Description
Submitted papers and abstracts should focus on solutions for radioactive waste streams that have specific
or challenging properties or characteristics, or that derive from less common or unique facilities,
activities or legacies. For example, such waste streams might include high activity DSRS or neutron
sources, graphite from reactor cores, waste also having hazardous properties (e.g., organic liquids and
solids), waste from prototype and high temperature reactors, depleted uranium, wastes from sites that
have been remediated, or sites with ongoing challenges, etc
This paper depicts a deployable system with safety measures in place and mission achievable tasks for handling medical related radioactive sources. Radioactive sources are used around the world to support life-improving and lifesaving industries. However, disposition or consolidation of radioactive sources pose safety risks to operators, making a well-designed remote handling system desirable....
Management of small volume of alpha contaminated liquid waste can pose significant challenges during the pre-disposal and disposal phases. The radiochemical characteristics of the waste have the major influence on the selection of waste management technology but of course the quantity of the waste may have a considerable influence on the scale and design of the waste treatment and conditioning...
In the context of decommissioning of many various NPPs worldwide and also a remediation of old legacy sites, it is necessary to process various problematic waste streams, which have been stored for many years, and for their properties were not processible by classical technologies. These include solid and liquid wastes, in varying quantities, sometimes located in a variety of...
The performance characterization of radioactive waste is an important part of the safety management process of radioactive waste. It runs through the whole process of waste generation, pretreatment, treatment,preparation and disposal, and is the basis for the selection of technical route of radioactive waste treatment and disposal.
The technological process of radioactive waste performance...
In future experimental fusion ITER facility, beryllium (Be) constitutes the main first wall plasma-facing material. ITER will then produce Be waste, either in the solid or in powder form. It is important to anticipate the management of the generated radioactive waste. To manage Be, direct immobilization in a cementitious matrix seems to be an option. A research project has then been undertaken...
Bayesian statistics is highly complementary to the Data Quality Objectives approach due to their underlying iterative principles. For waste characterisation this provides an opportunity for greater information for decision makers when analytical data approaches a waste boundary. The Bayesian t-test is analogous to the current statistical approach advised by CL:AIRE (Contaminated Land:...
- Introduction
Geopolymers(GPs) are defined as chains or networks of inorganic molecules linked with covalent bonds where their physical and chemical properties like thermal resistance, sorption properties, and structural strength have received great attention[1]. Due to these features, it is possible to apply geopolymers to stabilize intermediate and low-level radioactive wastes in the...
(SOGIN), Francesco Troiani (SOGIN)
Organic Alpha Contaminated Liquid Waste because of their dual nature of organic and radioactive compounds can affect nuclear safety and have harmful effects on health and environment. These kinds of contaminated liquid must be immobilized into a waste forms that can prevent their long-term release avoiding the contact with water and any loss of containment....
Alkali-borosilicate glasses (ABS) are used to accommodate wastes arising from day to day operations and the decommissioning of nuclear installations. Investigating the immobilization systems, chemical durability and structure under normal conditions have gradually increased and in the next two decades will become the prime focus. In this study some physical properties such as Dietzel field...
Deep eutectic solvents (DES) are a mixture of a hydrogen bond acceptor (HBA), commonly quaternary ammonium salt, and a hydrogen bond donor (HBD), such as a carboxylic acid or alcohol. These solvents are readily synthesized from easily accessible materials. DES are characterized by their low cost, melting point, flammability, toxicity and wide electrochemical windows. Chemical and physical...
Radioactive waste as spent ion exchange resins (IER), must be conditioned for storage and disposal, in order to reduce the possibility of dispersion, elution and diffusion of radioactive elements to the environment.
In this work, the immobilization of 0, 10, 20 and 30 wt% of dry cation exchange resins (CER), in linear low density polyethylene (LLDPE), high impact polystyrene (HIPS) and...
In this study, iron oxide super paramagnetic nanoparticles, Fe3O4@MnF2O4 and Fe3O4@SiO2 core/shell Nano composites synthesized via ultrasonic assisted chemical co-precipitating technique to remove heavy metals from wastewater, especially nuclear wastewater. Optimization method under controlled conditions was used to increase the adsorption of heavy metals by nanoparticles as adsorbent. Thus,...
Ten years have passed since the Fukushima accident occurred. TEPCO is undertaking decommissioning of Fukushima Daiichi Nuclear Power Station (NPS) steadily and safely, incorporating domestic and international expertise, to fulfill its responsibility for the March 11, 2011 accident.
From all of the decommissioning works, various types of solid waste have been generated. These volume are...
Maisiagala Radioactive Waste Storage Facility (MRWSF) in Lithuania is a Radon type disposal facility that had been in operation from 1963 till 1988 and was closed in 1989. It consists of a subsurface concrete vault with an overall volume of about 200 m3. The vault was filled to about 60 % with legacy radioactive waste (RW), ~114 m3) generated at industrial, medical, military and scientific...
