RD&D-Programme 2004 - SKB

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Maqarin Matlab MB MBA Microbe Mistra EIA MLH Mock-up Mox MSRE Muse MX-80 Nagra Nanet Natt NDT NDT Reliability NEA Net.excel NF-Pro NGI Nimonic 105 Nirex NKS n-TOF Nuctran Numlib Numo OECD OECD/NEA NDT Ondraf/Niras Opalinus OPG ORNL Padamot Particle Flow Code Partition Partnew PDS-XADS UDP PFC Phreeqc Pick51 Natural analogue. There is natural cement in the rock in Maqarin, Jordan. Commercial computer code for mathematical calculations. SFS 1998:808 Environmental Code. Material balance area. Microbial experiments at Äspö HRL. Swedish Foundation for Strategic Environmental Research. Environmental Impact Assessment. Medium Long Holes, early name for KBS-3H. Czech large-scale experiment simulating a vertical deposition hole with canister and buffer. Mixed oxide fuel. USDOE project. Molten Salt Reactor Experiment. EU project. Cluster Bastra, Demonstration of the physical principles of an external source-driven sub-critical core at near zero power. Sodium bentonite from Wyoming. Nationale Genossenschaft für die Lagerung von Radioaktiver Abfälle, Switzerland. EU project. Network to review natural analogue studies and their applications to repository safety assessment and public communication. Project financed by SKB, SKI and the nuclear power companies in Sweden. Neutron data for accelerator-driven transmutation technology. Non destructive testing. Research programme at BAM to determine the reliability of the NDT methods. Nuclear Energy Agency, Paris. EU project. Network of excellence in nuclear waste management and disposal. EU project. Understanding and physical and numerical modelling of the key processes in the near-field and their coupling for different host rocks and repository strategies. Norwegian Geotechnical Institute. Nickel-based superalloy. Nirex Ltd. Nordic nuclear safety collaboration. Neutron time-of-flight facility in Cern. SKB’s computer code for calculation of radionuclide transport in the near-field. Routine library for numerical calculations. Waste management organisation of Japan. Organisation for Economic Cooperation and Development, Paris. Organisation for Economic Cooperation and Development/Nuclear Energy Agency. Nondestructive testing. Belgian agency for radioactive waste and enriched fissile materials. Swiss project. Performance assessment of a high-level radioactive waste repository in Opalinus clay host. Ontario Power Generation. Oak Ridge National Laboratory, USA. EU project. Palaeohydrogeological data analysis and model testing. Computer code for rock mechanical analyses. EU project. Adopt cluster, Partitioning. EU project. Cluster Partitioning, New solvent extraction processes for Minor Actinides. EU project. Adopt, Preliminary design studies of an experimental accelerator-driven system. Deep Repository, Underground Design Premises. Particle flow code. Computer code for rock mechanical analyses. Computer code for coupled geochemistry and transport analyses. Proper submodule for communication with ASCII files. 410 RD&D-Programme 2004
PMMA POD Posiva Prism Proper Prototype PSACoin PSI PWR PVT Pyrorep RedImpact Retrock Rex RH Rixs RMN bentonite RNR ROC RVS SAD Polymethylmethacrylate autoradiographs. Probability of detection. Posiva Oy. Computer code for probabilistic calculations of radionuclide transport in the biosphere. SKB’s computer code package for handling of probabilistic calculations of hydrology and radionuclide transport. EU project. Full scale testing of the KBS-3 concept for high-level radioactive waste. OECD/NEA project. Probabilistic system assessment codes intercomparison. Paul Scherrer Institute, Switzerland. Pressurized water reactor. Method for measuring reaction kinetics (pressure-volume-temperature). EU project. Cluster Partition, Pyrometallurgical processing research programme. EU project. Impact of reduction and waste treatment techniques. EU project. Treatment of geosphere retention phenomena in safety assessments. Experiment at Äspö HRL. Redox experiment in detailed scale. Relative humidity. Resonant inelastic X-ray scattering. Czech bentonite. Experiment at Äspö HRL. Radionuclide retention experiment. Risk of false calls. Rock visualisation system. ISTC funded project. Creation of sub critical assembly driven by proton accelerator. Safe SKB project. Renewed safety report for the final repository for operational waste, 2001. Safir-2 SBM SEM-EDS SFR SFS Simulink SKB SKB 91 SKI SLU Soil Spire SQC Belgian project. Belgian programme on high-level and long-lived waste. Shaft boring machine. Scanning electron microscope – Energy dispersive spectroscopy. Final repository for short-lived low- and intermediate-level waste. EU project. Spent fuel stability under repository conditions. Commercial computer code for mathematical calculations. Svensk Kärnbränslehantering AB (Swedish Nuclear Fuel and Waste Management Co). SKB project. Importance of the bedrock for the long-term safety of the KBS-3 repository, 1992. Statens kärnkraftinspektion (Swedish Nuclear Power Inspectorate). Swedish University of Agricultural Sciences, Uppsala. Computer code that handles transpiration, growth and nutrient uptake for vegetation. EU project. Cluster Testra, Irradiation effects in martensitic steels under neutron and proton mixed spectrum. SQC Kvalificeringscentrum AB. SR 95 SKB project, template for safety reports with descriptive examples, 1996. SR 97 SKB project, post-closure safety of the deep repository, 1999. SR-Can SR-Site SSI Sum41 SveBeFo Sweclim Sysdjup SKB’s safety assessment as a basis for an application for a permit to build an encapsulation plant. SKB’s safety assessment as a basis for an application for a permit to build a deep repository. Statens strålskyddsinstitut (Swedish Radiation Protection Authority). SKB’s computer code for weighting and summation of time series in the biosphere (Proper submodule). Stiftelsen svensk bergteknisk forskning (Swedish Rock Engineering Research Foundation). Mistra project. Swedish regional climate modelling programme. SKB’s system analysis as a basis for an application for a permit to build the deep repository. RD&D-Programme 2004 411
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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
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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 and 396: Appendix B Abbreviations Abaqus ACL
Page 397: GIA Gis Goldsim Hindas HMC HPF HRL
Page 401: ISSN 1404-0344 CM Digitaltryck AB,
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