Prof.
Michael Ojovan
(International Atomic Energy Agency), Dr
Miklos (Mike) Garamszeghy
(Nuclear Waste Management Organization, Canada)
30/10/2017, 09:45
National and international collaborative waste management programs
Oral Presentation
Radioactive waste with widely varying characteristics is generated from the operation and maintenance of nuclear reactors, nuclear fuel cycle facilities, research facilities and medical facilities and the through the use of radioisotopes in industrial applications. The waste needs to be treated and conditioned as necessary to provide wasteforms acceptable for safe storage and disposal....
Mr
Hefin Griffiths
(ANSTO)
30/10/2017, 10:15
National and international collaborative waste management programs
Oral Presentation
Australia is currently in the process of establishing a National Radioactive Waste Management Facility and seeking to identify a site to host the facility.
The lecture will focus on the history of waste production in Australia, the current management of the diverse waste arisings, particularly focussed on operational and legacy wastes held at the Australian Nuclear Science and Technology...
Mr
Michael Slater
(Invited Lecturer)
30/10/2017, 10:45
National and international collaborative waste management programs
Oral Presentation
Plutonium has arisen from large scale reprocessing over many decades. When the programmes ends around 2020 there will be approx. 140te of separated plutonium in UK. Current policy is safe and secure long term storage in modern purpose built stores. This requires ongoing active management and institutional controls including significant security costs and is not a lifecycle solution....
Mr
Miklos Garamszeghy
(Nuclear Waste Management Organization)
30/10/2017, 11:15
National and international collaborative waste management programs
Oral Presentation
In Canada, used CANDU (CANada Deuterium Uranium) nuclear fuel from the operation of 22 current and former nuclear power reactors, as well as several prototype and demonstration reactors, is stored in water-filled pools for about seven to ten years before it is transferred to licensed dry storage containers at the nuclear reactor sites. Although safe, this storage practice requires continuous...
Dr
Evaristo J. Bonano
(Sandia National Laboratories)
30/10/2017, 11:45
National and international collaborative waste management programs
Oral Presentation
The recognition that the endpoint of spent fuel management practices will be deep geologic disposal of radioactive wastes leads to questions about how alternative options for spent nuclear fuel (SNF) management might affect performance of a geologic repository. Do some options for SNF management simplify the siting and design of a geologic repository? Do some geologic disposal concepts...
Mr
Gerry Triani
(ANSTO)
30/10/2017, 12:15
Performance Assessment and geological disposal
Oral Presentation
A new nuclear medicine facility is being built which will enable ANSTO to meet both domestic and global demand for Molybdenum-99. Co-located on the site will be an innovative waste treatment facility that deploys ANSTO’s Synroc technologies; a waste form tailored for immobilizing all the waste elements and fission products and an integrated process line for converting intermediate level...
Dr
Massey de los Reyes
(South Australian Environment Protection Authoirty)
30/10/2017, 12:45
National and international collaborative waste management programs
Oral Presentation
On the 19th of March 2015, the Nuclear Fuel Cycle Royal Commission (NFCRC) was established by the South Australian Government, and tasked to undertake an independent examination into the opportunities and risks for South Australia’s further involvement in the Nuclear Fuel Cycle. This presentation will review the process, findings and recommendations delivered by the NFCRC, with particular...
Prof.
David Shoesmith
(Western University)
30/10/2017, 14:30
National and international collaborative waste management programs
Oral Presentation
The internationally accepted approach for the disposal of spent nuclear fuel is to seal it in corrosion-resistant metal containers and bury it in a stable deep geologic repository. If containers were to fail, and the fuel become exposed to groundwater, radiolytic corrosion of the fuel could release radionuclides to the groundwater, the critical first step in their transport into the...
Prof.
Kastriot Spahiu
(SKB, Stockholm, Sweden and Chalmers University of Technology, Gothenburg, Sweden)
30/10/2017, 15:00
National and international collaborative waste management programs
Oral Presentation
Our experimental data indicate that the hydrogen effect is a complex phenomenon and has several aspects. The decomposition of hydrogen peroxide on the surface of SIMFUEL is followed by the reaction of the produced hydroxyl radicals with hydrogen to give water, or their reaction with H2O2 to give O2. Only a very small part of the initial hydrogen peroxide (<0.02%) causes oxidative dissolution...
Prof.
Nicolas DACHEUX
(University of Montpellier)
30/10/2017, 15:15
National and international collaborative waste management programs
Oral Presentation
Due to the concomitant formation of oxygen vacancies in the fluorite structure, it was found that the incorporation of trivalent lanthanide elements in ThO2 or CeO2 strongly affect their chemical durability during dissolution or leaching tests [1-4]. On the contrary, the impact of such elements on the dissolution of UO2 remains largely unknown. For this purpose, several lanthanide – uranium...
Dr
Anders Puranen
(Studsvik Nuclear)
30/10/2017, 15:30
National and international collaborative waste management programs
Oral Presentation
Leaching results on fragments of high burnup (65 MWd/kgU) UO2 fuel from a commercial pressurized water reactor are presented. The experiments were performed in simplified granitic groundwater under a hydrogen pressure of up to 5 MPa, representing conditions in a water intrusion scenario for a Swedish KBS-3 design spent nuclear fuel repository. The freshly crushed fragments were...
