RD&D-Programme 2004 - SKB

More documents

Recommendations

Info

The programme for the remaining development work and for building and operating the facilities is relatively well defined in terms of content and scope. Financially, there are few programmes with as good long-term prospects as the nuclear waste programme. The planning uncertainties that do exist mainly relate to society’s attitudes towards the nuclear waste programme, with the consequences this may have on decision processes and timetables. In the time perspective of the permit applications for the facilities in the nuclear waste programme (2006–2008), SKB is now well equipped and staffed for its mission. This applies to both key competencies and total manpower needs. There is, however, also a vulnerability in the form of insufficient redundancy within certain strategically important niches where qualified personnel are hard to find and/or take a long time to train. An example is system analyses and safety assessments, but the problem also exists in the geoscience, radiology and nuclear technology. Responsibility for identifying and eliminating such uncertainties in time rests with the company’s ongoing strategic human resources planning. When the permit applications have been submitted, the nuclear fuel programme will enter into a preparation phase prior to decisions regarding the facilities. It is then important to maintain continuity of competence, even though some uncertainty may exist with regard to the duration and outcome of the decision process. SKB’s main tasks during this phase will be to continue pursuing those activities that are not primarily affected by the decisions, to remain at the disposal of the decision-makers in different respects, and to make preparations for the establishment phase of both the encapsulation plant and the deep repository. Prior to the construction of the encapsulation plant and the deep repository, there is a great need for qualified, well-trained and well-prepared personnel for management of major construction projects, procurement and quality control. Building facilities is not in itself anything new for SKB, and the knowledge and skills gained from the construction of SFR, Clab and the Äspö HRL will comprise valuable core competencies. However, the deep repository is a much bigger project than the previous facilities. The construction phase requires competent and qualified contractors from different parts of the building sector, particularly rock construction. The ambitious plans that exist today for development of the country’s infrastructure are expected to contribute to a project volume that is sufficient to ensure continuity within this sector. To what extent resources will be available when the deep repository is to be built may determined by the timing of other large rock construction projects. Long-term development of the sector The development of key fields such as nuclear technology, radiation protection and geoscience, as well as the corresponding educational sectors, will in the long term be of great importance for the prospects of the nuclear waste programme to meet its future competence needs. Many of the senior positions in these areas (as well as in the entire nuclear power industry) are currently filled by persons with roots from the time when nuclear power was seen as a highly attractive and expansive future industry with a strong position in the educational system. Today this sector is said to be one of the mature industries that are finding it increasingly difficult to attract members of the younger generation. Active training and research programmes are vital in ensuring a future supply of qualified personnel. In the long run, the prospects of meeting future competence needs are highly dependent on what happens with nuclear power and nuclear engineering in Sweden and the rest of the world. The present-day situation in Sweden, with an unclear phase-out scenario, makes it difficult to judge both future competence needs and the prospects of meeting them. So far, however, fears of a shortage of competencies in the field of nuclear technology have proved unfounded, even though vigilance is certainly warranted. The radiation protection sector has expressed concern regarding the future availability of qualified personnel, especially at a stage when the nuclear power sector will be faced with the task of decommissioning the NPPs and managing the waste. 406 RD&D-Programme 2004
