RD&D-Programme 2004 - SKB

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Part II Technology development 4 Overview – technology development 5 Canister – fabrication 6 Canister – sealing 7 Canister – qualification 8 Canister – encapsulation 9 Transportation of encapsulated fuel 10 Deep repository – technology 11 Deep repository – design 12 Deep repository – monitoring
4 Overview – technology development Development of the technology for the KBS-3 method is currently in an intensive phase in preparation for the upcoming permit applications for the encapsulation plant and the deep repository. SKB’s strategy for the work is to focus on a reference design for each of the different parts of the system. Vertical deposition, KBS-3V, is the reference for the design of the deposition area in the rock. The work of designing the details follows a step-by-step process, where the final choices for different parts are made as late as possible so that they can be based on the most recent findings and investigations concerning alternative designs. Horizontal deposition of the copper canisters, KBS-3H, is one such alternative. The final choices are based on an evaluation of safety, technology, costs and environmental aspects. Questions relating to canister and encapsulation technology are dealt with in Chapters 5–8. Chapter 9 deals with the transportation of encapsulated spent nuclear fuel between the encapsulation plant and the deep repository. The technology for building and operating the deep repository is dealt with in Chapter 10, while the methodology for designing it is described in Chapter 11. Finally, long-term observations and monitoring of the deep repository are discussed in Chapter 12. Sections 4.1–4.8 contain short summaries of the programmes within each technology area. 4.1 Canister fabrication Copper tubes for canisters have been trial-fabricated using different methods such as roll forming, extrusion, pierce and draw processing and forging. The trials show that these methods are feasible for fabricating copper tubes. Various methods for casting the inserts are also being tested and evaluated. The development work is continuing in order to improve the fabrication technology, and SKB intends to report which methods are feasible for the future serial production of canisters in connection with the permit application for the encapsulation plant. The complete programme for canister fabrication and nondestructive testing of canister components is presented in Chapter 5. Fabrication of canisters will not take place at a single location. The inserts will be cast at different foundries and the copper tubes will presumably be made at some plant that has the requisite machinery. Machining of inserts and copper tubes will then take place at a machine shop or in the canister factory, which is a special facility for assembly and final inspection of the copper canisters before they are delivered to the encapsulation plant. The lids for the inserts and the copper lids are also components that will be fabricated by an external supplier. 4.2 Sealing technology SKB is currently working simultaneously to develop two welding methods to seal the copper canisters: electron beam welding (EBW) and friction stir welding (FSW). Equipment for testing of the two methods is in operation at the Canister Laboratory. The tests show that both methods work. Development work is continuing on the sealing technology to ensure that at least one method that meets the quality requirements will be available and that it can be used in serial production. Methods for nondestructive testing, above all ultrasonic and radiographic techniques, are also being developed in the Canister Laboratory. Work on this and to establish acceptance criteria will continue and be reported on in preparation for a permit application for the encapsulation plant. The programme for sealing technology for the canister and nondestructive testing of the sealing weld is described in Chapter 6. RD&D-Programme 2004 41
Page 1 and 2: Technical Report TR-04-21 RD&D-Prog
Page 3 and 4: Preface SKB, Svensk Kärnbränsleha
Page 5 and 6: welding and nondestructive testing
Page 7 and 8: Alternative methods. SKB is followi
Page 9 and 10: 5.5 Nondestructive testing of canis
Page 11 and 12: 15 Fuel 163 15.1 Initial state in f
Page 13 and 14: 18.1.10 Swelling pressure 229 18.1.
Page 15 and 16: Part I SKB’s programme and plan o
Page 17 and 18: Nuclear power plant Clab m/s Sigyn
Page 19 and 20: Figure 1-2. The Äspö HRL consists
Page 21 and 22: Figure 1-4. Interior from the Canis
Page 23 and 24: Siting SKB’s main alternative is
Page 25 and 26: Transport tunnel KBS-3V Deposition
Page 27 and 28: 2.1 Nuclear fuel programme In Swede
Page 29 and 30: Encapsulation plant 2003 2004 2005
Page 31 and 32: 2.2 LILW programme Parts of the sys
Page 33 and 34: environment. The barriers can also
Page 35: this cooperation entails that the o
Page 39 and 40: 4.7 Design of the deep repository T
Page 41 and 42: Diameter 1,050 Diameter 949 Diamete
Page 43 and 44: Conclusions in RD&D 2001 and its re
Page 45 and 46: Figure 5-3. Graphite shapes in cast
Page 47 and 48: Figure 5-5. Positions for test bars
Page 49 and 50: Programme The development project c
Page 51 and 52: Programme Trial fabrication of all
Page 53 and 54: The technology and procedures for c
Page 55 and 56: A method and equipment based on las
Page 57 and 58: Spacer plate Defect A Defect B Chan
Page 59 and 60: Newfound knowledge since RD&D 2001
Page 61 and 62: 2004 2005 Process model welding met
Page 65 and 66: 6.2.2 The welding process In parall
Page 67 and 68: Figure 6-9. Lid weld L028. Section
Page 69 and 70: Tensile test bars have been taken o
Page 73 and 74: 6.3.3 The welding process The param
Page 75 and 76: A limitation in the evaluation of t
Page 77 and 78: Nondestructive testing methods such
Page 79 and 80: a b Through-transmission Reflection
Page 81 and 82: simulation program, and the body of
Page 83 and 84: SKB has devised a quality system fo
Page 85 and 86: Newfound knowledge since RD&D 2001
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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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Newfound knowledge since RD&D 2001
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Conclusions in RD&D 2001 and its re
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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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Page 203 and 204:
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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
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SKB is responsible for management a
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25 Low- and intermediate-level wast
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25.2.1 Repository for short-lived L
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Programme Work on the design of the
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observation is that isosaccharinic
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stored so that the material can be
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6-4 Claesson S, 2004. Elektronstrå
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Chapter 14 14-1 SKB, 2004. Interim
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15-42 Ekeroth E, Jonsson M, 2003. O
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17-19 Le Bell J C, 1978. Colloid ch
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19-29 Hudson J (ed), 2002. Strategy
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19-77 Bath A, Milodowski A, Ruotsal
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20-19 Kautsky U (ed), 2001. The bio
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20-73 Blomqvist P, Jansson P-E, Esp
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20-119 Berggren J, Kyläkorpi L, 20
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23-10 NEA, 2002. Accelerator-driven
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SKB’s master plan Appendix A
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A1 Introduction A1.1 Background The
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generations unnecessarily. Another
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Encapsulation plant 2003 2004 2005
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facilitated by the fact that the re
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A2.3 System design A2.3.1 Fundament
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The system analyses will be largely
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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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