RD&D-Programme 2004 - SKB

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Nuclear power Industry, research and medical care Operation Decommissioning Short-lived Long-lived Short-lived Long-lived Only short-lived* Short-lived* Long-lived Clab interim storage facility Interim storage facility** Encapsulation plant Long-lived Short-lived* Short-lived* Long-lived Operation Decommissioning Final repository for low- and intermediatelevel short-lived waste Final repository for other long-lived waste High-level Intermediate-level Low-level *) Short-lived waste arising after SFR has been closed follows dashed line **) Intermediate-level long-lived decommissioning waste (core components) is interim-stored according to present plan, not clear where at present Deep repository for spent nuclear fuel Figure 1-5. The complete system for managing and disposing of nuclear waste. RD&D-Programme 2004 25
Siting SKB’s main alternative is to build the encapsulation plant adjacent to Clab so that it can be coordinated with existing activities. The spent fuel can then be transferred directly from the storage pools in Clab to the pools in the encapsulation plant. At Clab there are also personnel with expertise in and experience from radiological work. SKB has conducted a feasibility study of a standalone encapsulation plant /1-1/ as well as a comparison between different alternative sitings /1-2/. The standalone encapsulation plant is assumed to be located near the deep repository’s surface facility. The primary technical difference between the planned encapsulation plant at Clab and the one at the deep repository is the way in which the fuel is handled and prepared prior to encapsulation. In the latter case, pools are not used to receive the spent fuel. The fuel is instead stored under dry conditions before being encapsulated. 1.3.2 Deep repository SKB’s reference method for disposal of spent nuclear fuel is called the KBS-3 Method, where the abbreviation KBS stands for kärnbränslesäkerhet = Nuclear Fuel Safety. The method involves encapsulating the fuel in copper canisters which are then deposited, surrounded by a buffer of bentonite clay, in deposition holes in a tunnel system at a depth of approximately 400–700 metres in crystalline bedrock, see Figure 1-6. The purpose of the three barriers (canister, buffer and rock) is to isolate the radionuclides in the fuel from the surrounding environment. Only if the radionuclides are brought up to the surface by the moving groundwater do they become harmful to man and the environment. In the deep repository it is primarily the canister that provides the isolating function. If radionuclides should escape from a leaky canister, their transport must be retarded. All barriers contribute to the retarding function. A partially damaged copper canister can effectively contribute to retardation by impeding inflow and outflow of water. The bentonite buffer has the capacity to retain many of the long-lived radionuclides, since they adhere to the surfaces of the clay particles. The rock contributes to the retardation by virtue of the low water flux at such great depth. Furthermore, radionuclides can adhere to fracture surfaces or penetrate into microfractures containing stagnant water. Cladding tube Spent nuclear fuel Bentonite clay Surface portion of deep repository 500 m Fuel pellet of uranium dioxide Copper canister with cast iron insert Crystalline bedrock Underground portion of deep repository Figure 1-6. The KBS-3 method is based on multiple barriers (canister, buffer and rock) that prevent the radionuclides in the fuel from harming man and the environment. 26 RD&D-Programme 2004
Page 1 and 2: Technical Report TR-04-21 RD&D-Prog
Page 3 and 4: Preface SKB, Svensk Kärnbränsleha
Page 5 and 6: welding and nondestructive testing
Page 7 and 8: Alternative methods. SKB is followi
Page 9 and 10: 5.5 Nondestructive testing of canis
Page 11 and 12: 15 Fuel 163 15.1 Initial state in f
Page 13 and 14: 18.1.10 Swelling pressure 229 18.1.
Page 15 and 16: Part I SKB’s programme and plan o
Page 17 and 18: Nuclear power plant Clab m/s Sigyn
Page 19 and 20: Figure 1-2. The Äspö HRL consists
Page 21: Figure 1-4. Interior from the Canis
Page 25 and 26: Transport tunnel KBS-3V Deposition
Page 27 and 28: 2.1 Nuclear fuel programme In Swede
Page 29 and 30: Encapsulation plant 2003 2004 2005
Page 31 and 32: 2.2 LILW programme Parts of the sys
Page 33 and 34: environment. The barriers can also
Page 35 and 36: this cooperation entails that the o
Page 37 and 38: 4 Overview - technology development
Page 39 and 40: 4.7 Design of the deep repository T
Page 41 and 42: Diameter 1,050 Diameter 949 Diamete
Page 43 and 44: Conclusions in RD&D 2001 and its re
Page 45 and 46: Figure 5-3. Graphite shapes in cast
Page 47 and 48: Figure 5-5. Positions for test bars
Page 49 and 50: Programme The development project c
Page 51 and 52: Programme Trial fabrication of all
Page 53 and 54: The technology and procedures for c
Page 55 and 56: A method and equipment based on las
Page 57 and 58: Spacer plate Defect A Defect B Chan
Page 59 and 60: Newfound knowledge since RD&D 2001
Page 61 and 62: 2004 2005 Process model welding met
Page 65 and 66: 6.2.2 The welding process In parall
Page 67 and 68: Figure 6-9. Lid weld L028. Section
Page 69 and 70: 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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Newfound knowledge since RD&D 2001
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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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Conclusions in RD&D 2001 and its re
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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
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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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