RD&D-Programme 2004 - SKB

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Newfound knowledge since RD&D 2001 No new knowledge has been forthcoming. The pilot tests that were conducted of the possibility of studying SCC by measuring electrochemical noise gave negative results. The technique turned out not to be applicable to measurements of stress corrosion cracking. Programme A study of SCC in acetate-containing water will be conducted during the coming three-year period in cooperation with Posiva. In addition to this, a new pilot study is under way, this time of the possibility of studying SCC by measuring acoustic emission from crack growth. 16.2.14 Grain growth in copper Conclusions in RD&D 2001 and its review The field was not judged to require any further research, development or demonstration; it would be enough to monitor the field and take action when appropriate. Newfound knowledge since RD&D 2001 No new knowledge has been forthcoming. Programme SKB makes the same judgement as in RD&D 2001, that it is enough to monitor developments in the field. 16.2.15 Radionuclide transport Radionuclide transport in the near-field is dealt with in section 18.3. 16.2.16 Integrated studies – evolution of damaged canister If water enters a damaged canister, this leads to hydrogen gas generation, which increases the pressure inside the canister, which in turn reduces the rate at which the water enters. At some point when the pressure difference is small, inward diffusion of water vapour will be greater than the inflow of water. The time until this occurs varies with assumptions concerning the size of the hole and the corrosion rate, but is in most cases thousands of years. The inward diffusion of water vapour means that corrosion will not cease completely. This will lead to a slow accumulation of corrosion products and a pressure build-up inside the copper canister, which could eventually damage the copper shell. To get a picture of the evolution of a damaged canister, different processes must be modelled in an integrated fashion. Conclusions in RD&D 2001 and its review In SKI’s opinion, SKB’s previously reported model for a damaged canister shows that even a defective canister has a significant barrier function. However, the authority is sceptical to too literal an interpretation of the quantitative data obtained from the modelling of a damaged canister and to the direct integration of the data into a consequence analysis. Newfound knowledge since RD&D 2001 See section 16.2.7. RD&D-Programme 2004 191
Programme Short-term tests aimed at understanding what happens over time spans of hundreds of thousands of years are of limited value, but can nevertheless contribute to a better understanding of the evolution of a damaged canister in the deep repository. During the coming three-year period, SKB will start a number of model experiments where miniature canisters, complete with inserts but with defective copper shells, are deposited in borehole through water-conducting fractures in the Äspö HRL. The experiments are planned to continue for five to ten years and will hopefully contribute to a better understanding of how the corrosion attacks in the gap between copper shell and cast iron insert may develop. 192 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
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11.3 Execution - stepwise design Si
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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
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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 and 174: A research programme to study cast
Page 175 and 176: Newfound knowledge since RD&D 2001
Page 177 and 178: 16.2.3 Heat transport No new knowle
Page 179 and 180: Programme The ongoing experiments w
Page 181: Newfound knowledge since RD&D 2001
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.
Page 223 and 224: The wetting of the backfill from th
Page 225 and 226: Conclusions in RD&D 2001 and its re
Page 227 and 228: ackfill must have a compression mod
Page 229 and 230: Programme See section 17.2.17. 18.2
Page 231 and 232: 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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RD&D-Programme 2004 - SKB

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