Mr
Beng Thye Tan
(University of Cambridge, Singapore Nuclear Research and Safety Initiative)
30/10/2017, 15:45
National and international collaborative waste management programs
Oral Presentation
The migration of radionuclides from underground nuclear waste repositories will involve the formation of uranium secondary minerals when ground water reacts with the spent nuclear fuel.
During oxic or anoxic spent fuel dissolution, amorphous phases can precede the development of well-defined crystalline mineral phases. Nuclear magnetic resonance (NMR) can probe the structure of these...
Prof.
Nicolas DACHEUX
(University of Montpellier)
30/10/2017, 16:30
National and international collaborative waste management programs
Oral Presentation
Dissolution or leaching of the spent nuclear fuels (SNF) is a key step either in the field of their reprocessing or their long-term storage in underground repository. Moreover, SNF contain a wide variety of fission products including platinoid elements (PGM’s) either incorporated in the UO2 matrix, or present in various separated phases for which the specific impact on the overall dissolution...
David Shoesmith
(Western University)
30/10/2017, 17:00
National and international collaborative waste management programs
Oral Presentation
The corrosion of high level copper nuclear waste containers under permanent disposal conditions can occur via a number of processes which change in importance as the environment within a deep geologic repository evolves from warm and oxic to cool and anoxic. Under warm and oxic conditions the container could be exposed to gamma irradiated conditions which evolve from aerated vapour to fully...
Mr
Ernesto González-Robles Corrales
(Karlsruhe Institute of Technology)
30/10/2017, 17:15
National and international collaborative waste management programs
Oral Presentation
Zircaloy claddings of fuel rods for nuclear reactors are considered as first technical barrier for retention of radionuclides produced in the nuclear fuel. The integrity of the cladding is influenced by various processes during reactor operation and beyond, e.g. oxidation, hydrogen uptake, PCI, fission product precipitation, -decay, and radiation damage. Composition of agglomerates found on...
Dr
Michel Herm
(Karlsruhe Institute of Technology)
30/10/2017, 17:30
National and international collaborative waste management programs
Oral Presentation
Cladding tubes of water-cooled nuclear reactors are usually made of Zircaloy and are an important retaining element for radionuclides present in the fuel. However, cladding integrity is affected by various processes during reactor operation and beyond, e.g. oxidation, hydrogen uptake, PCI, fission product precipitation, alpha-decay, and radiation damage. Using experimental and modelling...
Dr
Tomofumi Sakuragi
(Radioactive Waste Management Funding and Research Center)
30/10/2017, 17:45
National and international collaborative waste management programs
Oral Presentation
On the issue related on a safe disposal of spent fuel claddings is the corrosion and the subsequent gas and radionuclides release. The Zircaloy corrosion under a prospected disposal condition has recently been investigated by sensitive hydrogen measurements at 30℃, and reported that the kinetics in the rate around nm/y follows the parabolic rate law.
In the present work, an improved equipment...
Ms
Rebecca Stohr
(Australian Safeguards and Non-Proliferation Office)
31/10/2017, 08:30
National and international collaborative waste management programs
Oral Presentation
Waste conditioning is an important step in minimising and controlling the migration of radionuclides from disposed wastes into the environment. However, when nuclear materials are present, consideration of nuclear safeguards is also needed. Safeguards is the set of tools and techniques used to ensure nuclear materials are only used for peaceful purposes. As part of a safeguards system, nuclear...
Dr
Irmgard Niemeyer
(Forschungszentrum Jülich GmbH)
31/10/2017, 09:00
National and international collaborative waste management programs
Oral Presentation
Safety, security and safeguards aspects regarding the geological disposal of high-level radioactive waste and spent fuel are usually addressed separately. Thus, apparently different methods and techniques exist for each of the three “S’s”. However, by identifying both synergies in overlapping methods or techniques and differences in the requirements with respect to safety, security and...
Mr
Oleksandr Novikov
(SSE Chernobyl NPP)
31/10/2017, 09:30
The Cooling Pond of Chornobyl NPP (hereinafter referred to as CP) was formed by constructing an embankment on the flood plain of the Prypiat River, its area made about 22.9 km2; its water volume making 151 million m3 was calculated for cooling Chornobyl NPP four units in mode of electric power generation.
When CP was operated the water level was maintained up to the design level which made...
Ms
Jeanne Poling
(CH2M)
31/10/2017, 09:45
National and international collaborative waste management programs
Oral Presentation
***Applying Successful Global Programs to the International Nuclear Decommissioning Market***
CH2M has successfully managed waste management, remediation and nuclear decommissioning programs incorporating both innovations and lessons learned that have broad applicability to upcoming major decommissioning programs throughout Australia and globally.
This abstract presents an...
Dr
Cristian Dragolici
(IFIN-HH)
31/10/2017, 10:00
The WWR-S research reactor from National Institute for R&D in Physics and Nuclear Engineering Horia Hulubei (IFIN-HH), Magurele site, Romania, is currently in the year 2 of the phase 3 of the decommissioning project. Big components are cut in small parts to reduce the size for a proper packing and temporary disposal. Segregation is used to separate different type of materials depending on...
