Annual Report 2009/2010 - JUWEL - Forschungszentrum Jülich

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The Product Control Group has to conduct studies in order to assess the suitability of various coating materials. Those investigations proof, whether these new coating materials are in line with the disposal conditions requirements for radioactive waste „Anforderungen an endzulagernde radioaktive Abfälle - Schachtanlage Konrad [1] (Stand: Dezember 1995)”. Polyurethan coating The coating with polyurethane is the most developed process in the industrial application. A polyurethane coating is used as corrosion protection for the walls at the dock "Benser - Siel" in a long time test. There, the materials demonstrated the effectiveness as a corrosion protection for more than 20 years. The investigations by the Department of Materials Technology at the University of Dortmund also assess the suitability as a long-term corrosion protection. In nuclear technology polyurethane was initially used as corrosion protection for KONRAD containers. The coating of waste products can be used for corrosion protection as well and on the other hand; the material properties of polyurethane can be used as a further protective effect for the waste products. The coating with polyurethane avoids the penetration of oxygen in hygroscopic waste other chemical reactions in the waste products can be blocked also. The basic property such as fire behaviour and thermal properties of polyurethane were examined in the approval of the coating material as a coating for disposal containers. The PKS evaluation covers the technical suitability for coating material for waste products (water permeability, impact strength). Several techniques are used for the application of polyurethane. The common techniques for the coating of KONRAD – containers and barrels are spray proceedings (Fig. 142), while the coating of super compacted waste is made by cast proceedings (Fig. 143). Fig. 142: Coating with Polyurethane Fig. 143: Pellet in a cast form Results The PKS's own assessments concerning the acceptability for reposition of new coating materials have shown that the polyurethane coating of radioactive waste products is adequate. 201
Polysiloxane which has been investigated alternatively at the beginning is not suitable as a coating. Because this material is permeable to air it has only got a limited protective function. The coating of radioactive waste products or containers with polyurethane can be used in cast proceeding as well as spraying procedures. For drums and containers the spray technique turned out to be advantageous. For super compacted waste (pellets) the cast proceeding has got considerable advantages. The suitability of polyurethane as corrosion protection has been demonstrated by studies at the University of Dortmund and in practice by the coating of a port basin. For reasons of economy the polyurethane coating is used only for problem waste. The coating meets the demands of the final repository for radioactive waste “Schachtanlage KONRAD”. References [1] Peter Brennecke, Bundesamt für Strahlenschutz, Fachbereich Nukleare Entsorgung und Transport, Salzgitter: „Anforderungen an endzulagernde radioaktive Abfälle“ (Endlagerungsbedingungen, Stand: Dezember 1995) – Schachtanlage Konrad –, Dezember 1995, ET-IB-79 [2] Prof. Dr.-Ing. Friedrich-Wilhelm Bach, Lehrstuhl für Werkstofftechnologie, Fakultät Maschinenbau, Universität Dortmund: „Prüfbericht: Langzeituntersuchungen von PU - beschichteten Proben“, 2000 [3] Prof. Dr. R. Odoj, FZJ, Dr. S. Maischak, FZJ, W. Pfeifer, FZK, L Valencia, FZK, L. Schneider, A. Rohr and C. Herzog, Stoller Ingenieurtechnik: “Application of Polysiloxanes for the Treatment of Radioactive Waste to Guarantee Safe Long Term Storage”, Waste Management 2004 Symposium, Tucson, Arizona 2004 202
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Mitglied Mitglied der der Helmholtz
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Forschungszentrum Jülich GmbH Inst
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TABLE OF CONTENTS 1 Preface .......
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6.2.2 Doctoral Thesis .............
