RD&D-Programme 2004 - SKB

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16 Canister as barrier SKB’s reference canister consists of an inner container of cast iron and an outer shell of copper. The cast iron insert provides mechanical stability while the copper shell protects against corrosion in the repository environment. The technical development of equipment and methods for fabricating, sealing and testing the canister is described in Chapters 5–7, while design of the encapsulation plant is dealt with in Chapter 8. The canister is an important barrier to the escape of radionuclides. This chapter describes the research being conducted by SKB to examine the long-term safety of the canister. 16.1 Initial state of canister By initial state of the copper canister and the cast iron insert is meant the state of the canister at the time of deposition. This state is described in the safety assessment with the aid of a set of variables. 16.1.1 Variables No changes have occurred with regard to the variables for the copper canister and the cast iron insert. It is the same set of variables as that presented in RD&D 2001, see Table 16-1. Table 16-1. Variables for copper canister and cast iron insert. Variable Geometry Radiation intensity Temperature Mechanical stresses Material composition Definition Geometric dimensions of the canister components. This also includes a description of possible fabrication defects (e.g. in welding). Intensity of α, β, γ and neutron radiation as a function of time and space in the canister components. Temperature as a function of time and space in the canister components. Mechanical stresses as a function of time and space in the canister components. Material composition of the canister components 16.1.2 Geometry The variable “canister geometry”, which is used in the safety assessment, includes not only the geometric shape of the canister, but also possible initial defects in the seal. Conclusions in RD&D 2001 and its review In RD&D-Programme 2001, SKB describes a plan for the development of acceptance criteria and says that experience from trial welding will provide information on the types and frequency of defects that can arise in connection with welding. SKI concurs that this is the right way to go, but wishes to emphasize that acceptance criteria must be established for permissible defects in the copper shell and its welds, as well as the cast inserts. Consequence analyses will show what happens if there are more and/or larger defects than allowed by the acceptance criteria. The effects of minor defects should also be analyzed to assess the sensitivity of the system, as is also pointed out by SSI. When it comes to future safety assessments, SKI says that there must be a strong link between input data to the safety assessment, acceptance criteria and test statistics from nondestructive testing. SKB says that the work will be conducted jointly with representatives from safety assessment, research and technology development, which SKI views very positively. RD&D-Programme 2004 183
Newfound knowledge since RD&D 2001 Data and experience since RD&D 2001 are presented in /16-1/. Programme SKB’s research programme to determine acceptance criteria and in a later stage work towards qualification of equipment for nondestructive testing will continue during the upcoming period. Evaluation of trial weldings is under way at the Canister Laboratory and information is being collected on the types of defects, as well as their frequency, to which electron beam welding (EBW) and friction stir welding (FSW) can give rise, see also Chapter 6. 16.1.3 Radiation intensity SKB’s criterion is that the surface dose rate on the canister may not exceed 1 Gy/h. Conclusions in RD&D 2001 and its review No direct viewpoints were offered. Newfound knowledge since RD&D 2001 No new knowledge has been forthcoming. Programme The field is judged today not to require any further research, development or demonstration. New developments are being monitored and will be acted on when appropriate. 16.1.4 Temperature This refers to the initial temperature of the canister, i.e. the temperature immediately after deposition. This variable is formally included in the initial state, but occasions no research. The canister’s temperature evolution is estimated in an integrated temperature modelling of the repository’s near-field, see section 15.1.4. 16.1.5 Mechanical stresses The residual stresses that may remain in the sealing weld after a very long time are low and not deemed to be of any importance for the lifetime of the canister. Conclusions in RD&D 2001 and its review No research programme was presented in RD&D 2001. Newfound knowledge since RD&D 2001 No new knowledge has been forthcoming. Programme As was stated in RD&D 2001, the field is not judged to require any further research, development or demonstration for canisters sealed with an electron beam weld. The size and importance of any residual stresses in sealing welds made by friction stir welding should be investigated during the period. 184 RD&D-Programme 2004
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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
Page 123 and 124: Newfound knowledge since RD&D 2001
Page 125 and 126: Conclusions in RD&D 2001 and its re
Page 127 and 128: 11.3 Execution - stepwise design Si
Page 129 and 130: Programme Design step D, which incl
Page 131 and 132: 12 Deep repository - monitoring SKB
Page 133 and 134: • Trigger levels for action. •
Page 135 and 136: Part III Safety assessment and rese
Page 137 and 138: As a complement to the numerical mo
Page 139 and 140: Table 13-2. Research on the initial
Page 141 and 142: 13.2.4 Backfill Together with Posiv
Page 143 and 144: Table 13-3. Projects and experiment
Page 145 and 146: spent nuclear fuel. It was neverthe
Page 147 and 148: concepts or whose descriptions requ
Page 149 and 150: 14.2.2 Radionuclide transport and d
Page 151 and 152: At present, the computational time
Page 153 and 154: Inflow Nuclides in a soluble phase
Page 155 and 156: 15.1.2 Geometry The deep repository
Page 157 and 158: 7 6 BWR 55 MWd/tU PWR 42 MWd/tU PWR
Page 159 and 160: 15.1.11 Gas composition Conclusions
Page 161 and 162: 15.2.5 Heat transport Dealt with in
Page 163 and 164: simulating the repository environme
Page 165 and 166: 238 U 237 Np 239 Pu Concentration,
Page 167 and 168: The catalytic effect of uranium dio
Page 169 and 170: oxidant consumption in the bulk sol
Page 171 and 172: The influence of hydrogen peroxide
Page 173: A research programme to study cast
Page 177 and 178: 16.2.3 Heat transport No new knowle
Page 179 and 180: Programme The ongoing experiments w
Page 183 and 184: Programme Short-term tests aimed at
Page 185 and 186: Swelling properties The buffer must
Page 189 and 190: have been performed for some ten co
Page 191 and 192: 17.1.13 Impurity levels Bentonite i
Page 193 and 194: out when the buffer swells, but our
Page 195 and 196: These processes have been studied i
Page 199 and 200: • The gas injection phase will be
Page 203 and 204: Conclusions in RD&D 2001 and its re
Page 205 and 206: 19 9 D=205 d=175 D=172 d=170 D=168
Page 207 and 208: • Tests of the wetting process cl
Page 211 and 212: Figure 17-4. Natural redox front in
Page 213 and 214: These phenomena have been studied b
Page 215 and 216: 17.2.24 Radionuclide transport - ad
Page 217 and 218: Programme SKB does not consider sor
Page 219 and 220: 18.1.6 Smectite content SKB, togeth
Page 221 and 222: Programme See section 18.2.2. 18.1.
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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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