MRS2017 - Scientific Basis for Nuclear Waste Management Symposium 2017

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Sessions*

Partitioning & Transmutation

Radionclide solubility, speciation, sorption & migration

ANSTO Tour

Repositories & Geological Disposal

Special topic on Tc and Re

Welcome Address

Function

Safeguards, Decontamination & Decommissioning

Spent Fuel & Zircaloy Cladding

National & International Waste Management Programs: Session Chairs Greg Lumpkin & Simone Richter

Registration

Ceramic and Glass-Ceramic Wasteforms

Glass Wasteforms

Radiation Damage

Poster Session

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Contributions*

(Scholarship application) Thermal Treatment of Magnox Sludge Intermediate Level Nuclear Waste through Vitrification (in session "Glass Wasteforms")

A New Method for Production of Glass-Y2Ti2O7 Pyrochlore (in session "Ceramic and Glass-Ceramic Wasteforms")

A study to develop a new glass formulation for the immobilisation of HLW containing molybdenum and large amounts of sodium. (in session "Glass Wasteforms")

Activation energy for parabolic corrosion kinetics of Zircaloy-4 by consecutive hydrogen measurement at 30 – 80℃ (in session "Spent Fuel & Zircaloy Cladding")

Advanced Materials and Processes for Application to the Back-end of the Nuclear Fuel Cycle (in session "Partitioning & Transmutation")

Advances in conditioning of low and intermediate nuclear waste (in session "National & International Waste Management Programs: Session Chairs Greg Lumpkin & Simone Richter")

Alkali technetium oxides and their relation to Tc loading in nuclear waste glasses (in session "Special topic on Tc and Re")

Alkali tin silicate glass as a wasteform for the immobilisation of plutonium (in session "Glass Wasteforms")

Ambient-Cured Geopolymers for Low Level Nuclear Waste Storage (in session "Radiation Damage")

Apparent Diffusion Coefficients Consistent with Sorption Derived Based on Changes in Depth Profiles of Radiocaesium in Soil Contaminated by the Fukushima Nuclear Accident and Future Prediction of Depth Profile (in session "Radionclide solubility, speciation, sorption & migration")

Application of Nuclear Waste Management and Remediation Experience and Lessons Learned (in session "Safeguards, Decontamination & Decommissioning")

Aqueous leaching of high burnup UO2 fuel under hydrogen conditions (in session "Spent Fuel & Zircaloy Cladding")

Atomistic simulation of interfaces in glass/crystal composites for nuclear waste forms (in session "Ceramic and Glass-Ceramic Wasteforms")

Behaviour of sand-bentonite buffer material of deep geological repository under high confining pressure (in session "Repositories & Geological Disposal")

Best Practice in the Management of Site Investigations for Geological Disposal Facilities (in session "Repositories & Geological Disposal")

Characterisation of the UK cement backfill material pre- and post- groundwater leaching experiments (in session "Repositories & Geological Disposal")

Chemical Durability of Borosilicate Glass-Ceramic High-Level Waste Form in Dilute and Static Conditions (in session "Glass Wasteforms")

Chornobyl NPP Cooling Pond: Decommissioning (in session "Safeguards, Decontamination & Decommissioning")

Comparison of calculated and measured radionuclide inventory of a Zircaloy-4 cladding tube plenum section (in session "Spent Fuel & Zircaloy Cladding")

Comparison of thermal expansion of Tc and Re salts. (in session "Special topic on Tc and Re")

Current advances on titanate-based glass-ceramics for actinide immobilization (in session "Ceramic and Glass-Ceramic Wasteforms")

Development of solid state MAS NMR techniques for the characterization of alteration products formed during the dissolution of spent nuclear fuel. (in session "Spent Fuel & Zircaloy Cladding")

Digital autoradiography on C-14 labelled PMMA impregnated rock samples using the Beaver$^{TM}$ (in session "Radionclide solubility, speciation, sorption & migration")

Dissolution Behavior of Lead Borate Glass under Simulated Geological Disposal Conditions (in session "Glass Wasteforms")

Effect of Carbonate on Lanthanides Migration Behavior in Compacted Bentonite (in session "Repositories & Geological Disposal")

Effect of platinoid elements on the dissolution of uranium dioxide (in session "Spent Fuel & Zircaloy Cladding")

