Scientific basis for nuclear waste management XXXVI : symposium held November 25 - 30, 2012, Boston, Massachusetts, U.S.A. ; [Symposium LL, Scientific Basis for Nuclear Waste Management XXXVI, was held ... at the 2012 MRS fall meeting] (Englisch)
- Neue Suche nach: Hyatt, Neil
2013
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ISBN:
- Konferenzband / Print
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Titel:Scientific basis for nuclear waste management XXXVI : symposium held November 25 - 30, 2012, Boston, Massachusetts, U.S.A. ; [Symposium LL, Scientific Basis for Nuclear Waste Management XXXVI, was held ... at the 2012 MRS fall meeting]
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Beteiligte:
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Kongress:Symposium LL Scientific Basis for Nuclear Waste Management ; 36 ; 2012 ; Boston, Mass.
Fall meeting. Materials Research Society (MRS) ; 2012 ; Boston, Mass. -
Erschienen in:
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Verlag:
- Neue Suche nach: Cambridge Univ. Press
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Erscheinungsort:New York, NY
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Erscheinungsdatum:2013
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Format / Umfang:XIII, 285 S.
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Anmerkungen:Ill., graph. Darst., Kt.
Literaturangaben -
ISBN:
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Medientyp:Konferenzband
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Format:Print
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Sprache:Englisch
- Neue Suche nach: 58.54
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- Neue Suche nach: 621.4838
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Inhaltsverzeichnis Konferenzband
Die Inhaltsverzeichnisse werden automatisch erzeugt und basieren auf den im Index des TIB-Portals verfügbaren Einzelnachweisen der enthaltenen Beiträge. Die Anzeige der Inhaltsverzeichnisse kann daher unvollständig oder lückenhaft sein.
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The Use of High Durability Alumino-borosilicate Glass for the Encapsulation of High Temperature Reactor (HTR) FuelHeath, P.G. / Stennett, M.C. / McGann, O.J. / Hand, R.J. / Hyatt, N.C. / Materials Research Society et al. | 2013
- 9
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Long-term Aqueous Alteration Kinetics of an Alpha-doped SON68 borosilicate glassTribet, M. / Rolland, S. / Peuget, S. / Magnin, M. / Broudic, V. / Janssen, A. / Wiss, T. / Jegou, C. / Toulhoat, P. / Materials Research Society et al. | 2013
- 15
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Corrosion and Alteration of Lead Borate Glass in Bentonite Equilibrated WaterMukunoki, A. / Chiba, T. / Kikuchi, T. / Sakuragi, T. / Owada, H. / Kogure, T. / Materials Research Society et al. | 2013
- 21
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Vitrification of High Molybdenum Feeds in the Presence of Reprocessing Waste LiquorShort, R. / Dunnett, B. / Gribble, N. / Steel, H. / Steele, C.J. / Materials Research Society et al. | 2013
- 41
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The Effect of gamma -radiation on Mechanical Properties of Model UK Nuclear Waste GlassesMcGann, O.J. / Gandy, A.S. / Bingham, P.A. / Hand, R.J. / Hyatt, N.C. / Materials Research Society et al. | 2013
- 47
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Structural Characterization and Analysis of Glasses in the Al~2O~3-B~2O~3-Fe~2O~3-Na~2O-SiO~2 SystemStefanovsky, S.V. / Nikonov, B.S. / Omelyanenko, B.I. / Fox, K.M. / Marra, J.C. / Materials Research Society et al. | 2013
- 53
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Infrared and Raman Spectroscopic Study of Glasses in the Al~2O~3-B~2O~3-Fe~2O~3-Na~2O-SiO~2 SystemStefanovsky, S.V. / Fox, K.M. / Marra, J.C. / Materials Research Society et al. | 2013
- 59
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XAFS Study of Fe K Edge in Al~2O~3-B~2O~3-Fe~2O~3-Na~2O-SiO~2 GlassesStefanovsky, S.V. / Shiryaev, A.A. / Zubavichus, Y.V. / Fox, K.M. / Marra, J.C. / Materials Research Society et al. | 2013