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state of NRW. The collaborative pro
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2 Institute’s Profile Due to the
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2.2. Organization chart Reactor Saf
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3 Key Research Topics 3.1. Long Ter
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actinide co-conversion into polyact
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Fig. 7: Non-destructive analytical
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Fig. 9: Thermal treatment of an AVR
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3.8. Product Quality Control of Rad
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3.8.2 Product Quality Control of Lo
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The advantage of working at low vac
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NdPO 4 powder sample, directly rece
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4.5. Non-destructive assay testing
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5 Scientific and Technical Reports
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Results and Discussion The irradiat
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work will focus on the identificati
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Different solvents (iso-propanol an
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e & j) Aggregates of aluminium oxid
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Experimental details The corrosion
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Intensity [CPS] 500 400 300 200 100
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Fig. 24: Left: High resolution TEM
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a) MD model [10] b) Derived Lesukit
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5.4. Minor actinide(III) recovery f
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Extensive extraction studies were p
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of the extraction properties of the
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Cm(III) together with the lanthanid
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using a mixture of CyMe4BTBP and TO
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A more challenging route studied wi
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These preliminary results show that
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The 1-cycle SANEX process is intend
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Continuous counter-current tests us
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Conclusion In this work, it was sho
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shaken by a vortex mixer for 15 min
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100 100 Distribution ratio 10 1 0.1
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Tab. 15: The distribution ratios of
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5.7. Synthesis and thermal treatmen
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Acid-Deficient Uranyl-Nitrate via d
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Optical investigation showed a noti
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TG /% 100 98 96 94 92 90 88 86 84 8
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Radiolysis in the aqueous solutions
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is about 4% while the one of the rh
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Fig. 59: Compressibility curve for
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Conclusion and outlook Monazite-typ
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Fig. 63: Description of the unit ce
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agents for the synthesis of neodymi
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100 TG 785°C Exo DSC 0,2 0,0 90 -0
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After synthesis the product was cen
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process of monazite and additional
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Tab. 18: Lattice parameters determi
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Conclusions For Sm 1-x Ce x PO 4 mo
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5.11. Raman Spectra of Synthetic Ra
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The numerical values of all measure
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knowledge, these special relationsh
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Fig. 80: Raman spectra of LaPO 4 ir
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5.12. MC simulation of thermal neut
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content was replaced by hydrogen. C
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constant for hydrogen concentration
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with a 0 1 -183.88 ± 8.55 and a 2
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5.13. An Improved Method for the no
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2 2 2 d0 R ds d0 dw la( )
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The relative uncertainty for the ac
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In the drum, 4 ‘hot spots’ for
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activity of Cs-137 is much more und
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gamma-ray detector approximated by
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shown in Fig. 96. In both cases the
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econstruction than the old calculat
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Neutron capture cross sections and
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Outlook The evaluated data will be
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from carbon-based HTR fuel elements
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Fig. 102: 3D volume reconstructions
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dislocate the 14 C atom from its pr
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It can be seen that nearly all trit
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Acknowledgement The authors like to
Page 155 and 156: development by investigations of ga
Page 157 and 158: Fig. 109: The left picture shows th
Page 159 and 160: [2] A European Roadmap for Developi
Page 161 and 162: from airborne SWIR Full Spectrum Im
Page 163 and 164: Fig. 113: Visualization of the vege
Page 165 and 166: number of training samples up to 19
Page 167 and 168: Acknowledgements The work presented
Page 169 and 170: three approaches has severe drawbac
Page 171 and 172: neighbours from the list of merge c
Page 173 and 174: it gives a difference in segmentati
Page 175 and 176: [6] I. Niemeyer, F. Bachmann, A. Jo
Page 177 and 178: Monitoring 3 cooperated intensively
Page 179 and 180: facilities and other treaty related
Page 181 and 182: parameters of the SAR system, such
Page 183 and 184: The MGD products used in the study
Page 185 and 186: Fig. 134 contains the result for th
Page 187 and 188: [2] H. Maître (ed.), Processing of
Page 189 and 190: Preparatory Committee to allocate t
Page 191 and 192: unconditional security assurances f
Page 193 and 194: safeguards was also requested. Deci
Page 195 and 196: [16] United Nations Security Counci
Page 197 and 198: 5.24. Development and Application o
Page 199 and 200: Hardware layer The hardware layer i
Page 201 and 202: So in most applications the scale u
Page 203 and 204: The ENDF-B/V and ENDF-B/VI librarie
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Page 209 and 210: acceptance requirements [3]. In the
Page 211 and 212: Fig. 145: List of description and d
Page 213 and 214: 6.1. Courses taught at universities
Page 215 and 216: Umwelt / Energy & Environment 2010;
Page 217 and 218: 6.5. Institute Seminar The IEK-6 or
Page 219 and 220: 6.5.3 Invited talks 2009 30.04.2009
Page 221 and 222: 21.09.2010 Dr. N. Evans: The Chemis
Page 223 and 224: 8 Selected R&D projects 8.1. EU pro
Page 225 and 226: K. Aymanns: Nominated as deputy re
Page 227 and 228: Bukaemskiy A.A., Barrier D., Modolo
Page 229 and 230: 11.2. Publications 2009 11.2.1 Jour
Page 231 and 232: Rezniczek, A.; Richter, B.; Jussofi
Page 233 and 234: Daniels, H.: Co-conversion of actin
Page 235 and 236: 11.3. Publications 2010 11.3.1 Jour
Page 237 and 238: Sypula, M.; Wilden, A.; Schreinemac
Page 239 and 240: (Partitioning) - Stabilitätsunters
Page 241 and 242: Modolo, G.; Bosbach, D.; Geist, A.;
Page 243 and 244: 12 How to reach us Postal Address F
Page 245 and 246: By train: Take the train from Aache
Page 247 and 248: Schriften des Forschungszentrums J
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Schriften des Forschungszentrums J
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Schriften des Forschungszentrums J
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