RD&D-Programme 2004 - SKB

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Important events In the project 2004 2005 2006 2007 2008 2009 Application deep repository Encapsulation plant Application Permit Safety assessments SR-Can SR-Site Supporting material for safety assessment, fabrication and sealing Sealing methods Executed Fabrication methods Methodology Methodology Executed NDT NDT NDT Supporting material for safety assessment NDT Insert Reliability study NDT welding Reliability study NDT fabrication Methodology/plan established Probabilistic strength analysis finished Reliability NDT fabrication executed Figure 7-1. Timetables for compiling supporting material for the various safety assessments. 7.2 Qualification of NDT methods The canisters with spent nuclear fuel will undergo NDT by means of e.g. radiography and ultrasonics before being emplaced in the repository. Like the fabrication and sealing methods, the NDT methods planned to be used will also undergo qualification. Conclusions in RD&D 2001 and its review Two milestones can be distinguished in qualification. The first will be reached when SKB plans to apply for a permit to build an encapsulation plant. At this point, qualification will be focused on so-called technical justification. What technical justification entails is laid down in ENIQ (European Network for Inspection Qualification) Recommended Practice 2 /7-2/. SKB intends to apply this recommendation in the documentation of its NDT methods. The second milestone will be reached when the encapsulation plant is commissioned. Then SKB intends to qualify the NDT methods based on ENIQ Recommended Practice 4 /7-3/. SKI recommends that SKB more clearly describe who is to carry out the qualification of nondestructive testing and what the infrastructure for qualifications should look like. SKI believes that SKB underestimates the time required for qualification and that the results of qualification can, at a late stage, influence the design of the encapsulation plant, for example if an NDT method does not have the desired result. Furthermore, the Inspectorate points out that the qualification methodology described in ENIQ’s document must be adapted for the nondestructive testing of canisters, since it has actually been developed for the recurrent testing of mechanical devices in nuclear power plants. The development of the methodology should take place towards clearly defined qualification goals. A necessary condition for qualification is knowledge of possible defects as well as acceptance criteria. The work on acceptance criteria must be given high priority. RD&D-Programme 2004 89
Newfound knowledge since RD&D 2001 SKB concurs with the viewpoints of the Inspectorate that the qualification process must be adapted to KBS-3. SKB has an ongoing dialogue with SKI regarding the general forms and the long-term timetable for qualification. SKB is holding a parallel dialogue with the independent qualification body SQC Kvalificeringscentrum AB (SQC) regarding the development of a qualification programme adapted to KBS-3. In preparation for the upcoming applications for the encapsulation plant and the deep repository, SKB is working on a plan for qualification of NDT methods. The discussions being held with SKI have shed light on the need for clarifying the different steps in the qualification programme, the logic in the underlying documentation, and links to the safety assessments prior to the application for a permit to build the encapsulation plant (SR-Can) and the deep repository (SR-Site). The overall timetable SKB is working with to carry out qualification of nondestructive testing is shown in Figure 7-2. “Principles for technical documentation” are to be described in conjunction with the application. By this is meant documentation that can be regarded as relevant for setting up the requirements for nondestructive testing. Work on defining relevant technical material is under way. The purpose of the milestone is to compile the supporting material in a coherent fashion and, if necessary, present action plans for ensuring that the compilation is complete when it is presented in its final form in mid-2011. A suitable structure for this supporting material is: • Design premises. Analysis and development of requirements derived from the overall design premises for the deep repository. The analysis results in detailed design premises for the canister and supporting material for the choice of canister material. • Load data. The different loads on the canister such as handling loads, compressive loads in the deep repository and the various chemical processes that affect the canister on different time scales. • Strength analyses. Determination of the material properties of the canister, strength calculations and their premises. Dimensional design of the canister. • Fabrication, sealing and inspection. Fabrication and welding processes as well as description of the defects that can arise during them. The inspection processes intended to be applied and acceptance criteria. Qualification requirements and detection goals for the inspection processes. Important events Deep repository 2006 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 Application deep repository Siting permit Deposition permit Encapsulation plant Application Permit Operating licence application Operating licence Qualification NDT external SKB presents principles for technical documentation SKB proposes sequence and strategy SKB submits technical documentation SKB submits qualification organization SKB submits documentation Qualification begins Qualification of NDT finished Certificate issued SKI prescribes technical review SKI approves sequence and strategy Review of technical documentation SKI approves qualification organization Figure 7-2. General timetable for carrying out qualification of nondestructive testing. 90 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
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
Page 73 and 74: 6.3.3 The welding process The param
Page 75 and 76: A limitation in the evaluation of t
Page 77 and 78: Nondestructive testing methods such
Page 79 and 80: a b Through-transmission Reflection
Page 81 and 82: simulation program, and the body of
Page 83: SKB has devised a quality system fo
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 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. •
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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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Newfound knowledge since RD&D 2001
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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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Conclusions in RD&D 2001 and its re
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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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Conclusions in RD&D 2001 and its re
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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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