RD&D-Programme 2004 - SKB

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As mentioned above, fast reactors can be used for transmutation. During the 1990s, fuel research was focused on combustion of plutonium in sodium-cooled fast reactors. Special types of fuel were studied in France. In recent years, interest has also been directed towards gascooled fast reactors. The fast reactor can also be used for transmutation of other transuranics. However, this requires a special design in order to prevent serious deterioration of the dynamic and safety-related properties of the reactor. If the fast reactor is designed as a breeder reactor, very high level of energy recovery can be achieved from the mined uranium as well as an effective transmutation of all transuranics. Studies by the OECD/NEA indicate that a breeder reactor can extract up to 100 times more energy per tonne of natural uranium compared with a light-water reactor with direct disposal (once-through fuel cycle) /23-10/. The Russians are also interested in civilian applications of fast reactors cooled with liquid lead-bismuth. Furthermore, some work is being done on ADS with funding mainly through the so-called ISTC (International Science and Technology Centre) programme. As already mentioned, systems with a high flux of fast neutrons are of greatest interest when a virtually complete transmutation of all long-lived transuranics is desired. If one is content with transmutation of plutonium alone, however, other systems may also be used. French studies show that with specially designed fuel assemblies, the amount of plutonium generated by a light-water reactor park can be limited and stabilised. Studies by General Atomics in the USA and others have shown that a fuel can be developed for gas-cooled high-temperature reactors that permits a burn-up of up to 700 MWd/kg and combustion of more than 90 percent of the actinide content, including plutonium-239. Research in the EU Current research was dealt with to some extent in the previous section. As noted above, relatively large research programmes are under way in several countries. The biggest national programmes are in France, Japan and the USA. In the EU there is also considerable collaboration between the member states within projects partially funded by the European Commission. The scope of the EU programme for research on partitioning and transmutation has grown over the past decade, see Table 23-1. The EU’s Fifth Framework Programme is coordinated in so-called clusters associated with the EU’s Adopt network, whose purpose is to ensure coordination and consistency between the various EU project and the national programmes. Adopt is also trying to identify gaps in the programmes and is supposed to provide input for future research projects. With regard to transmutation, the projects are strongly focused on accelerator-driven systems. The biggest project is a preliminary design study of an accelerator-driven system: PDS-XADS. It is being led by Framatome in France and has no fewer than 25 participating partners. Fuel studies concerning plutonium and americium nitrides (Confirm), oxides (Future) and thorium fuels are included in the cluster Fuetra. A number of technological special studies have been gathered within Testra. They concern irradiation effects on materials, particularly windows, for spallation sources (Spire), technology for systems cooled with lead-bismuth (Tecla) and participation in the Megapie project at PSI involving testing of a spallation source with lead-bismuth. Basic data are being gathered within the projects included in Bastra. The Muse project involves reactor physics measurements on subcritical systems with a fast neutron spectrum and is being carried Table 23-1. Scope of the EU’s programme for research on partitioning and transmutation. Programme Period when projects EU grants in millions of euro for research and are approved and started development on partitioning and transmutation FWP 3 1991–1994 4.8 FWP 4 1994–1998 5.8 FWP 5 1999–2002 28.6 FWP 6 tentative 2003–2006 30–35 RD&D-Programme 2004 313
out in Cadarache, France. Hindas and N-TOF concern measurements of reaction cross-sections for neutrons with high energies etc. Pyrochemical partitioning processes were studied within Pyrorep. The project Partnew examined different organic compounds with a view towards possible use for partitioning of heavy transuranics. Calixpart studied organic compounds of another type for partitioning of e.g. actinides, cesium and technetium. Within the Sixth Framework Programme, all partitioning studies are coordinated within a so-called integrated project Europart, which started at the beginning of 2004. In a similar manner, a coordination of the transmutation projects within Eurotrans is planned. But this is not expected to start until early 2005 at the earliest. Research in Sweden The Department of Nuclear Chemistry at Chalmers University of Technology (CTH) has been conducting SKB-funded research on partitioning since 1991. The research on transmutation at the Royal Institute of Technology (KTH) in Stockholm is principally concentrated on accelerator-driven systems (ADS). The research at the Department of Nuclear and Reactor Physics has been supported by SKB since 1993. Projects for measurement of cross-sections for neutrons in the high-energy range 20 to 100 MeV are being carried out at The Svedberg Laboratory (TSL) and the Department of Neutron Research at the University of Uppsala. The projects are being funded in part by contributions from SKB, the nuclear power plants and SKI. The Swedish research groups are participating in several EU projects. The Department of Nuclear and Reactor Physics at KTH is the coordinator of the project Confirm, where plutonium nitride fuel (PuN fuel) will be irradiated at the R2 reactor in Studsvik. Additional EU projects where Swedish research groups are participating are PDS-XADS (KTH), Future (KTH), Spire (KTH), Tecla (KTH, Nuclear Safety is coordinator), Muse (KTH), Hindas (UU) and Partnew and the new Europart (CTH, Nuclear Chemistry is participating in both). In the Tecla project, a special circuit has been built in a laboratory at KTH for studying thermohydraulic conditions during lead-bismuth cooling. This project is being funded in the EU’s Fourth Framework Programme. A continuation is planned within the Sixth Framework Programme, as a part of Eurotrans, where, incidentally, both KTH and Uppsala University plan to participate. The Swedish research programme is being funded primarily by SKB and is partially coordinated with the EU projects in which the Swedish groups are participating. SKB has provided some support to all of these projects except Tecla. The results of the Swedish research are reported in various scientific publications. Furthermore, annual reports are compiled by the three groups at CTH, KTH and Uppsala University. The last three years’ reports /23-11 to 23-20/ contain summaries of the most important results as well as abstracts, reprints and/or references to the scientific papers. During the period 2001–2003, two doctorates, five licentiate degrees and five undergraduate degree projects have been based on work within the Swedish programme for Partitioning and Transmutation. In recent years, the nuclear chemistry group at CTH has increasingly tied their P&T research to the partially EU-funded projects described briefly above. The following are among the more important projects in recent years. The formation of nitrate complexes with promethium, europium, americium and curium has been investigated. The results of these studies will soon be ready for publication. Nitrate complex formation has also been investigated experimentally for other lanthanides. The basic chemical properties of bromodecanoic acid have been determined. It is important to know how this extraction reagent works when it is used in combination with various nitrogenbased synergy reagents. The results will hopefully be able to provide information on the extraction mechanism. The basic chemical properties of several nitrogen-based synergy reagents have further been studied. The results have been published for two of the reagents. Several other compounds, synthesized by the University of Reading, have also been tested, but the results are not yet ready for publication. 314 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
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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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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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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
Page 253 and 254: Uranium series analyses from clay-
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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
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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
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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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