RD&D-Programme 2004 - SKB

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discontinuities. The study shows a good correlation between indications obtained from NDT and actual defect sizes. Furthermore, the results of the investigations are also useful in describing defects obtained in EBW welds. Another conclusion of the investigation was that a more detailed study should be conducted to determine the detection capability of the NDT methods. There is also reason to further study the technology for digital radiography, in view of the fact that research and development to date has mainly focused on ultrasonic testing. Based on the above, a project was initiated in 2003 at BAM (Bundesanstalt für Materialforschung und -prüfung) entitled “NDT Reliability”. The 3-year project is focusing on inspection of welds made by means of both EBW and FSW. The programme is described in greater detail under the heading “Programme” below. Within digital radiography, a similar methodology will initially be used for testing of FSW welds as that used for testing of EBW welds. However, a review will be made of possible development needs within the project “NDT Reliability”, which also deals with other development work on digital radiography. Development efforts within ultrasonic testing have been aimed at developing methods for inspection of FSW sealing welds. For development of the testing methodology, a new phased array ultrasonic system was procured at the end of 2002. The system meets the requirements for FSW testing with regard to frequency range and greatly simplified programming compared with the previous system. It is easier to control and focus the sound beam with the new system. In order to enable a suitable testing frequency to be specified in the ultrasonic testing of FSW welds, the sound attenuation and propagation properties of the structure have been studied. Similar tests have also been conducted on material from copper lids and cylinders. Testing methods have been defined on the basis of heretofore known types of defects that can occur in FSW welds in copper. Furthermore, theoretically possible defect formations have been posited and testing methods have been devised to cover these hypothetical cases as well. The testing methods are being progressively improved by evaluation of the indications obtained and comparison with the results from destructive tests. The methods that are currently being developed and evaluated are all based on phased array ultrasonic technology and can be described in brief as follows: • Testing of discontinuities with principal extent in the radial-tangential direction. This testing is currently being done from the top side of the lid with a 5 MHz probe that focuses in the middle of the weld, see Figure 6-22a. • Testing of discontinuities with principal extent in the axial-tangential direction. Two methods are currently being tried with testing from the outer surface: – Method 1 focuses on the area 2–10 millimetres from the surface and is performed with a 10 MHz array probe that is controlled so that it simulates a double crystal probe, see Figure 6-22b. – Method 2 focuses on the internal part of the weld and is performed with a 5 or 10 MHz phased array probe that is focused centrally in the weld, see Figure 6-22c. • Testing of discontinuities with principal extent in the radial-axial direction. Two configurations are currently being tried with 5 MHz phased array probes: – Most of the welding volume is examined by one probe on the outer surface and one on the inside of the lid. The probes scan at a 45 degree incident angle with direct throughtransmission and with reflection against any discontinuities, see Figure 6-22d. – For the lower part of the weld, the inside of the pipe is used as a reflector for two phased array probes on the outer surface. The location of the receiver is varied depending on whether the discontinuities are to be detected by defect echo reflection or back-wall echo reduction, see Figure 6-22e. RD&D-Programme 2004 83
a b Through-transmission Reflection c d Bottom echo/ reflection Defect echo/ reflection e Figure 6-22. Methods for ultrasonic testing of FSW sealing weld. 84 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
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
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: Nondestructive testing methods such
Page 81 and 82: simulation program, and the body of
Page 83 and 84: 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 127 and 128: 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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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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