Dr
Stefan Neumeier
(Forschungszentrum Jülich GmbH)
31/10/2017, 10:15
National and international collaborative waste management programs
Oral Presentation
The application of safeguards measures by the International Atomic Energy Agency (IAEA) involves analytical measurements of samples taken during inspections and requires the development and advancement of analytical techniques. For quality control purposes, the IAEA has expressed the need to acquire reference materials for particle analysis methods applied in safeguards.
To this purpose, a...
Dr
Claire Corkhill
(NucleUS Immobilisation Science Laboratory, University of Sheffield,)
31/10/2017, 11:00
National and international collaborative waste management programs
Oral Presentation
Under the generic scenario envisaged for the geological disposal of vitrified UK high- and intermediate-level waste glass (HLW and ILW, respectively), high pH environments, formed through degradation of the cementitious engineered barrier, are expected to dominate the ground water chemistry thousands of years into the future. We highlight the main findings of a number of recent and ongoing...
Mr
Sean Barlow
(University of Sheffield)
31/10/2017, 11:30
National and international collaborative waste management programs
Oral Presentation
Vitrification of sludge waste arising from legacy nuclear activities such as Magnox reprocessing is a promising alternative to the current baseline plan of cementation with superior long-term durability, improved waste loadings and significant volume reduction. Glass products were produced from oxidized and metallic uranium and magnesium, representative of the extremes found with the First...
Mr
Jarrod Crum
(PNNL)
31/10/2017, 11:45
National and international collaborative waste management programs
Oral Presentation
A borosilicate glass-ceramic waste form is being developed to significantly increase waste loading of high-level waste relative to single phase glass. The glass-ceramic waste form is comprised of approximately 70% borosilicate glass, 20% oxyapatite (X2Ln8Si6O26), and 10% powellite (XMoO4), by mass, where X = alkaline earth and Ln = lanthanides. Understanding the overall corrosion behavior of...
Prof.
John McCloy
(Washington State University)
31/10/2017, 12:00
National and international collaborative waste management programs
Oral Presentation
Owing to high concentrations of Al2O3 from dissolved fuel cladding and Na2O from basification of the waste, about half of the high-level waste by volume at Hanford, Washington, USA is rich in both Na and Al. Formulations of high waste-loading glasses result in lower amounts of SiO2, which often leads to undesirable precipitation of nepheline (NaAlSiO4). Nepheline crystallization can be...
Ms
Amber Mason
(University of Sheffield)
31/10/2017, 13:45
National and international collaborative waste management programs
Oral Presentation
UK stocks of separated civil plutonium are projected to exceed 140 tons at the end of reprocessing. This material may require immobilisation in a proliferation resistant wasteform, should it prove uneconomic to recycle in MOX fuel. We have investigated and optimised alkali tin silicate glass compositions for the immobilisation of this stockpile using CeO2 as a PuO2 surrogate. A remarkable...
Mr
Rui Guo
(University of Cambridge)
31/10/2017, 14:00
National and international collaborative waste management programs
Oral Presentation
The magnesium content of UK Magnox waste glass makes its aqueous durability much poorer than glasses such as SON68, which does not contain Mg. The glass dissolution kinetics is ultimately dependent on the composition/structures of the altered layers(1), here we try to elucidate formation mechanisms.
Alteration layers formed by in-situ precipitation have been discussed widely(2,3), but any...
Mr
Atsushi Mukunoki
(JGC Corporation)
31/10/2017, 14:15
National and international collaborative waste management programs
Oral Presentation
Lead borate glass vitrified at a low temperature is regarded as one of the promising immobilization materials of Iodine-129 which will be removed from a spent AgI filter generated from reprocessing plants and may cause significant effect onto long term safety of geological disposal.
Immersion tests in various solutions have been conducted to understand glass dissolution behaviors in possible...
Dr
Clive Brigden
(ISL, Department of Materials Science & Engineering, University of Sheffield, S1 3JD, UK.)
31/10/2017, 14:30
National and international collaborative waste management programs
Oral Presentation
A study to develop a new high level waste (HLW) glass formulation for waste from the highly active liquor storage (HAL) tanks at Sellafield is described. A likely washout scenario for the tanks at the end of operations involves the use of sodium carbonate as a tank washout reagent [1] leading to a high soda wastestream. Titanium is not currently used in existing HLW formulations in European...
Prof.
Maik Lang
(University of Tennessee)
31/10/2017, 15:15
National and international collaborative waste management programs
Oral Presentation
For the past 30 years, the development of durable materials for radionuclide immobilization has been central to efforts to dispose of wastes generated by the nuclear fuel cycle. There still exist, however, large gaps in the understanding of fundamental modes of waste form degradation under repository conditions. Comprehensive evaluation of waste form performance, including resistance to...
Dr
Ian Farnan
(University of Cambridge)
31/10/2017, 15:45
Oral Presentation
Plutonium doped YPO4 was prepared to test the extent of solid solution and the effect of radiation damage over several years. Y0.92 238Pu0.08PO4 showed the presence of a Pu substituted xenotime phase and a 238PuP2O7 phase by X-ray diffraction (XRD). The 31P magic‑angle spinning nuclear magnetic resonance (MASNMR) spectrum showed peaks for PuP2O7 and peaks assigned to phosphorus coupled to...
