RD&D-Programme 2004 - SKB

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after the end of the delay time. Sorption of radionuclides to the internal parts of the canister is neglected. Conclusions in RD&D 2001 and its review SKI questions whether it is possible to obtain an improved understanding of the transport phenomena by using a simple analytical model. According to SKI, it is not clear whether SKB has improved the description of the transport and reaction processes included in Comp23. Newfound knowledge since RD&D 2001 As a complement to and for evaluation of the near-field code used in SR 97, Comp23, an alternative code, Compulink, has been developed. This alternative code is based on the same conceptual model as Comp23 and includes the same processes; the two codes should therefore yield comparable results. Like the whole Proper package, Comp23 is written in Fortran 77, while the alternative code is written as an application that is run in a Matlab and Simulink environment. (Information on Matlab and Simulink is available on the Web at http://www.mathworks. com/). Matlab is a well-established commercial program that is used to solve various types of numerical problems. Matlab also contains a script language that makes it possible to write programs and/or applications where Matlab’s own commands are used. This makes it possible to change parameters, start simulations and save results, which in turn makes it possible to carry out probabilistic simulations based on random number distributions generated either directly in Matlab or by a free-standing program. Simulink is a program package that supplements Matlab and contains routines for carrying out simulations in a graphic environment, offering the possibility of easily combining different computation modules and thereby easily simulating complex models. We believe that Simulink’s graphic environment, in combination with Matlab’s built-in mathematical functions, make a model implementation in Compulink even more easily accessible and comprehensible for developers and reviewers than the existing Fortran 77 implementation in the Proper package. The lower learning threshold also allows access to a larger group of developers, making the development work less sensitive to changes in the development team. At present the Compulink application has been developed on a Windows PC, but since applications developed in Matlab and Simulink can be run on several platforms (Windows, Unix/Linux or Macintosh OS X), the porting work connected with platform changes is minimized. Near-field releases calculated with Compulink show good agreement with Comp23. Figure 18-2 shows releases from the near-field to the geosphere for a test case where an initial canister defect occurs after 6,500 years and a larger defect after 25,000 years. The agreement between the releases from the two codes is good for all nuclides. The computation time for the Compulink simulation on an office computer (1,700 MHz Pentium 4 and Windows XP operating system) is around one minute per realization, which makes the code suitable for probabilistic simulations too. Programme The development of the Simulink-Matlab implementation of Compulink will continue during the coming period; among other things, the user interface must be improved so that selection of input data is simplified. Some of this work will be pursued in cooperation with the development of a new Matlab-Simulink-based code for biosphere simulations. The software development of Comp23 will, on the other hand, not continue at the same rate as before during the coming three-year period. The reason for this is not that development resources are being shifted from Comp23 to Compulink, but that the development need is not as great as before. There are however areas where refinements and implementations of models are possible. An example is models for fuel dissolution, where development of new models is taking place. RD&D-Programme 2004 241
10 –5 I-129 Release rate (moles/year) 10 –6 10 –7 10 –8 Cs-135 I-129 Ni-59 Cs-135 U-235 Cl-36 U-238 U-234 Sn-126 Se-79 Tc-99 Ni-59 U-235 U-238 Cs-135 I-129 Th-230 10 –9 C-14 Nb-94 C-14 Th-230 10 –4 Pu-242 Nb-94 Ra-226 Cl-36 Pa-231 Cl-36 10 –10 Pu-239 10 3 10 4 Sn-126 10 5 10 6 Time (years) Figure 18-2. Release from the near-field for a realistic test case from Comp23 (circles) and Compulink (lines). 242 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
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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
Page 181 and 182: Newfound knowledge since RD&D 2001
Page 183 and 184: Programme Short-term tests aimed at
Page 185 and 186: Swelling properties The buffer must
Page 189 and 190: have been performed for some ten co
Page 191 and 192: 17.1.13 Impurity levels Bentonite i
Page 193 and 194: out when the buffer swells, but our
Page 195 and 196: These processes have been studied i
Page 199 and 200: • The gas injection phase will be
Page 203 and 204: Conclusions in RD&D 2001 and its re
Page 205 and 206: 19 9 D=205 d=175 D=172 d=170 D=168
Page 207 and 208: • Tests of the wetting process cl
Page 211 and 212: Figure 17-4. Natural redox front in
Page 213 and 214: These phenomena have been studied b
Page 215 and 216: 17.2.24 Radionuclide transport - ad
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Page 219 and 220: 18.1.6 Smectite content SKB, togeth
Page 221 and 222: Programme See section 18.2.2. 18.1.
Page 223 and 224: The wetting of the backfill from th
Page 225 and 226: Conclusions in RD&D 2001 and its re
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Page 229 and 230: Programme See section 17.2.17. 18.2
Page 231: 18.2.23 Radionuclide transport - so
Page 235 and 236: and the rock matrix, is also crucia
Page 237 and 238: A thermal model will be constructed
Page 239 and 240: In a continuation of the super-regi
Page 241 and 242: A thorough overview has been done o
Page 243 and 244: The authorities are of the opinion
Page 247 and 248: 19.2.11 Advection/mixing - groundwa
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Page 251 and 252: Diffusion measurements in the labor
Page 253 and 254: Uranium series analyses from clay-
Page 255 and 256: 19.2.18 Microbial processes Conclus
Page 257 and 258: 19.2.20 Colloid formation - colloid
Page 259 and 260: 19.2.23 Methane ice formation Concl
Page 261 and 262: 19.2.26 Integrated modelling - radi
Page 263 and 264: development that has taken place ha
Page 265 and 266: 20.2 Review of RD&D 2001 Following
Page 267 and 268: work will continue, particularly in
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Page 271 and 272: The above work will be pursued in c
Page 273 and 274: certain substances, such as uranium
Page 275 and 276: In connection with the Safe project
Page 277 and 278: 20.9 International work and dissemi
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Page 281 and 282: 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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