- 67
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Thermal Conversion of Cs-exchanged IONSIV IE-911 into a Novel Caesium Ceramic Wasteform by Hot Isostatic PressingChen, T.-Y. / Hriljac, J.A. / Gandy, A.S. / Stennett, M.C. / Hyatt, N.C. / Maddrell, E.R. / Materials Research Society et al. | 2013
- 73
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Aging Studies of Pu-238 and -239 Containing Calcium Phosphate Ceramic Waste-formsFong, S.K. / Metcalfe, B.L. / Scheele, R.D. / Strachan, D.M. / Materials Research Society et al. | 2013
- 79
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Development of the Synthetic Rock Technique for the Immobilization of Iodine: Kinetics of the Alumina Matrix Dissolution under High Alkaline ConditionsMiyakawa, H. / Sakuragi, T. / Owada, H. / Kato, O. / Masuda, K. / Materials Research Society et al. | 2013
- 85
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A Study on Iodine Release Behavior from Iodine-immobilizing Cement SolidHaruguchi, Y. / Higuchi, S. / Obata, M. / Sakuragi, T. / Takahashi, R. / Owada, H. / Materials Research Society et al. | 2013
- 91
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Towards a Silicate Matrix for the Immobilisation of Halide-rich WastesGilbert, M.R. / Materials Research Society et al. | 2013
- 97
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Decontamination of Molten Salt Wastes for Pyrochemical Reprocessing of Nuclear FuelsStennett, M.C. / Hand, M.L. / Hyatt, N.C. / Materials Research Society et al. | 2013
- 103
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Thermodynamic Modeling and Experimental Tests of Irradiated Graphite Molten Salt DecontaminationKarlina, O. / Ojovan, M. / Pavlova, G. / Klimov, V. / Materials Research Society et al. | 2013
- 111
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Ceramic Immobilisation Options for TechnetiumStennett, M.C. / Backhouse, D.J. / Freeman, C.L. / Hyatt, N.C. / Materials Research Society et al. | 2013
- 117
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Technetium Incorporation into C14 and C15 Laves Intermetallic PhasesBuck, E.C. / Schemer-Kohrn, A.L. / Wierschke, J.B. / Materials Research Society et al. | 2013
- 123
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Technetium-99m Transport and Immobilisation in Porous Media: Development of a Novel Nuclear Imaging TechniqueCorkhill, C.L. / Bridge, J.W. / Hillel, P. / Gardner, L.J. / Banwart, S.A. / Hyatt, N.C. / Materials Research Society et al. | 2013
- 133
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Modelling the Activation of H~2 on Spent Fuel Surface and Inhibiting Effect of UO~2 DissolutionDuro, L. / Riba, O. / Martinez-Esparza, A. / Bruno, J. / Materials Research Society et al. | 2013
- 139
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Corrosion Study of SIMFUEL in Aerated Carbonate Solution Containing Calcium and SilicateJung, H. / Ahn, T. / Pabalan, R. / Pickett, D. / Materials Research Society et al. | 2013
- 145
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Effects of Matrix Composition on Instant Release Fractions from High Burn-up Nuclear FuelRoth, O. / Low, J. / Granfors, M. / Spahiu, K. / Materials Research Society et al. | 2013
- 151
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Reducing the Uncertainty of Nuclear Fuel Dissolution: An Investigation of UO~2 analogue CeO~2Corkhill, C.L. / Bailey, D.J. / Thornber, S.M. / Stennett, M.C. / Hyatt, N.C. / Materials Research Society et al. | 2013
- 157
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Research and Development on Cementation of Liquid Radioactive Waste (LRW) Resulting from Spent Nuclear Fuel Reprocessing in the Experimental Demonstration Center (EDC) of Mountain Chemical CombineLebedeva, A.V. / Sukhanov, L.P. / Ustinov, O.A. / Materials Research Society et al. | 2013
- 167
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NMR Study of Interlayer and Non-interlayer Porewater in Water-saturated Bentonite and MontmorilloniteCarlsson, T. / Muurinen, A. / Root, A. / Materials Research Society et al. | 2013