Dr
Ming Tang
(Los Alamos National Laboratory)
31/10/2017, 16:00
National and international collaborative waste management programs
Oral Presentation
Multi-phase ceramic waste forms were fabricated by melt-processing and hot isostatic pressing (HIP) to immobilize alkaline/alkaline earth (Cs/Sr-CS) + lanthanide (LN) + transition metal (TM) fission product waste streams from nuclear fuel reprocessing. Al2O3 and TiO2 were combined with these waste components to produce multi-phase crystalline ceramics containing hollandite-type phases,...
Dr
Christoph Lenz
(ANSTO)
31/10/2017, 16:15
National and international collaborative waste management programs
Oral Presentation
The investigation of radiation damaged or metamict minerals and their synthetic analogues has increased appreciably over the past two decades, stimulated by the potential use of mineral-like ceramics as waste forms for the immobilisation of reprocessed spent nuclear fuel and other radioactive waste. In this research field, however, a fast and inexpensive technique operating in the micrometre...
Dr
Tao Wei
(ANSTO)
31/10/2017, 16:30
National and international collaborative waste management programs
Oral Presentation
Radioactive wastes are generated from the entire nuclear fuel cycle from mining to the burning of uranium fuel in the nuclear reactors. Pyrochlore (ABTi2O7) and zirconolite (CaZrTiO7) based glass-ceramics have been became an immerging candidate waste form matrix and attracted attention as it combines the process and chemical flexibility of glasses with the chemical durability of ceramics. It...
Dr
Nelly TOULHOAT
(CNRS/IN2P3/IPNL)
31/10/2017, 16:45
National and international collaborative waste management programs
Oral Presentation
Graphite has been widely used in different types of reactors such as gas or water cooled reactors. Disposal of the irradiated graphite waste is a current management strategy for the resulting graphite waste for which two main radionuclides, 14C and 36Cl, might be dose determining at the outlet. In order to simulate both ballistic and electronic effects induced by irradiation, model and nuclear...
Ms
Isadora Borba da Busch
(UNSW Sydney)
31/10/2017, 17:00
National and international collaborative waste management programs
Oral Presentation
Radioactive materials are used for several key applications in Australia, and resultantly, ~4248 m3 of low level and 656 m3 of intermediate level waste are currently stored on site. The present work investigates the development of an ambient-cured geopolymer composition for storage of low level radioactive wastes. These geopolymers were fabricated by ambient curing of mixtures of fly ash and...
Dr
Dirk Mallants
(CSIRO)
31/10/2017, 17:15
Cementitious materials are being widely used as solidification/stabilisation and barrier materials for a variety of radioactive wastes. The retention properties result from mineral phases in hydrated cement that (i) possess a high density and diversity of reactive sites for the fixation of radionuclides through a variety of sorption reactions (surface adsorption, incorporation and...
Prof.
Neil Hyatt
(University of Sheffield)
01/11/2017, 08:30
National and international collaborative waste management programs
Oral Presentation
Decommissioning and clean up of nuclear facilities requires the development of new technologies to condition radioactive wastes, producing passively safe waste packages of minimal volume, to reduce storage and disposal costs. We have applied hot isostatic pressing to demonstrate conceptual wasteforms for ion exchange materials and sludges present on the Sellafield site, UK, and Fukushima...
Dr
Greg Lumpkin
(ANSTO)
01/11/2017, 09:00
National and international collaborative waste management programs
Oral Presentation
With the aim of creating novel ceramics with high radiation tolerance and ionic mobility, multiple samples with A-B-O stoichiometries ranging from 215 to 227 were synthesized and characterized by a combination of SEM, XRD, and TEM methods. Single-phase defect-fluorite-type compounds with A = Sm or Yb and B = Ti, Zr, and/or Sn are reported; whereas, pyrochlore compounds were also found as a...
Dr
adel mesbah
(ICSM Marcoule, France)
01/11/2017, 09:15
National and international collaborative waste management programs
Oral Presentation
The share of nuclear energy in order to supply electricity continues to increase, which makes a growing need for more uranium resources. Currently uraninite (UO2) and coffinite (USiO4) are the two most abundant and exploited minerals. With the exhausting of these resources, other minerals are currently considered and are subject to multiple studies. Among them brannerite (UTi2O6) represents...
Mr
Sean Barlow
(University of Sheffield)
01/11/2017, 09:30
National and international collaborative waste management programs
Oral Presentation
Ce3NbO7 weberite-type materials, an inactive analogue for Am3NbO7, have potential use in americium radioisotope thermoelectric generators to be developed by the European Space Agency for scientific missions beyond the orbit of Jupiter. Ceramics with greater than 97% purity were synthesised by thermal solid-state reaction and analytically characterised by X-ray diffraction, neutron diffraction,...
Dr
Zhaoming Zhang
(ANSTO)
01/11/2017, 09:45
National and international collaborative waste management programs
Oral Presentation
A multi-phase titanate waste form was synthesized using high temperature sintering in air or Ar with the composition of Ca0.71Y0.088Ce0.52Hf0.22Ti2Ox. The phase assemblage was investigated as a function of the sintering atmosphere. X-ray diffraction measurements indicated that oxidizing sintering atmosphere (air) favors the formation of pyrochlore, whereas neutral environment (Ar) promotes the...