Appendix B Abbreviations Abaqus ACL Adopt ADS AECL AFCI Amber Andra Apse ASCII ATB ATW BAM Barra Bastra BEM Benchpar Big Bertha Bio42 Bioclim Biomass Biomat Biopath Bioprota Bios BNFL BWR CAD Calixpart CEA CEC Chan3D Chemlab Ciemat Clab Code Bright Comp23 Compass Compulink Confirm Connectflow Coup Finite-element computer code for strength calculations. Active Central Laboratory, Studsvik. EU project. Thematic network on advanced options for partitioning and transmutation. Accelerator-driven systems. Atomic Energy of Canada Ltd, Canada. Advanced fuel cycle initiative. Computer code for safety assessment (biosphere). Agence National Pour la Gestion des Dechets Radioactifs (Andra), France. Experiments at Äspö HRL, Pillar Stability Experiment. American standard code for information interchange. Transport casks for spent nuclear fuel and core components. Accelerator-driven transmutation of nuclear Waste. Bundesanstalt für Materialprüfung in Germany. Enresa project. EU project. Adopt cluster, Transmutation – Basic studies. Boundary element method. EU project. Benchmark tests and guidance on coupled processes for performance assessment of nuclear waste repositories. Full-scale test, swelling of bentonite. SKB’s computer code for calculation of radionuclide transport in the biosphere (Proper submodule). EU project. Modelling sequential biosphere systems under climate change for radioactive waste disposal. IAEA project. Programme on biosphere modelling and assessment. Computer code (biosphere) SKB’s computer code for radionuclide transport in the biosphere. International collaboration on key technical issues in biosphere aspects of assessment of the long-term safety of the deep repository. Biological iron oxides. British Nuclear Fuels Ltd. Boiling water reactor. Computer aided design. EU project. Cluster Partition, Selective extraction of minor actinides from high activity liquid waste by organised matrices. Commissariat à l’Energie Atomique. Cation exchange capacity. Computer code, channel network model in three dimensions. Measurement probe for investigations in boreholes, Äspö HRL. Research Centre for Energy, Environment and Technology in Spain. Central interim storage facility for spent nuclear fuel. Computer code for thermo-hydro-mechanical calculations. SKB’s computer code for calculation of radionuclide transport in the near-field (Proper submodule). Computer code for thermo-hydro-mechanical calculations. SKB’s computer code for calculation of radionuclide transport in the near-field (alternative to Comp23). EU project. Cluster Feutra, Collaboration on nitride fuel irradiation and modelling. Computer code for groundwater flow calculations. Computer code that handles transpiration, growth and nutrient uptake for vegetation. RD&D-Programme 2004 407
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 and 22:
Figure 1-4. Interior from the Canis
Page 23 and 24:
Siting SKB’s main alternative is
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 63 and 64:
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 71 and 72:
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 and 84:
SKB has devised a quality system fo
Page 85 and 86:
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:
Page 125 and 126:
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. •
Page 135 and 136:
Part III Safety assessment and rese
Page 137 and 138:
As a complement to the numerical mo
Page 139 and 140:
Table 13-2. Research on the initial
Page 141 and 142:
13.2.4 Backfill Together with Posiv
Page 143 and 144:
Table 13-3. Projects and experiment
Page 145 and 146:
spent nuclear fuel. It was neverthe
Page 147 and 148:
concepts or whose descriptions requ
Page 149 and 150:
14.2.2 Radionuclide transport and d
Page 151 and 152:
At present, the computational time
Page 153 and 154:
Inflow Nuclides in a soluble phase
Page 155 and 156:
15.1.2 Geometry The deep repository
Page 157 and 158:
7 6 BWR 55 MWd/tU PWR 42 MWd/tU PWR
Page 159 and 160:
15.1.11 Gas composition Conclusions
Page 161 and 162:
15.2.5 Heat transport Dealt with in
Page 163 and 164:
simulating the repository environme
Page 165 and 166:
238 U 237 Np 239 Pu Concentration,
Page 167 and 168:
The catalytic effect of uranium dio
Page 169 and 170:
oxidant consumption in the bulk sol
Page 171 and 172:
The influence of hydrogen peroxide
Page 173 and 174:
A research programme to study cast
Page 175 and 176:
Page 177 and 178:
16.2.3 Heat transport No new knowle
Page 179 and 180:
