RD&D-Programme 2004 - SKB

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Crop Crud CTH DarcyTools Decovalex DFN EBS EBW EC Ecoclay Ecolego Ecopath EDF EDZ EKG Elforsk Embras Eniq Enresa Equip Erica Esarda Esdred ET EU Euratom Europart Examine Farf31 Fasset Febex Fep F factor Flac3D R&D Fracman/PAworks Fracod FSW RD&D RD&D-K Fuetra Gambit Gasnet Geotrap EU project. Cluster repository project, a basis for evaluating and developing concepts of final repositories for high-level radioactive waste. Chalk river unidentified deposits. Surface contamination. Chalmers Tekniska Högskola (Chalmers University of Technology), Göteborg. Computer code for groundwater flow calculations. International project. Mathematical models of coupled THM processes for nuclear waste repositories. Discrete fracture network. Engineered barrier system. Electron beam welding. European Commission. EU project. Effect of cement water on clay barrier performance. Computer code for safety assessment (biosphere). Computer code for safety assessment (biosphere). Ecosystem-specific Dose Conversion Factor. Excavation Disturbed Zone. Technical group within SKB for exchange of information between site investigation, analysis group, safety assessment and research. Svenska elföretagens forsknings- och utvecklings AB. IAEA project. EU project. European Network for Inspection Qualification. Empresa Nacional de Residuos Radiactivos, Spain. EU project. Evidence from Quaternary infillings for palaeohydrology. EU project. Environmental Risk from Ionising Contaminants. European Safeguards Research and Development Association. EU project. Engineering studies and demonstrations of repository designs. Eddy current testing. European Union. European Atomic Energy Community. EU project. European research program for the partitioning of minor actinides and some long-lived fission products from high active wastes issuing the reprocessing of spent nuclear fuels. Computer code for rock mechanical analyses. SKB’s computer code for calculation of radionuclide transport in the far-field (Proper submodule). EU project. Framework for assessment of environmental impact. Full-scale high level waste engineered barriers experiment, Grimsel, Switzerland. Feature, events and processes. Transport resistance. Computer code for rock mechanical analyses. Research and Development. Computer code, discrete fracture network for performance assessment. Computer code for rock mechanical analyses. Friction stir welding. Research, Development and Demonstration. Integrated account of method, site selection and programme prior to the site investigation phase, 2000. EU project. Adopt cluster, Transmutation – Basic studies. International project. Gas migration in bentonite. EU network. A thematic network on gas issues in safety assessment of deep repositories for nuclear waste. OECD/NEA project. Radionuclide migration in geologic, heterogeneous media. 408 RD&D-Programme 2004
GIA Gis Goldsim Hindas HMC HPF HRL HTGR HTO IAEA Global isostatic adjustment. Geographic information system. Computer code for safety assessment (biosphere). EU project. Cluster Bastra, High and intermediate energy nuclear data for accelerator-driven systems. Hydro-mechanical-chemical. International project. Hyperalkaline plume in fractured rocks, Grimsel, Switzerland. Hard rock laboratory. High-temperature gas-cooled reactor technology. Tritiated water. International Atomic Energy Agency. Ibeco Deponit CA-N Calcium bentonite from Milos. ICP-AES ICP-MS ICRP IJC InCan INF Inka IPCC ISI IRPA ISA ISO 14001 ISO 9001 ISTC ITU IUR JNC JobFem JRC KASAM KBS KBS-3H KBS-3 method KBS-3V K d CSI K-S-P KSU KTB KTH Inductively coupled plasma – optical emission spectroscopy. Inductively coupled plasma – mass spectrometer. International Commission on Radiological Protection. International joint committee, Äspö HRL. EU project. In can processes. Department of Neutron Research at Uppsala University. SKB project. Design of encapsulation plant. Intergovernmental panel on climate change. Initial site investigation. International Radiation Protection Association. Isosaccharinic acid. International quality standard, environmental management systems. International quality standard, quality management systems. International Science and Technology Center. Institute for Transuranium Elements, Karlsruhe. International Union of Radioecology. Japan Nuclear Cycle Development Institute, Japan. Computer code for thermomechanical analyses. Joint Research Center in the Netherlands. Swedish National Council for Nuclear Waste. Kärnbränslesäkerhet = Nuclear fuel safety. Variant of KBS-3, horizontal deposition with several consecutive canisters in medium-long deposition holes. SKB’s reference method for disposing of spent nuclear fuel. Reference variant of KBS-3, vertical deposition with one canister in each deposition hole. Element-specific distribution coefficients. Complete site investigation. Hydraulic parameters. Permeability (K) Saturation (S) Pressure (P). Kärnkraftsäkerhet och Utbildning AB (Nuclear Power Safety and Training Company). Kontinentales Tiefbohrprogramm der Bundesrepublik Deutschland. Kungliga Tekniska Högskolan (Royal Institute of Technology, Stockholm). KTL Kärntekniklag (Nuclear Activities Act, SFS 1984:3). KTS 001 Lasgit LILW Lot LTDE M3 SKB’s technical specification – Copper ingots and billets for canister components. Experiment at Äspö HRL, Large scale gas injection test. Low- and intermediate-level waste. Experiment at Äspö HRL, Long term test of buffer material. Experiment at Äspö HRL, Long term diffusion experiment. Computer code for hydrochemical analyses, Mixing and mass balance modelling. RD&D-Programme 2004 409
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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
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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
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
Page 369 and 370: In the subsequent phase, verificati
Page 371 and 372: The canister development work will
Page 373 and 374: Deep repository Year 2003 2004 2005
Page 375 and 376: A4.2 Site investigations Site inves
Page 377 and 378: Already in the feasibility study, l
Page 379 and 380: In step D2, the facility descriptio
Page 381 and 382: Table 4. Current situation and prel
Page 383 and 384: 2003 2004 2005 2006 2007 2008 Desig
Page 385 and 386: Table 5. Continued. Technology issu
Page 387 and 388: A4.6.1 Siting factors Before priori
Page 389 and 390: A possible alternative scenario is
Page 391 and 392: of the NPPs starts, however, long-l
Page 393 and 394: Between now and 2008, an organizati
Page 395: Appendix B Abbreviations Abaqus ACL
Page 399 and 400: PMMA POD Posiva Prism Proper Protot
Page 401: ISSN 1404-0344 CM Digitaltryck AB,
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