Mr
Robert Aughterson
(ANSTO)
01/11/2017, 10:00
National and international collaborative waste management programs
Oral Presentation
The structure types within the Ln2TiO5 (Ln = lanthanides) system have similarities with many of the proposed phases within the titanate ceramic waste-form Synroc. Certain compounds might also be suitable for inert matrix fuel applications. Previous studies have shown a relationship between lanthanide radii and polymorph type for the Ln2TiO5 system. By using multiple lanthanides the average...
Dr
Stéphanie Szenknect
(ICSM)
01/11/2017, 10:45
National and international collaborative waste management programs
Oral Presentation
Minerals belonging to the monazite family, REEPO4 (REE: Y, Sc, La to Dy) could incorporate in their structure substantial amounts of Th and U [1]. Moreover, monazites maintain their crystallinity even after geological times of exposure to self-irradiation. Therefore, this phase appears as a promising candidate for the specific conditioning of transuranic elements (AnIV,AnIII). Already, many...
Dr
adel mesbah
(Institut de Chimie Séparative de Marcoule, UMR 5257 CEA/CNRS/UM/ENSCM, Site de Marcoule, BP 17171, 30207 Bagnols-sur-Cèze cedex, France)
01/11/2017, 11:15
National and international collaborative waste management programs
Oral Presentation
Monazite, i.e. LnPO4 (Ln = La-Gd), has been widely studied as specific ceramic for the conditioning of trivalent and tetravalent actinides.1 Owing to its chemical and structural flexibility, the monazite allows a variety of possible substitutions following different mechanisms.2 Among them, the so-called cheralite-family, i.e. Ln1-2xCaxAnIVxPO4. In this frame, the major part of protocols...
Dr
Stefan Neumeier
(Forschungszentrum Jülich GmbH, Institute of Energy and Climate Research - IEK-6: Nuclear Waste Management and Reactor Safety, 52425 Jülich, Germany)
01/11/2017, 11:30
National and international collaborative waste management programs
Oral Presentation
Phosphate ceramics with monazite structure are considered as potential waste forms for the conditioning of specific nuclear waste streams (e.g. minor actinides and plutonium) due to their outstanding properties. In this study, the incorporation of actinides (Cm3+ and Pu3+) into the monazite structure has been investigated combining X-ray diffraction (XRD) as well as X-ray absorption- (XAS) and...
Dr
adel mesbah
(ICSM Marcoule, France)
01/11/2017, 11:45
National and international collaborative waste management programs
Oral Presentation
The management and the conditioning of radwaste represents a major challenge in the nuclear industry. Therefore a variety of host matrices have been studied, including several phosphate based ceramics.1 They represent promising candidates for the specific conditioning of actinides (III, IV) owing to their easy way of preparation and high chemical durability.2
The incorporation of actinides in...
Dr
Eric R Vance
(ANSTO)
01/11/2017, 13:30
Oral Presentation
Spent fuel has long been unofficially classified as HLW which is cooled for a few years to allow the dissipation of short-lived fission products and then is to be contained in thick-walled Cu or carbon steel containers for deep repository disposal where it is argued that the containers will perform immobilisation for ~105 yr. However immobilisation assumes highly reducing conditions in which...
Dr
Yingjie Zhang
(ANSTO)
01/11/2017, 13:45
National and international collaborative waste management programs
Oral Presentation
Glass-ceramics have attracted recent attention as they have the advantage of combining the chemical flexibility of glasses with the excellent durability of ceramics, making them potential waste forms for the immobilization of actinide wastes with processing chemicals. Glass-ceramics based on titanate ceramic phases, e.g. zirconolite, pyrochlore and brannerite have been developed at ANSTO. The...
Ms
Stephanie Thornber
(University of Sheffield)
01/11/2017, 14:00
National and international collaborative waste management programs
Oral Presentation
The UK has over 100 tonnes of separated PuO2 stored at the Sellafield site. The UK policy for managing this plutonium stockpile is to reuse this material as MOx fuel. However, not all of the material is suitable for reuse and a proportion has been classified as higher activity waste. These plutonium wastes, and any material which is not ultimately reused, will require immobilization, in a...
Dr
Linggen Kong
(Australian Nuclear Science and Technology Organisation)
01/11/2017, 14:15
National and international collaborative waste management programs
Oral Presentation
The actinide immobilisation research group at ANSTO has been investigating pyrochlore glass-ceramics for plutonium immobilisation. A novel method of glass ceramic preparation via a soft chemistry route has been designed recently. Significant advantages over a more traditional mixed oxide route include removal of the need for an organic solvent in synthesis and milling steps, and product devoid...
Dr
Paul C. M. Fossati
(Imperial College London)
01/11/2017, 14:30
National and international collaborative waste management programs
Oral Presentation
High-Level Waste (HLW) resulting from fuel reprocessing is immobilised in a borosilicate glass matrix, particularly in France and the UK.
Some HLW components have higher melting points than the glass, and thus never disolve into the melt.
Other crystalline phases may also form during fabrication due to limited solubility.
