RD&D-Programme 2004 - SKB

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Year 06 08 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40 42 44 46 48 50 52 54 56 58 Operation of NPPs 60 40 years of operation Final repository for short-lived LILW Operational waste Design Construction Decommissioning waste Interim storage of core components At the NPPs and at Clab At SFR Final disposal of other long-lived waste Safety evaluation Siting Design Construction Operation of final repository for other long-lived waste Figure 25-1. General timetable for management and disposal of LILW, including waste from decommissioning of the NPPs. 25.2 Short-lived LILW Today, short-lived LILW is waste from operation and maintenance of the NPPs. This waste is well-characterized and has been handled routinely for nearly 30 years. Disposal of the portion for which SKB is responsible has been going on in SFR since 1988. In the future, when the phase-out of the NPPs begins, decommissioning waste will be added to this category. This waste consists of the same types of waste as arise in the operation and maintenance of the NPPs, but in different proportions. These waste types will be able to be treated, transported and deposited in the same way as the operational waste. The decommissioning waste is dominated by scrap metal and concrete residues. Conclusions in RD&D 2001 and its review The review of RD&D 2001 called for a better clarification of how the waste from decommissioning will be managed, in particular the large quantities of low-level waste that are expected. Newfound knowledge since RD&D 2001 SKB is striving for a more coherent planning and handling of issues related to the low- and intermediate-level waste. This is being done by e.g. recurrent waste forecasts as well as new and updated studies regarding quantities and types of waste. As far as management of LILW is concerned, SKB is responsible for the waste that will be disposed of in SKB’s facilities. Other kinds of waste, for example materials released for unrestricted use and low-level materials intended for onsite disposal at the NPPs, are also the responsibility of the NPPs. The whole problem can be addressed and optimal solutions found by cooperation between SKB and the power companies. Programme See section 25.5. 328 RD&D-Programme 2004
25.2.1 Repository for short-lived LILW Final disposal of short-lived LILW takes place today in SFR. When the phase-out of the NPPs has reached the start of decommissioning, SKB must have a final repository for the shortlived waste ready to receive the waste. This repository is planned to be an extension of SFR. An extension for operational waste will be needed in the mid-2020s if many of the NPPs are operated for more than 40 years. Conclusions in RD&D 2001 and its review The regulatory authorities consider it reasonable that a final repository for decommissioning waste should stand ready to receive waste in 2015. Newfound knowledge since RD&D 2001 The phase-out planning in effect today indicates that large-scale decommissioning will not take place until after 2020 at the earliest. In conjunction with the extension of SFR to receive decommissioning waste, SKB will re-license the facility so it can accommodate short-lived waste, regardless of whether it comes from operation or decommissioning. Programme See section 25.5. 25.2.2 Safety evaluation No formal safety assessment has been carried out for the final repository for short-lived decommissioning waste since the preliminary safety assessment for SFR in 1982. The intention is to conduct a new preliminary safety evaluation during the period. A safety assessment will be submitted in connection with the publication of a preliminary safety report for the extended final repository for short-lived decommissioning waste in 2013. 25.3 Long-lived low- and intermediate-level waste The long-lived LILW consists mainly of two categories: • Long-lived waste from research, medical care and industry. • Core components and some reactor internals (highly neutron-irradiated) from maintenance and decommissioning of the NPPs. The first category is packaged and interim-stored in a special rock cavern in Studsvik in moulds or drums for subsequent disposal. The material from the NPPs is interim-stored today in storage canisters in Clab, or at the NPPs. Final packaging is done in conjunction with disposal. Decommissioning of the NPPs will give rise to large quantities of long-lived scrap (reactor internals and core components). Alternatives to interim storage in Clab will be investigated. An inventory of the long-lived LILW that exists and is expected to arise was done in 1998 as a basis for the preliminary safety assessment of a final repository for other long-lived waste, which was carried out the following year /25-1/. The total volume of long-lived LILW from Studsvik was estimated at 1,850 m 3 . Core components and reactor internals from the NPPs were estimated to total 7,800 m 3 for BWRs and 1,800 m 3 for PWRs. The volumes are calculated from the outside dimensions of the waste packages that already exist or will be produced. RD&D-Programme 2004 329
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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
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
Page 303 and 304: • 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: 25 Low- and intermediate-level wast
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 and 366: Time horizon 2017 The current phase
Page 367 and 368: 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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