Effect of thiosulfate on the SCC behavior of carbon steel welds exposed to concrete pore water under anoxic conditions (in session "Repositories & Geological Disposal")

Effects of Li, Ca, Fe, and B on NaAlSiO4 nepheline crystallization in high level waste glasses (in session "Glass Wasteforms")

Efficient remediation of radiodine with silver-functionalized silica aerogel (in session "Ceramic and Glass-Ceramic Wasteforms")

Emulsions as a powerful tool to design silica monoliths able to selectively uptake radioactive caesium (in session "Partitioning & Transmutation")

Functionalised Titania and Zirconia Materials for Selective Actinide and Lanthanide Separations (in session "Partitioning & Transmutation")

Highly porous and stable metal–organic frameworks for uranium extraction (in session "Partitioning & Transmutation")

Hot isostatic pressing of ion exchange materials, from the Fukushima and Sellafield sites, to produce ceramic wasteforms. (in session "Ceramic and Glass-Ceramic Wasteforms")

Identification of chemical form of stable carbon released from type 304 and 316 stainless-steel powders in alkaline solution and in acidic solution under low-oxygen condition (in session "Repositories & Geological Disposal")

Impact of lanthanide elements on the dissolution of uranium dioxide (in session "Spent Fuel & Zircaloy Cladding")

Inert matrix fuel deployment for reducing the plutonium stockpile in reactors (in session "Partitioning & Transmutation")

Interaction of nuclear safeguards and safety requirements when planning for waste disposal (in session "Safeguards, Decontamination & Decommissioning")

Investigating Local Defect Structures in Nuclear Waste Form Materials (in session "Radiation Damage")

Investigation of C-14 in the CRUD collected on the coolant filter for safety disposal of radioactive waste containing C-14 (I)- C-14 release behavior and thermal decomposition characteristics of crud particles collected from the coolant filter of commercial PWR - (in session "Radionclide solubility, speciation, sorption & migration")

Investigation of C-14 in the CRUD collected on the coolant filter for safety disposal of radioactive waste containing C-14 (II) –Chemical alternation of ion exchange resin under simulated condition in primary coolant of PWR – (in session "Radionclide solubility, speciation, sorption & migration")

Invited Lecture: Plutonium Waste Management in the UK (in session "National & International Waste Management Programs: Session Chairs Greg Lumpkin & Simone Richter")

Ion Beam Irradiation of Ceramic-glass Waste Form at ANSTO (in session "Radiation Damage")

Ion irradiation used as surrogate for neutron irradiation to understand nuclear graphite evolution during reactor operation: consequences for the long lived radionuclide’s behavior (in session "Radiation Damage")

Management of the Radioactive Waste arising from the Decommissioning of the WWR-S Research Reactor from IFIN-HH, Magurele, Romania (in session "Safeguards, Decontamination & Decommissioning")

Microparticle Production as Reference Materials for Particle Analysis Methods in Safeguards (in session "Safeguards, Decontamination & Decommissioning")

Modelling the Corrosion of Spent Nuclear Fuel Inside a failed Waste Container (in session "Spent Fuel & Zircaloy Cladding")

Multinational Waste Repositories: A South Australian Initiative (in session "National & International Waste Management Programs: Session Chairs Greg Lumpkin & Simone Richter")

NEW ASPECTS OF THE MECHANISM OF HYDROGEN EFFECT ON SPENT FUEL DISSOLUTION (in session "Spent Fuel & Zircaloy Cladding")

New aspects of U(V) chemistry in oxo-materials: from ambient to extreme conditions (in session "Ceramic and Glass-Ceramic Wasteforms")

New route for synthesis of Synroc-like ceramic using non-selective sorbent LHT-9 (in session "Ceramic and Glass-Ceramic Wasteforms")

Nuclear Waste Management update in Australia (in session "National & International Waste Management Programs: Session Chairs Greg Lumpkin & Simone Richter")

P-31 Nuclear Magnetic Resonance as a Probe of Plutonium Incorporation and Radiation Damage in Phosphates (in session "Radiation Damage")

Partitioning of Ce, as a Simulant for Pu, in a Multiphase Ceramic Nuclear Waste Form (in session "Ceramic and Glass-Ceramic Wasteforms")

Porosity distribution in a heterogeneous clay-rich fault core (in session "Repositories & Geological Disposal")