Separation could also occur later through a process of...
Dr
Josef Matyas
(Pacific Northwest National Laboratory)
01/11/2017, 15:15
National and international collaborative waste management programs
Oral Presentation
Various volatile radionuclides are being released into gas streams and aqueous solutions during reprocessing of used nuclear fuel and vitrification of radioactive waste. Radioactive iodine-129 is of a particular concern because of its long half-life of 15.7 million years and the potential for biological processes to concentrate iodine. A number of materials are being developed worldwide to...
Prof.
John McCloy
(Washington State University)
01/11/2017, 15:45
National and international collaborative waste management programs
Oral Presentation
Iodine-129, released in the off-gas stream during nuclear fuel reprocessing, is problematic due to its long half-life, high mobility in the earth’s environment, incorporation into the human thyroid, and difficulty in immobilizing it using traditional vitrification methods. Iodosodalite (Na8Al6Si6O24I2) has been considered as to immobilize iodine-129 due to feasibility of synthesis at low...
Dr
EUGENIA KUO
(Australian Nuclear Science and Technology Organisation)
01/11/2017, 16:00
National and international collaborative waste management programs
Oral Presentation
Sodalites have been investigated experimentally for the capture and long-term containment of iodine-129, a significant and hazardous waste product of the nuclear fuel cycle. Sodalites are zeolite-type structures commonly occurring in nature in alkaline igneous rocks and having the prototype formula Na$_8$(AlSiO$_4$)$_6$Cl$_2$. The crystal structure is based around $\beta$-cages consisting of...
Prof.
Evgeny Alekseev
(Forschungszentrum Jülich)
01/11/2017, 16:15
National and international collaborative waste management programs
Oral Presentation
Using extreme pressure (10GPa/1200°C) we obtained a new modification of U2O5 with an extraordinary dense structure. The crystal structure of resulting HP (high pressure)-U2O5 is dramatically differs from ambient pressure polymorph so called delta-U2O5. The structure of HP-U2O5 is more related to the cubic UO2 than to the layered delta-U2O5. Using state of the art ab initio methods we reveal...
Mr
Gabriel Murphy
(University of Sydney)
01/11/2017, 16:45
Novel techniques in waste-form development (including glass, ceramic, metallic, and composite waste forms)
Oral Presentation
In situ investigations of nuclear waste form related materials under extreme conditions are highly desirable for understanding and optimising applications of these materials, however they are often exceedingly challenging from a safety and radiological perspective. As a part of our investigations into actinide materials, we have developed a number of novel experimental methodologies which...
Ms
Bella Zubekhina
(researcher, V.G. Khlopin Radium Institute (KRI), St-Petersburg, Russia)
01/11/2017, 17:00
National and international collaborative waste management programs
Oral Presentation
Immobilization of bulk liquid high level waste (HLW) in Synroc ceramic is well-known reliable way for final isolation of waste from biosphere. It is proposed the alternative method of synthesis of titanate Synroc-like ceramic. Radionuclide incorporation into crystalline titanate host-phases can be provided as a result of direct radionuclide sorption from liquid HLW using non-selective sorbent...
Dr
Vittorio Luca
(Comisión Nacional de Energía Atómica)
02/11/2017, 08:30
National and international collaborative waste management programs
Oral Presentation
The nuclear industry generates a wide variety of radioactive waste streams during reactor operations and maintenance and in virtually all parts of the fuel cycle. In order to improve the sustainability of the industry it is necessary to develop improved methods and processes for treating, conditioning and disposing of this waste. The talk will provide an overview of research being conducted at...
Dr
Jeremy Causse
(Institut de Chimie Séparative de Marcoule (ICSM) - UMR5257 - CEA Marcoule)
02/11/2017, 09:00
National and international collaborative waste management programs
Oral Presentation
This work deals with the development of new templating routes to design porous nanostructured materials with innovative properties and/or easier to prepare. For example, we have shown that copper hexacyanoferrate nanoparticles could stabilize High-Internal Phase Emulsions or HIPE (**Mayer et al., J. Coll. Int. Sci., 2017, doi.org/10.1016/j.jcis.2017.05.113**) that can be used in a second step...
Dr
Michael Carboni
(CEA)
02/11/2017, 09:15
National and international collaborative waste management programs
Oral Presentation
Transformative technologies are needed in order to achieve economic uranium extraction from waste to generate a new fuel or for a safe storage. Metal–organic frameworks (MOFs) are a class of hybrid materials composed of organic bridging ligands coordinated to metal ions or metal ion clusters. The result is the formation of a porous crystalline solid that possess adequate stability in aqueous...
Dr
hugo luis bianchi
(Gerencia Química, Comisión Nacional de Energía Atómica, CAC, Av. Gral. Paz 1499 (1650) Buenos Aires, Argentina / ECyT, UNSAM, Martín de Irigoyen 3100 (1650) San Martín, Argentina)
02/11/2017, 09:30
National and international collaborative waste management programs
Oral Presentation
Spent ion exchange resins (IER) represent an important waste stream that is generated during the operation of both light and heavy-water reactors. Over the past 60 years of nuclear activity Argentina has accumulated over 300 m3 of spent IERs that to this day remain interim storage. With a view toward achieving a significant volume reduction and improved product stability we are investigating a...
