RD&D-Programme 2004 - SKB

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Table 13-1. Research on long-term safety. Code: Major initiatives Moderate initiatives Minor initiatives/monitoring during coming three-year period Fuel Canister Buffer Backfill Geosphere R Radioactive decay 15.2.2 Radiation attenuation/heat generation 15.2.3 Induced fission (criticality) 15.2.4 Radiation attenuation/heat generation 16.2.2 Radiation attenuation/heat generation 17.2.2 Radiation attenuation/heat generation 18.2.3 T Heat transport 15.2.5 Heat transport 16.2.3 Heat transport 17.2.3 Heat transport 18.2.4 Heat transport 19.2.2 H Water/gas transport 15.2.6 Water transport unsatur. 17.2.4 Water transport unsatur. 18.2.5 Groundwater flow 19.2.3 Water transport satur. 17.2.5 Water transport satur. 18.2.6 Gas transport/dissolution 17.2.6 Gas transport/dissolution 18.2.7 Gas flow/dissolution 19.2.4 M Deformation insert 16.2.4 Swelling 17.2.7 Swelling 18.2.8 Movements in intact rock 19.2.5 Thermal expansion/cladding failure 15.2.7 External deformation Cu 16.2.5 Mech. inter. buffer/backfill 17.2.8 Mech. inter. backfill/rock 18.2.9 Reactivation (earthquakes) 19.2.7 Inner deformation Cu 16.2.7 Mech. inter. buffer/canister 17.2.9 Fracturing 19.2.8 Mech. inter. buffer/rock 17.2.10 Time-dependent deformations 19.2.9 Thermal expansion 16.2.6 Thermal expansion 17.2.11 Thermal expansion 18.2.10 Thermal movement 19.2.6 Erosion 19.2.10 C Advection/diffusion 15.2.8 Advection 17.2.13 Advection 18.2.11 Advection/mixing 19.2.11 Resid. gas radiolysis/oxygen form. 15.2.9 Diffusion 17.2.14 Diffusion 18.2.12 Diffusion 19.2.13 Corrosion insert 16.2.8 Osmosis (salt effect) 17.2.15 Osmosis (salt effect) 18.2.13 Reactions with rock 19.2.15 Water radiolysis 15.2.10 Galvanic corrosion 16.2.9 Ion exch./sorption 17.2.16 Ion exch./sorption 18.2.14 Dissol./precip. fract. minerals 19.2.16 Metal corrosion 15.2.11 SCC insert 16.2.10 Montmorillonite transf. 17.2.17 Montmorillonite transf. 18.2.15 Microbial processes 19.2.18 Fuel dissolution 15.2.12 Radiation effects 16.2.11 Dissolution/prec. impurities 17.2.18 Dissolution/prec. impurities 18.2.16 Inorganic decomp. 19.2.19 Dissolution gap invent. 15.2.13 Copper corrosion 16.2.12 Colloid release/erosion 17.2.19 Colloid release/erosion 18.2.17 Colloid turnover 19.2.20 Speciation radionuclides/colloid formation 15.2.14 SCC shell 16.2.13 Radiation-induced montmorillonite transf. 17.2.20 Radiation-induced transf. 18.2.13 Gas formation/dissolution 19.2.22 Helium production 15.2.15 Grain growth copper 16.2.14 Radiolysis pore water 17.2.21 Radiolysis pore water 18.2.19 Methane ice formation 19.2.23 Integration HMC evolution damaged canister 16.2.16 Microbial processes 17.2.22 Microbial processes 18.2.20 Salt exclusion 19.2.24 THM evolution unsaturated 17.2.12 THMC evolution saturated 17.2.23 HC evolution 19.2.25 Radionuclide Advection 17.2.24 Advection 18.2.21 Advection/mixing 19.2.12 transport Diffusion 17.2.25 Diffusion 18.2.22 Diffusion 19.2.14 Sorption 17.2.26 Sorption 18.2.23 Sorption 19.2.17 Speciation 17.2.27 Speciation 18.2.24 Speciation 15.2.14 Colloid transport 17.2.28 Colloid transport 19.2.21 Gas phase transport 19.2.4 RN transport near-field 16.2.15 RN transport geosphere 19.2.26 RD&D-Programme 2004 147
Table 13-2. Research on the initial state of the repository. Fuel Canister Buffer Backfill Geosphere Geometry 15.1.2 Geometry 16.1.2 Geometry 17.1.2 Geometry 18.1.2 Radiation intensity 15.1.3 Radiation intensity 16.1.3 Pore geometry 17.1.3 Pore geometry 18.1.3 Temperature 15.1.4 Temperature 16.1.4 Radiation intensity 17.1.4 Radiation intensity 18.1.4 Hydrovariables 15.1.5 Mechanical stresses 16.1.5 Temperature 17.1.5 Temperature 18.1.5 Mechanical stresses 15.1.6 Material composition 16.1.6 Smectite content 17.1.6 Smectite content 18.1.6 Total radionuclide inventory 15.1.7 Water content 17.1.7 Water content 18.1.7 Site Investigations Gap inventory 15.1.8 Gas contents 17.1.8 Gas contents 18.1.8 Material composition 15.1.9 Hydrovariables 17.1.9 Hydrovariables 18.1.9 Water composition 15.1.10 Swelling pressure 17.1.10 Swelling pressure 18.1.10 Gas composition 15.1.11 Smectite composition 17.1.11 Smectite composition 18.1.11 Pore water composition 17.1.12 Pore water composition 18.1.12 Impurity levels 17.1.13 Impurity levels 18.1.13 Code: Major initiatives Moderate initiatives Minor initiatives/monitoring during coming three-year period 148 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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Page 87 and 88: 8 Canister - encapsulation The desi
Page 89 and 90: Figure 8-2. Work stations in the en
Page 91 and 92: The filled canister transport casks
Page 93 and 94: Stages encapsulation plant 2003 200
Page 95 and 96: Figure 8-4. Possible location of a
Page 97 and 98: 9 Transportation of encapsulated fu
Page 99 and 100: 9.3 SKB’s transportation system -
Page 101 and 102: absorbs neutron radiation. The lid
Page 103 and 104: Applicable international and Swedis
Page 105 and 106: een specified yet. Since the size o
Page 107 and 108: • Methods exist for full-face dri
Page 109 and 110: Programme SKB keeps track of curren
Page 111 and 112: Judgement with regard to long-term
Page 113 and 114: Furthermore, it must not have an ad
Page 115 and 116: Studies of equipment will be conduc
Page 117 and 118: A third type of seal is intended to
Page 119 and 120: 10.6.1 Requirements and premises In
Page 121 and 122: 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: As a complement to the numerical mo
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 and 174: 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
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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
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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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