RD&D-Programme 2004 - SKB

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• An encapsulation plant co-sited with Clab is planned. Design of the plant is under way and development of the encapsulation technology is proceeding. As an alternative, a siting at a deep repository in Forsmark will be examined. • Two candidate sites are being investigated for the siting of the deep repository: Forsmark in the municipality of Östhammar and Simpevarp/Laxemar in the municipality of Oskarshamn. These sites were prioritized after a decision process based on broad information gathered from general siting studies and feasibility studies. The intention is that one of the candidate sites will be chosen later on as the site of the deep repository. • The selection pool for siting of the deep repository that is currently available also includes other sites that remain as possible alternatives, in the event the investigations of the candidate sites do not yield satisfactory results. Furthermore, a large body of comparison material is available from the study site investigations conducted previously at some ten sites in various parts of the country, as well as from investigations in the Finnish nuclear waste programme. • Both the encapsulation plant and the deep repository require permits under the Environmental Code and the Nuclear Activities Act. Statutory consultation procedures for this have been commenced, and the coming decision processes are well defined. On this basis, SKB has updated the plans of action for the remainder of the programme. The main goal is to be able to put the entire system, including the remaining facilities, into operation. The more immediate goal is to obtain the permits needed to establish the encapsulation plant and the deep repository. Time horizon 2017 The current timetable for the two remaining nuclear facilities in the programme, up to the start of operation of the entire system, is shown in Figure 2. The plan has been revised slightly compared with the one presented in RD&D-Programme 2001. It shows the best estimate SKB can make at the present time. A prerequisite for implementation is that the broad political support enjoyed by the deep repository programme today is sustained. It is projected that the waste management system, including an initial stage of the deep repository, will be able to be put into operation in 2017. The initial operating phase includes 200–400 canisters, and is intended to serve as a final trial and demonstration of the method. Initial operation will last for several years and be evaluated before a decision is made whether or not to proceed to regular operation of the system. If the evaluation provides support for a transition to regular operation, the latter can be commenced almost immediately. How long regular operation then needs to continue is directly dependent on the operating times of the NPPs. SKB’s planning assumption is that all reactors except Barsebäck 1 (shut down in November 1999) are operated for 40 years. With an average deposition pace of about 160 canisters per year, this would mean that the deep repository would continue to operate until the early 2050s and that the whole programme could be wound up in around 2060. The capacity requirement for the deep repository system at full operation is set at 200 canisters per year. At the end of 2003, just over 4,000 tonnes of spent nuclear fuel were in interim storage at Clab. Plans call for the completed extension to Clab to be commissioned in the autumn of 2004. The space that will thereby be freed for interim storage is judged to be sufficient for the needs of the entire nuclear fuel programme, provided that the system for encapsulation and deep disposal becomes available according to the timetable in Figure 2. If this is delayed, an additional extension of Clab may be necessary. Time horizon 2008 The goal for the period up to the end of 2008 is to be able to submit permit applications for the system’s remaining two nuclear facilities. Crucial prerequisites for being able to realize this goal are: 364 RD&D-Programme 2004
Encapsulation plant 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 SKB Application KTL, MB PERMIT Application KTL PERMIT Safety assessments SR-Can Consultations, EIA Design Draft documents (Stage D) Authorities Government Municipality Deep repository 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 SKB Site investigations Oskarshamn, Forsmark Safety assessments Preliminary evaluations APPLI- CATION Main documents Application KTL, MB Evaluation SR-Site PERMIT Engineering documents Construction Rock Buildings Installations Commissioning Trial operation APPLI- CATION Application KTL Documentation PERMIT Initial operation Initial operation Consultations, EIA Design Draft documents (Stage D) Main documents Engineering documents Documentation Authorities Government Municipality APPLI- CATION Construction, detailed characterization Rock Buildings Installations Commissioning Trial operation APPLI- CATION Figure 2. Timetable for the encapsulation plant and the deep repository, 2003–2017. • Application for a permit to build an encapsulation plant assumes co-siting at Clab. If the Clab siting is rejected as the main alternative, the timetable must be revised. The secondchoice alternative is a siting at Forsmark, which assumes that the deep repository is also located on this site. • The initiated site investigations for the deep repository can largely be carried out within the planned timeframe (by the middle of 2007), and with results favourable enough to warrant an application for a permit to build the deep repository on one of the sites. An outcome where additional candidate sites for the deep repository must instead be added to the siting programme would require revision of the timetable. RD&D-Programme 2004 365
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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
Page 301 and 302: • Very effective methods for tran
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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
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: generations unnecessarily. Another
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
Page 399 and 400: PMMA POD Posiva Prism Proper Protot
Page 401: ISSN 1404-0344 CM Digitaltryck AB,
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