Dr
Jessica Veliscek Carolan
(ANSTO)
02/11/2017, 09:45
National and international collaborative waste management programs
Oral Presentation
Actinides and lanthanides are targets for partitioning from solutions of spent nuclear fuel. Traditionally, actinide separation processes are based on liquid-liquid extraction. However, use of solid phase sorbent materials has several advantages such as the lack of organic solvent wastes. Framework materials based on titania and zirconia have been developed and functionalised with organic...
Prof.
Claude Degueldre
(Engineering Department, Lancaster University, LA1 4YW, UK)
02/11/2017, 10:00
National and international collaborative waste management programs
Oral Presentation
Abstract – The 450 reactors operating (Nov. 2016) around the world (30 countries) produce about 100 tonnes of plutonium annually, in spent fuel. Some amounts are separated through reprocessing. While the recycling of plutonium as MOX fuel derives additional energy from this resource, it does little to address the issue of growing plutonium inventories. If a political objective is to reduce the...
Prof.
Haruo Sato
(Okayama University)
02/11/2017, 11:00
National and international collaborative waste management programs
Oral Presentation
H. Sato and M. Yoshii, Okayama University, 3-1-1, Tsushima-naka, Kita-ku, Okayama-shi, Okayama 700-8530, Japan
The accident at the Fukushima Daiichi Nuclear Power Plant occurred following the Great East Japan Earthquake in March 2011, and led to the release of volatile radionuclides (RNs) which were deposited on the surrounding environment in the Fukushima prefecture. The authors conducted...
Mr
Kenichiro Kino
(Nucler Development Corporation)
02/11/2017, 11:15
National and international collaborative waste management programs
Oral Presentation
In the safety assessment of radioactive waste repository, it is important to evaluate the migration behavior of long half-life radionuclides in the disposal environment. It was reported that insoluble C-14 was generated in PWR. However, the knowledge about the chemical form of C-14 is little.
In this study, particles including C-14 collected from the coolant filters in PWR were analyzed by...
Dr
Kotaro Nakata
(CRIEPI)
02/11/2017, 11:30
National and international collaborative waste management programs
Oral Presentation
Radiocarbon (C-14) is recognized as a radionuclide that includes significant impact on public exposure in safety assessment of radioactive waste disposal. Its origin, generation mechanism and chemical forms in the wastes are required to be understood for the reasonable and proper safety assessment of the radioactive waste disposal. Some previous studies have reported occurrence of insoluble...
Dr
Mikko Voutilainen
(Department of Chemistry, University of Helsinki, Finland)
02/11/2017, 11:45
National and international collaborative waste management programs
Oral Presentation
In Finland and Sweden KBS-3 concept has been chosen for disposal of spent nuclear fuel in crystalline rock. Recent transport experiments have shown that heterogeneity of rock may play a major role in transport of radionuclides. Autoradiographic methods has been proven to be able to assist the characterization of heterogeneous structures. In this study we tested a novel digital autoradiographic...
Mr
Sebastien CAES
(SCK-CEN)
02/11/2017, 13:30
National and international collaborative waste management programs
Oral Presentation
The Supercontainer (SC) is the reference concept for the post-conditioning of vitrified high-level nuclear waste and spent fuel in Belgium. It comprises a prefabricated concrete buffer that completely surrounds a carbon steel overpack. Welding is being considered as a final closure technique of the carbon steel overpack in order to ensure its water tightness. Welding is known to induce...
Ms
Rita Vasconcelos
(University of Sheffield)
02/11/2017, 14:00
National and international collaborative waste management programs
Oral Presentation
In the UK, the volume of intermediate level waste (ILW) requiring final disposal in a geological disposal facility, is almost 450,000 m3. In one of the UK conceptual scenarios for the geological disposal facility in a high-strength crystalline rock, the vaults will be backfilled with a cement-based material, known as Nirex Reference Vault Backfill (NRVB). This material will provide a physical...
Mr
Ville Nenonen
(University of Helsinki)
02/11/2017, 14:15
National and international collaborative waste management programs
Oral Presentation
Fault zones influence the mechanical properties and seismological behaviour of the Earth’s crust and also the migration and trapping of sub-surface fluids. In addition to natural processes, their behaviour has broad implications to issues such as oil and gas production, the sequestration of carbon dioxide and the geological disposal of radioactive wastes.
Recent investigations carried out at...
Dr
Janaka J. Kumara
(Department of Civil Engineering, Meijo University, Japan)
02/11/2017, 14:30
National and international collaborative waste management programs
Oral Presentation
Deep geological repositories have been proposed as a safe waste management system for high-level radioactive wastes. Sand-bentonite buffer materials are used in engineered barrier system of deep geological facilities thank to their excellent swelling properties. In this research, volumetric and strength behaviour of sand-bentonite buffer material under high confining pressures of 1-3MPa were...
Prof.
Kazuya Idemitsu
(Kyushu university)
02/11/2017, 15:15
National and international collaborative waste management programs
Oral Presentation
The apparent diffusion coefficients of La, Nd, Eu, Dy, Er and Lu in compacted bentonites were investigated in various bicarbonate concentration. The apparent diffusion coefficients of lanthanides tended to decrease with increase of dry density. In the lower bicarbonate conditions than 0.25 M lanthanum had the largest diffusion coefficient of ca. 10-13 m2/s at 1.0...
