
2003 2004 2005 2006 2007 2008 Phases in canister development Process development Process window Verification Demonstration Account Compilation Regulatory review and possible supplementary work Encapsulation plant Facility design Layout and system documents phase D Final design phase D Application documents Layout and system documents phase C Procurement documention Canister report Canister development Sealing (welding) Development process and machine Parameter studies Choise of welding method Evaluation Welding reports Possible supplementation of permit application Continued welding of copper lids with chosen method Nondestructive testing (NDT) of welds Development of methods and equipment NDT for trial series NDT reports Possible supplementation of permit application Continued NDT of welds Reliability Statistical model Reliability in NDT of welds Background material for SR-Can Components Fabrication technology Fabrication methods at different suppliers and gradual development of methods Fabrication report Verification and demonstration of fabrication methods Verified fabrication methods Safety assessment SR-Can and SR-Site SR-Can interim report SR-Can report SR-Can report SR-Site report Qualification NDT, welding and fabrication Draft of plan for qualification Summarizing account Plan for qualification finished Preparations for qualification, inspection organization Accounts RD&D 2004 Application encapsulation plant RD&D 2007 Application deep repository 2003 2004 2005 2006 2007 2008 Figure 8. Plan for encapsulation, 2003–2008. During the period 2006–2008, the principal emphasis will be on supporting the submitted application with whatever clarifications and supplementary material the authorities may request, to continue working with design and technology development, and to adapt the encapsulation to resource-effective production. A status report on encapsulation is planned in conjunction with the permit application for the deep repository. Granting of a permit entails that the site for the encapsulation plant and the main features of its design are approved. As far as technical optimization on the detailed level and adaptation of the process to resource-effective production are concerned, considerable degrees of freedom will remain even after a siting decision. An example is serial production and assembly of canister components. How this is organized and where it will take place are questions that will be decided later on. RD&D-Programme 2004 379
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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
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 and 364: KBS-3H Basic Design Detailed engine
Page 365: Time horizon 2017 The current 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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