RD&D-Programme 2004 - SKB

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Programme The intention is to supplement the report /15-4/ with information on Mox fuel and possibly some other type of fuel. The alternative would be to recalculate nuclide content, activity and decay heat for “standard BWR and PWR” as well as Mox, but it is uncertain whether this would provide any additional information. It would, however, be an advantage if the calculations were done in the same way, and this would provide new material for comparison. In order to be able to perform all the different types of calculations that will be needed, it is important to define a model canister with a standard nuclide content so that the canister’s decay heat output is 1,700 W. 15.1.8 Gap inventory Conclusions in RD&D 2001 and its review Experiments in a hydrogen gas environment with fuel pellets of varying burnup and irradiation history were planned. If possible, such pellets were to be used where the release of fission gas had already been determined. SKI proposed studies of the occurrence of radionuclides as a function of time and space in the gap and grain boundaries. Newfound knowledge since RD&D 2001 Tests where a hydrogen-saturated solution is forced through fuel pellets proved to be complicated and require great resources. They are therefore still under planning and development. Various methods for sealing fuel pellets have been tested during the period, and analysis methods for certain readily soluble radionuclides have been described in preparation for a more systematic study. Programme The method needs to be further tested. If the results are promising, a systematic study of the gap inventory as a function of burnup and other fuel parameters will be started. 15.1.9 Material composition Conclusions in RD&D 2001 and its review SKB decided to conduct a study of the importance of non-radioactive fission products prior to the next safety assessment. No direct viewpoints on this were offered in the review. Newfound knowledge since RD&D 2001 No new knowledge has been forthcoming. Programme The strategy remains as outlined in RD&D 2001. 15.1.10 Water composition Under deposition conditions where water occurs in vapour form, see section 15.1.11 below. RD&D-Programme 2004 167
15.1.11 Gas composition Conclusions in RD&D 2001 and its review RD&D 2001 did not include any research programme for this area, and no direct viewpoints were offered in the review. Newfound knowledge since RD&D 2001 The largest quantity of water in a canister reported in previous research programmes was 50 grams. This may be an optimistic figure, and 600 grams has now been given as a realistic upper limit. Programme The consequences of more water entering the canister must be studied. By filling the canister with argon (section 8.1.1), the gas composition inside the canister can be changed from air and water vapour to an inert gas and water vapour, see also section 15.2.9. 15.2 Processes in fuel/cavity A number of processes will with time alter the state in the fuel and in the canister’s cavity. Some take place in any circumstances, while many others only occur if the isolation of the copper canister is breached and water enters the canister. 15.2.1 Overview of processes The radionuclides in the fuel will eventually be transformed into non-radioactive substances by radioactive decay. This process gives rise to alpha, beta, gamma and neutron radiation which, by interaction with the fuel itself and with surrounding materials, is attenuated and converted to thermal energy. The temperature in the fuel is changed by heat transport in the form of conduction and radiation, and heat is removed to the surroundings. The temperature change will lead to some thermal expansion of the fuel’s constituents. This can, in combination with the helium formation caused by the alpha radiation, lead to rupture of the cladding tubes in the fuel. In an intact canister, radiolysis of residual gases in the cavity will lead to the formation of small quantities of corrosive gases, which could contribute to stress corrosion cracking (SCC) of the cast iron insert. If the copper canister is not intact, water may enter the canister cavity, radically altering the chemical environment. Radiolysis of the water in the cavity will further alter the chemical environment. The water in the canister causes corrosion of cladding tubes and other metal parts in the fuel. If the cladding tubes’ isolation should be breached initially or later by corrosion or mechanical stresses, the fuel will come into contact with water. This leads to dissolution of radionuclides that have collected on the surface of the fuel matrix, and to dissolution or transformation of the fuel matrix and release of radionuclides. The radionuclides may either be dissolved in the water, rendering them accessible for transport, or precipitate in solid phases in the canister void. This is determined by the chemical conditions in the canister cavity. On dissolution of the fuel, colloids with radionuclides may also form. Radionuclides dissolved in water can be transported with mobile water in the canister (advection) or by diffusion in stagnant water. Colloids carrying radionuclides can be transported in the same way. Nuclides dissolved in water can be sorbed to the different materials in the canister. Certain nuclides can also be transported in the gas phase. Finally, water can attenuate the energy of neutrons in the canister cavity. Low-energy neutrons can subsequently cause fission of certain nuclides in the fuel, releasing more neutrons. If conditions are unfavourable, criticality may be achieved, i.e. the process becomes self-sustaining. 168 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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Page 111 and 112: Judgement with regard to long-term
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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: Newfound knowledge since RD&D 2001
Page 125 and 126: Conclusions in RD&D 2001 and its re
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
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Page 155 and 156: 15.1.2 Geometry The deep repository
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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 177 and 178: 16.2.3 Heat transport No new knowle
Page 179 and 180: Programme The ongoing experiments w
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
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Page 207 and 208: • 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
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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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RD&D-Programme 2004 - SKB

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