RD&D-Programme 2004 - SKB

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Within eddy current testing, the project at Uppsala University has been concluded with good results /6-7/. The results show that the testing results are not dependent on the material’s microstructure, i.e. welds and parent metal give equivalent results. The distance from the surface to the discontinuity can be determined by means of the signals’ phase angle, regardless of the shape of the discontinuities. At the Canister Laboratory, equipment for eddy current testing (ET instrument with probe and data collection system) has been acquired, and evaluation of full-scale welds is currently under way. Programme Development of methodology and equipment for nondestructive testing (NDT) of FSW is under way at the Canister Laboratory and is expected to be completed during 2004. As a part of the programme for determining the reliability of the NDT methods (NDT Reliability), we will study radiographic inspection of welds. The basis for this is that SKB has not conducted any studies on radiographic testing, something which SKI has emphasized is important. A 35 degree incident angle to the weld is used in radiographic testing of EBW welds, which gives good results. One question is whether we should use other and multiple beam directions in order, for example, to be able to determine defect position. These questions are of interest for FSW welds in particular. Practical radiographic tests are time-consuming and expensive and not possible in a reasonable time perspective, since possible beam directions are limited by the X-ray chamber. This part of the project includes the following: • Measurement of the spectrum of the radiation source and the detector at the Canister Laboratory. This survey is focused on the linear accelerator’s characteristics, the detector’s sensitivity and spatial resolution, and a comparison of system performance with standards for traditional film-based radiography. • Adaptation of BAM’s simulation model with the aid of the above-measured parameters. • Simulation tests to study the detection possibilities at different configurations. Reconstructions of actual defects imaged by means of high-resolution microfocus computer tomography and placed in a CAD model of the weld are used as input data in the simulation. The simulations are validated by comparing simulated images with real images obtained in SKB’s system. • Evaluation of alternative radiographic methods and detectors. A second part of the project concerns determination of the reliability of the NDT methods. In an initial stage, test objects are being examined according to established testing procedures at the Canister Laboratory and the results are being carefully documented. The test objects consist of lid welds with a large number of discontinuities created by varying important parameters beyond the process window for the particular welding method. The purpose of this approach is to ensure that different types of possible discontinuities are present in the test objects. In the next stage the incidence of defects is investigated in detail by computer tomography complemented by high-resolution microfocus computer tomography. In addition, investigations are also conducted by means of other NDT methods and destructive tests on metallographic sections and tensile specimens. These data are then processed statistically. In order to describe the reliability of the NDT methods, POD (probability of detection) curves and ROC (risk of false calls) curves are used in accordance with relevant recommendations in the standard MIL-HDBK-1823 /6-8/. The statistical processing of the data will shed light on the reliability of the NDT methods both individually and in combination. Simulation tests will also be performed in the project in order to determine POD in the use of radiographic technique. Initially, the information that exists on the real defects with respect to such important parameters as orientation, size, shape factors, gap width etc will be processed. The next step is to statistically determine within what limits these parameters vary and randomly generate defects within this parameter window. The advantage is that a virtually unlimited number of relevant defects can be generated and imaged in the RD&D-Programme 2004 85
simulation program, and the body of statistics available for the analysis can thereby be increased considerably. The above process, which is described schematically in Figure 6-23, will take place along two parallel tracks that deal with sealing welds executed by EBW and FSW. The project at BAM is expected to be concluded during 2005 and the final report published in 2006. Interim results from the study will be reported during this period. We intend to publish experience and results from nondestructive testing during the first half of 2005. After the choice of welding method, we intend to start a feasibility study regarding the requirements for and possible usefulness of ultrasonic modelling. Plans call for the feasibility study to start during the second half of 2005. Digital radiography Survey of SKB’s system Modelling Simulation Optimization of methodology Defect description POD simulation NDT reliability Generation of defects NDT at SKB Evaluation of defect incidence Results POD, ROC Figure 6-23. Flow chart (project “NDT Reliability” at BAM). 86 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
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 and 78: Nondestructive testing methods such
Page 79: a b Through-transmission Reflection
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
Page 129 and 130: 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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