RD&D-Programme 2004 - SKB

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Sysinka TBM TBT TDB TDS Tecla Tecplot TEF TEM Tensit Testra THM THMC TN17-2 TN17-CC True TS01 TSL TWG TWI UPC URL US NRC USDOE UU Wave WPS Xanes XAS XPS XRD Yalina Zedex SKB’s system analysis as a basis for an application for a permit to build the encapsulation plant. Tunnel boring machine. Experiment at Äspö HRL. Temperature buffer test. OECD/NEA project. Thermodynamic data bases. Total dissolved solids. EU project. Cluster Testra, Technologies, materials and thermal-hydraulics for lead alloys. Computer code for postprocessing of results. Technical Evaluation Forums, Äspö HRL. Transmission electron microscopy. SKB’s computer code package for numerical calculations of radionuclide transport. EU project. Adopt cluster, Transmutation – technology studies. Thermo-hydro-mechanical. Thermo-hydro-mechanical-chemical. Transport cask for spent nuclear fuel. Transport cask for spent core components. Experiment at Äspö HRL. Tracer retention understanding experiments. Proper submodule for communication with ASCII files. The Svedberg Laboratory, Uppsala. European technical working group of experts on ADS. The Welding Institute, Cambridge, England. Universitat Politècnica de Catalunya. Underground Rock Laboratory. United States Nuclear Regulatory Commission. United States Department of Energy. Uppsala University. Computer code for rock mechanical analyses. Welding procedure specification. X-ray absorption near edge structures. X-ray absorption spectroscopy. X-ray photoelectron spectroscopy. X-ray diffraction. ISTC-funded project. A sub-critical, thermal facility set up in Minsk. Experiment at Äspö HRL. Zone of excavation disturbance experiment. α radiation β radiation γ radiation σ @Risk 3D 3DEC Alpha radiation. Beta radiation. Gamma radiation. Rock stress. Commercial risk analysis program. Three-dimensional. Computer code for rock mechanical analyses. 412 RD&D-Programme 2004
ISSN 1404-0344 CM Digitaltryck AB, Bromma, 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
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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
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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 and 398: GIA Gis Goldsim Hindas HMC HPF HRL
Page 399: PMMA POD Posiva Prism Proper Protot
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