- 173
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Long-term Corrosion of Zircaloy-4 and Zircaloy-2 by Continuous Hydrogen Measurement under Repository ConditionSakuragi, T. / Miyakawa, H. / Nishimura, T. / Tateishi, T. / Materials Research Society et al. | 2013
- 179
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Radioelement Solubilities in SR-Site, the Influence of Variability and UncertaintyDahlberg, C.G. / Sellin, P. / Grive, M. / Duro, L. / Spahiu, K. / Materials Research Society et al. | 2013
- 185
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Glass-iron-clay Interactions in a Radioactive Waste Geological Disposal: A Multiscale ApproachRebiscoul, D. / Burger, E. / Bruguier, F. / Godon, N. / Chouchan, J.-L. / Mestre, J.-P. / Frugier, P. / Lartigue, J.-E. / Gin, S. / Materials Research Society et al. | 2013
- 191
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Suitability of Bioapatite as Backfill Material for Nuclear Waste IsolationFinlay, A.J. / Drewicz, A.E. / Terry, D.O. / Grandstaff, D.E. / Ash, R.D. / Materials Research Society et al. | 2013
- 197
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Collocation and Integration of Back-End Fuel Cycle Facilities with the Repository: Implications for Waste FormsForsberg, C. / Materials Research Society et al. | 2013
- 203
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Processing and Disposal of Radioactive Waste: Selection of Technical SolutionsOjovan, M.I. / Drace, Z. / Materials Research Society et al. | 2013
- 211
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Assessment of the Evolution of the Redox Conditions in the SKB ILW-LLW SFR-1 Repository (Sweden)Duro, L. / Domenech, C. / Grive, M. / Roman-Ross, G. / Bruno, J. / Kallstrom, K. / Materials Research Society et al. | 2013
- 217
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Characterization of Radionuclide Retaining Properties of Backfill Materials for Near Surface Repositories for Low and Intermediate Level Radioactive WastesOstashkina, E.E. / Varlakova, G.A. / Golubeva, Z.I. / Materials Research Society et al. | 2013
- 225
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Some Experiments on Sorption Behavior of Iodide Ions into CSH Gel under the Condition Saturated with Saline GroundwaterNiibori, Y. / Funabashi, T. / Mimura, H. / Materials Research Society et al. | 2013
- 231
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Sorption Behavior of Nickel and Palladium in the Presence of NH~3(aq)/NH~4^+Kobayashi, T. / Sasaki, T. / Ueda, K.-y. / Kitamura, A. / Materials Research Society et al. | 2013
- 237
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Sensitivity Analysis for the Scenarios on Deterioration or Loss of Safety Functions Expected in Disposal System Due to Human Error on Application of Engineering TechnologyTakeda, S. / Inoue, Y. / Kimura, H. / Materials Research Society et al. | 2013
- 245
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Decontamination Pilot Projects: Building a Knowledge Base for Fukushima Environmental RemediationMiyahara, K. / Tokizawa, T. / Nakayama, S. / Materials Research Society et al. | 2013
- 257
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Research and Development Activities for Cleanup of the Fukushima Daiichi Nuclear Power StationSasaki, T. / Kaminishi, S. / Miyamoto, Y. / Funasaka, H. / Materials Research Society et al. | 2013
- 269
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Decontamination of School Facilities in Fukushima-cityYoshikawa, H. / Iijima, K. / Sasamoto, H. / Fujiwara, K. / Mitsui, S. / Kitamura, A. / Kurikami, H. / Tokizawa, T. / Yui, M. / Nakayama, S. et al. | 2013
- 277
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Investigation and Research on Depth Distribution in Soil of Radionuclides Released by the TEPCO Fukushima Dai-ichi Nuclear Power Plant AccidentSato, H. / Niizato, T. / Amano, K. / Tanaka, S. / Aoki, K. / Materials Research Society et al. | 2013