RD&D-Programme 2004 - SKB

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Part IV Low- and intermediate-level waste 24 Decommissioning 25 Low- and intermediate-level waste
24 Decommissioning The facilities covered by SKB’s RD&D-programmes are the Swedish nuclear power plants and SKB’s own facilities. When it comes to radioactive waste management, the programmes also include the waste from Studsvik, the Fuel Factory in Västerås, Ranstad, and, last but not least, the Ågesta reactor. The costs for management and disposal of radioactive waste from these suppliers are not covered by the funds allocated to the Nuclear Waste Fund, but are funded and paid separately. SKB’s work for decommissioning of the Swedish nuclear power plants in Oskarshamn, Barsebäck, Ringhals and Forsmark is discussed in the following. 24.1 Planning The timetable for decommissioning of the nuclear power plants has not been finalized. The power companies estimate that the operating time of the reactors could end up being 60 years or more. SKB’s planning and cost estimates in Plan 2004 are based on the assumption that the power plants are operated for about 40 years and are then decommissioned as soon as possible. The final planning for construction, operation and decommissioning of SKB’s facilities is based on the planning at the NPPs. Other facilities are decommissioned so that they fit in chronologically with these plans. They are financed outside of the Financing Act, and not by the Nuclear Waste Fund. The cost of decommissioning a nuclear power plant is updated annually based on the knowledge and experience gained from our own studies and from following international development efforts. A detailed estimate of the decommissioning costs is presented in SKB’s annual Plan report /24-1/. Current situation Owners of nuclear installations are obliged to ensure that the installations are decontaminated and dismantled to a sufficient extent when they have been taken out of service. There are no specific regulations governing this in Sweden today; judgements are made by the regulatory authorities (SSI and SKI) from case to case. There have not yet been any large-scale decommissioning projects in Sweden. As of the closure of Barsebäck unit 1 in 1999, however, planning for a future decommissioning has assumed more concrete forms. The division of responsibility between SKB and its owner companies is such that SKB carries out general decommissioning studies and ensures that the necessary technology and competence exists and that the costs are estimated correctly. The nuclear power utilities take responsibility for the planning, licensing and execution of decommissioning of their own facilities. Management of the waste is coordinated with SKB. SKB keeps track of international developments in the decommissioning field by participating in the decommissioning studies undertaken by international organizations, but also by direct contact with various decommissioning projects that may be of value for planning in Sweden. The experience we have of decommissioning in Sweden today is limited to small research plants that have been decommissioned. The biggest one is the R1 research reactor on Drottning Kristinas väg near KTH in Stockholm. Decontamination and dismantling of the ACL (Active Central Laboratory) in Studsvik is under way, and SKB is learning from this experience. Decommissioning logistics The Swedish NPPs were commissioned during a relatively short span of time. The oldest is from 1972 and the youngest from 1985. Assuming that the service lives of the NPPs are equally long, they will be taken out of service over a 13-year period. An exception is Barsebäck 1, which was shut down in 1999, long before the end of its technical lifetime. RD&D-Programme 2004 323
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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
Page 261 and 262: 19.2.26 Integrated modelling - radi
Page 263 and 264: development that has taken place ha
Page 265 and 266: 20.2 Review of RD&D 2001 Following
Page 267 and 268: work will continue, particularly in
Page 269 and 270: 2 In Sea (mol) 3 Water Sea (mol/m 3
Page 271 and 272: The above work will be pursued in c
Page 273 and 274: certain substances, such as uranium
Page 275 and 276: In connection with the Safe project
Page 277 and 278: 20.9 International work and dissemi
Page 279 and 280: the underlying material are current
Page 281 and 282: These reports describe dominant fun
Page 283 and 284: Glacial Permafrost Permafrost Borea
Page 285 and 286: Shoreline displacement has an isost
Page 287 and 288: The hydromechanical modellings that
Page 289 and 290: model that includes these factors a
Page 291 and 292: The salinity of the sea, inland sea
Page 293 and 294: • Public opinion and attitudes -
Page 295 and 296: Socioeconomic impact • Local deve
Page 297 and 298: Previously existing material is bei
Page 299 and 300: • 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: Kasam says that disposal in Very De
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
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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
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KBS-3H Basic Design Detailed engine
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Time horizon 2017 The current phase
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2003 2004 2005 2006 2007 2008 Phase
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In the subsequent phase, verificati
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The canister development work will
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Deep repository Year 2003 2004 2005
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A4.2 Site investigations Site inves
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Already in the feasibility study, l
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In step D2, the facility descriptio
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Table 4. Current situation and prel
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2003 2004 2005 2006 2007 2008 Desig
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Table 5. Continued. Technology issu
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A4.6.1 Siting factors Before priori
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A possible alternative scenario is
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of the NPPs starts, however, long-l
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Between now and 2008, an organizati
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Appendix B Abbreviations Abaqus ACL
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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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