Preparation of Ln1-2xCaxThxPO4.nH2O rhabdophane-type as low precursors to monazite-Cheralite ceramics (in session "Ceramic and Glass-Ceramic Wasteforms")

Pyrolysis and Plasma applied to Nuclear ion Exchange Resins Treatment (in session "Partitioning & Transmutation")

Quantification of irradiation induced structural disorder in nuclear waste-form ceramics with µ-luminescence spectroscopy of lanthanides (in session "Radiation Damage")

Radiation stability study of melt processed and hot isostatically pressed multi-phase ceramic waste forms (in session "Radiation Damage")

Radioactive Iodine-129 Capture in Mixed Cation Sodalites: ab initio modelling (in session "Ceramic and Glass-Ceramic Wasteforms")

Radionuclide containing solid phases on the inner surface of a Zircaloy-4 cladding tube (in session "Spent Fuel & Zircaloy Cladding")

Radionuclide Sorption Behaviour on Fresh and Aged Cementitious Materials: A Comprehensive Database with 25 Elements (in session "Radiation Damage")

Simplified UK Magnox waste glass alteration layer characterisation using 29Si, 17O and 25Mg NMR techniques (in session "Glass Wasteforms")

Sodalite waste forms for iodine (in session "Ceramic and Glass-Ceramic Wasteforms")

Solubility of the rhabdophane, LnPO4.0.667 H2O (Ln = La to Dy): implications for the long-term stability of monazite matrices. (in session "Ceramic and Glass-Ceramic Wasteforms")

Status of Used Nuclear Fuel and Radioactive Waste Long-term Management Programs in Canada (in session "National & International Waste Management Programs: Session Chairs Greg Lumpkin & Simone Richter")

Structural incorporation of Cm3+ and Pu3+ in phosphate ceramics with monazite structure. (in session "Ceramic and Glass-Ceramic Wasteforms")

Synroc Waste Treatment Plant for fission-based Molybdenum-99 Production (in session "National & International Waste Management Programs: Session Chairs Greg Lumpkin & Simone Richter")

Synthesis and characterisation of rare Ce3NbO7 compounds for use as nuclear space batteries by neutron powder diffraction and X-ray absorption spectroscopy (in session "Ceramic and Glass-Ceramic Wasteforms")

Synthesis and characterization of brannerite UTi2O6 (in session "Ceramic and Glass-Ceramic Wasteforms")

Synthesis and Structure of Novel Oxide Compounds Containing RE = Y, Yb, Gd, Sm, and La and M = Zr, Ti, and Sn (in session "Ceramic and Glass-Ceramic Wasteforms")

Tc reduction by bacteria from soda lake (in session "Special topic on Tc and Re")

The Corrosion of Copper Nuclear Waste Containers under Deep Geologic Disposal ConditionsF (in session "Spent Fuel & Zircaloy Cladding")

The development of zirconolite glass-ceramics for the immobilisation of Pu-residues in the UK. (in session "Ceramic and Glass-Ceramic Wasteforms")

The Fabrication and Characterisation of Novel Complex Ceramic Oxides (Ln2TiO5) For Polyphase Ceramic Waste-Forms. (in session "Ceramic and Glass-Ceramic Wasteforms")

The Need for Integrating the Back End of the Nuclear Fuel Cycle (in session "National & International Waste Management Programs: Session Chairs Greg Lumpkin & Simone Richter")

Thorium incorporation in phosphates matrices: the case of xenotime (in session "Ceramic and Glass-Ceramic Wasteforms")

Towards a ‘3S toolbox’ for providing safety, security and safeguards at geological disposal of high-level radioactive waste and spent fuel (in session "Safeguards, Decontamination & Decommissioning")

Towards understanding the dissolution of vitrified nuclear waste in a cementitious geological disposal facility (in session "Glass Wasteforms")

U-rich ceramics for Spent Fuel or Acidic 99Mo Production ILW (in session "Ceramic and Glass-Ceramic Wasteforms")

Unique capabilities and methods for analysing nuclear waste form materials using ANSTO’s landmark infrastructure (in session "Ceramic and Glass-Ceramic Wasteforms")

Unusual redox neighborhood in technetium compounds (in session "Special topic on Tc and Re")

Include materials from selected contributions

Events scheduled on*

28/10/2017

29/10/2017

30/10/2017

31/10/2017

01/11/2017

02/11/2017

03/11/2017

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