Dr
Ryo Nakabayashi
(Central Research Institute of Electric Power Industry)
02/11/2017, 15:30
National and international collaborative waste management programs
Oral Presentation
The chemical form of carbon-14 released from irradiated stainless steel is a key parameter in the safety assessment of the sub-surface disposal system in Japan. In this study, unirradiated 304 and 316 stainless-steel powders were immersed in HCl solution and in NaOH solution under a low-oxygen condition to identify the chemical form of the released carbon. The main chemical forms of the carbon...
Dr
Paul Degnan
(Catalystra)
02/11/2017, 15:45
National and international collaborative waste management programs
Oral Presentation
The disposal of intermediate- and high-level radioactive waste requires emplacement in suitably engineered underground facilities in order to ensure an adequate level of isolation and containment for safety and security. We now have several examples of radioactive waste management organisations who have designed and undertaken extensive multi-disciplinary site investigation projects to...
Prof.
Gordon Thorogood
(ANSTO)
02/11/2017, 16:00
National and international collaborative waste management programs
Oral Presentation
99Tc is the most significant long-lived product of uranium fission, producing the largest fraction of the total long-lived radiation emissions of nuclear waste. Tc 7+ compounds are highly mobile in the environment. Relatively little is known regarding the solid state chemistry of Tc. Recently we studied the structural properties of (NH4)TcO4 (Tc7+) and confirmed that this is isostructural...
Prof.
John McCloy
(Washington State University)
02/11/2017, 16:15
Oral Presentation
Because of their radioactive nature, solid technetium-99 oxides have been rarely studied, and there is
a dearth of modern spectra and diffraction patterns in the literature. This publication aims to address
this by detailing a low-temperature synthesis method for pure, crystalline alkali pertechnetates,
along with complete analysis by static and magic-angle-spinning nuclear magnetic...
Prof.
Konstantin German
(A.N.Frumkin Institute of Physical Chemistry and Electrochemistry of Russian Academy of Sciences)
02/11/2017, 16:30
Oral Presentation
One of the problematic types of LRW are alkaline wastes generated in some types of spent
nuclear fuel reprocessing. Environmental friendly biological techniques of LRW treatment
are not widespread because of its extremely high salt contents and alkalinity usually not
suitable for organisms. The aim of this work was to explore the use of microorganisms
from extremely alkaline habitat to...
Prof.
Konstantin German
(A.N.Frumkin Institute of Physical Chemistry and Electrochemistry of Russian Academy of Sciences)
02/11/2017, 16:45
Oral Presentation
Techetium has a great number of oxidation states (usually we say 9 but in fact much
more) and is evidently one of the elements with the most complicated chemistry. This is
due its position in the center of 4d elements row with 7 electrones available for chemical
bonding. One of the very special options complicating technetium chemistry is its ability to
cluster formation and especially the...
Dr
Yohan Kim
(Korea Institute of Nuclear Safety)
National and international collaborative waste management programs
Poster
Radioactive compounds leached from radioactive wastes have been considered as widespread contaminants to threat human health and environment due to their radioactivity in aqueous phase. They are exposed from radioactive waste disposal facility and ubiquitously presented in water. To protect human health and environment, adsorptive removal is one of the most effective technology for separation...
Mr
GEUN-IL PARK
(Korea Atomic Energy Research Institute)
High Level Wastes and Spent Fuel (durability, ceramics and glasses)
Oral Presentation
This paper is to review the status for developing the systemic waste treatment and storage/transportation process by reduction of the final waste volume, fabrication of durable wasteforms applicable to disposal environment and the saft packaging and storage system.
Systemic framework of technologies for treating waste filter, metal waste and waste salt from KAERI pyroprocessing was...
Mr
Kristian Barnsley
(University of Warwick)
Novel techniques in waste-form development (including glass, ceramic, metallic, and composite waste forms)
Poster
11B MAS NMR methods for analysis of borosilicate glasses for storage of high-level waste.
Dr
Philip Kegler
(Forschungszentrum Jülich GmbH, Institute of Energy and Climate Research - IEK-6: Nuclear Waste Management and Reactor Safety, Jülich, Germany)
National and international collaborative waste management programs
Oral Presentation
Monazite-type orthophosphates (monoclinic LnPO4; Ln = La – Gd) are promising candidates as potential waste forms for the immobilization of specific nuclear waste streams, such as separated Pu from civilian or military sources unsuitable for further use, or separated minor actinides due to their specific physicochemical properties.
The thermochemical behavior of single phase La1-xLnxPO4 (Ln =...
Dr
Kwang-Wook Kim
(Korea Atomic Energy Research Institute)
Methods of processing challenging waste constituents
Oral Presentation
A large volume of problematic radioactive waste of spent uranium catalyst, which was used to produce acrylonitrile for fabrication of synthetic fibers, was generated by a private company in Korea until 2004. This has been stored onsite awaiting a management strategy that is to minimize the volume/cost requirements for the final disposal. This work will introduce a process to greatly reduce the...