Programme The ongoing experiments w
Page 181 and 182:
Page 183 and 184:
Programme Short-term tests aimed at
Page 185 and 186:
Swelling properties The buffer must
Page 187 and 188:
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 197 and 198:
Page 199 and 200:
• The gas injection phase will be
Page 201 and 202:
Page 203 and 204:
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 209 and 210:
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
Page 217 and 218:
Programme SKB does not consider sor
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:
Page 227 and 228:
ackfill must have a compression mod
Page 229 and 230:
Programme See section 17.2.17. 18.2
Page 231 and 232:
18.2.23 Radionuclide transport - so
Page 233 and 234:
10 -5 I-129 Release rate (moles/yea
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 245 and 246:
Page 247 and 248:
19.2.11 Advection/mixing - groundwa
Page 249 and 250:
a so-called Markov-directed Random
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
Page 269 and 270:
2 In Sea (mol) 3 Water Sea (mol/m 3
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
Page 279 and 280:
the underlying material are current
Page 281 and 282:
These reports describe dominant fun
Page 283 and 284:
Glacial Permafrost Permafrost Borea
Page 285 and 286:
Shoreline displacement has an isost
Page 287 and 288:
The hydromechanical modellings that
Page 289 and 290:
model that includes these factors a
Page 291 and 292:
The salinity of the sea, inland sea
Page 293 and 294:
• Public opinion and attitudes -
Page 295 and 296:
Socioeconomic impact • Local deve
Page 297 and 298:
Previously existing material is bei
Page 299 and 300:
• The driving forces behind the d
Page 301 and 302:
• Very effective methods for tran
Page 303 and 304:
• A subcritical nuclear reactor w
Page 305 and 306:
out in Cadarache, France. Hindas an
Page 307 and 308:
Important results since 2001 includ
Page 309 and 310:
Programme The goal of SKB’s resea
Page 311 and 312:
Kasam says that disposal in Very De
Page 313 and 314:
24 Decommissioning The facilities c
Page 315 and 316:
SKB is responsible for management a
Page 317 and 318:
25 Low- and intermediate-level wast
Page 319 and 320:
25.2.1 Repository for short-lived L
Page 321 and 322:
Programme Work on the design of the
Page 323 and 324:
observation is that isosaccharinic
Page 325 and 326:
stored so that the material can be
Page 327 and 328:
6-4 Claesson S, 2004. Elektronstrå
Page 329 and 330:
Chapter 14 14-1 SKB, 2004. Interim
Page 331 and 332:
15-42 Ekeroth E, Jonsson M, 2003. O
Page 333 and 334:
17-19 Le Bell J C, 1978. Colloid ch
Page 335 and 336:
19-29 Hudson J (ed), 2002. Strategy
Page 337 and 338:
19-77 Bath A, Milodowski A, Ruotsal
Page 339 and 340:
20-19 Kautsky U (ed), 2001. The bio
Page 341 and 342:
20-73 Blomqvist P, Jansson P-E, Esp
Page 343 and 344: 20-119 Berggren J, Kyläkorpi L, 20
Page 345 and 346: 23-10 NEA, 2002. Accelerator-driven
Page 347 and 348: SKB’s master plan Appendix A
Page 349 and 350: A1 Introduction A1.1 Background The
Page 351 and 352: generations unnecessarily. Another
Page 353 and 354: Encapsulation plant 2003 2004 2005
Page 355 and 356: facilitated by the fact that the re
Page 357 and 358: A2.3 System design A2.3.1 Fundament
Page 359 and 360: The system analyses will be largely
Page 361 and 362: Two safety reports will therefore b
Page 363 and 364: KBS-3H Basic Design Detailed engine
Page 365 and 366: Time horizon 2017 The current phase
Page 367 and 368: 2003 2004 2005 2006 2007 2008 Phase
Page 369 and 370: In the subsequent phase, verificati
Page 371 and 372: The canister development work will
Page 373 and 374: Deep repository Year 2003 2004 2005
Page 375 and 376: A4.2 Site investigations Site inves
Page 377 and 378: Already in the feasibility study, l
Page 379 and 380: In step D2, the facility descriptio
Page 381 and 382: Table 4. Current situation and prel
Page 383 and 384: 2003 2004 2005 2006 2007 2008 Desig
Page 385 and 386: Table 5. Continued. Technology issu
Page 387 and 388: A4.6.1 Siting factors Before priori
Page 389 and 390: A possible alternative scenario is
Page 391 and 392: of the NPPs starts, however, long-l
Page 393: Between now and 2008, an organizati
Page 397 and 398: GIA Gis Goldsim Hindas HMC HPF HRL
Page 399 and 400: PMMA POD Posiva Prism Proper Protot
Page 401: ISSN 1404-0344 CM Digitaltryck AB,
show all

RD&D-Programme 2004 - SKB

You also want an ePaper? Increase the reach of your titles

Delete template?

Save as template?