The safe management and disposal of low and intermediate level radioactive waste requires accurate and quality assured characterization by non-destructive and destructive methods, and determination of the radionuclide inventory, chemical, physical properties in the different steps of waste management. Relevant procedures, standards and practices have been developed and continue to be refined...
Since 2018, Orano with its partners CEA and the Japanese subsidiary ANADEC, is studying the applicability of In-Can melting system developed for French needs to Fukushima-Daiichi. Target wastes are secondary waste from the contaminated water treatment and are present in different forms and properties. Zeolites, silicotitanate, ion exchange resin, activated carbon are solid waste ; carbonated,...
There are significant numbers of produced spent fuels (SFs) eligible to take out from storage pool and transfer to store in dry condition due to more than 50 years operation of Tehran Research Reactor. A multi-phase plan was conceived, designed and has implemented to prepare an infrastructure and required equipment for converting the wet storage to dry for the first try in the country for TRR...
Ionization smoke detectors as a kind of fire alarm device mounted on the building ceiling and the lightning prevention containing radioactive substances were collected from building construction companies and radioisotope users in Thailand. The most common ionization smoke detectors contain americium-241 with activities up to 0.666 MBq lightning preventers contain americium-241 or radium-226...
The incorporation of organic liquids in cement-based materials is of interest for various applications, and in particular for the immobilization of radioactive industrial wastes. Immobilization of wastes into cementing materials by stabilization and solidification (S/S) is a common procedure, because it ensures chemical stabilization of many compounds and produces a mechanically stable waste...
The Ukraine a DGR concept considers the crystalline rock environments. The solution is based on the multiple barriers principle. The most common buffer material for engineered barrier system (EBS) is compacted bentonite, which features low permeability and high retardation of radionuclide transport. The task “Influence of temperature on clay-based material behaviour” of the EURAD project aims...
The incorporation of organic liquids in cement-based materials is of interest for various applications like the formation of porous material through emulsion templating and removal of the dispersed phase, the design of composite materials with improved and/or combined properties or the immobilization of industrial wastes. Immobilization of wastes into cementing materials by stabilization and...
An advanced Phosphoric Acid Decontamination (PHADEC)-based process is being developed to manage the large amount of contaminated metallic materials coming from dismantling activities in nuclear decommissioning. Volume savings of the final waste, lower environmental footprint and reduction of secondary waste by declassifying scrap metals and reusing decontaminated phosphoric solution are the...
The CERUS project was developed by the Argentinean National Atomic Energy Commission (CNEA) according to the strategies of spent fuel management policy declare at the National report for the Joint convention on the safety of spent fuel management and on the safety of radioactive waste management, in order to achieve a predisposal treatment to the conditioning of $U_{3}Si_{2}$-Al clad spent...
Ion exchange resins (IEX) which are used in nuclear power plants have to be treated and dried, in order to ensure a safe storage in future. A main advantage of the hot resin compaction during mentioned treatment process, is the saving of limited storing capacities in comparison to non-compacted IEX.
Supplied and temporarily stored IEX have to be transported as IEX / water mixture by piping...
Waste conditioning, handling and storage is a challenging task not only during operation and decommissioning of nuclear sites, but also in other areas like science and research.
Usually waste is packed in drums where a detailed documentation of the drum content is mandatory.
In many cases e.g. due to the change of regulatory requirements it becomes necessary to re-characterise waste drums...
Nuclear graphite has been widely used as moderator and reflector in I and II generation reactors and it is being considered for some next generation projects. Several graphite-moderated nuclear reactors have already been permanently shut-down, and others will be in the next years. Therefore, decommissioning of this material is becoming an important issue, given that an ultimate strategy for...
In response to lessons learned from a 2019 contamination incident during a source removal in Seattle, WA, the National Nuclear Security Administration’s (NNSA), Office of Radiological Security’s (ORS) Off-Site Source Recovery Program (OSRP) has implemented new procedures and contracting requirements to enhance safety during the removal of self-shielded irradiators containing Category 1 and 2...
The characterization, dismantling and pre-disposal management of radioactive materials have an important role in view of safe decommissioning of nuclear facilities. One of the main challenges is related to the management of irradiated graphite (i-graphite) used as moderator and reflector in several nuclear power plants and research reactors. In addition to common radioprotection issues typical...
In Germany, the Asse II mine was originally used for the commercial potash and rock salt production and later on for the emplacement of radioactive waste. Between 1967 and 1978, nearly 47,000 m3 of low- and intermediate-level waste were emplaced in the Asse II mine but the exact composition of the disposed waste is poorly known. At the time of emplacement, the waste acceptance criteria did not...
Nuclear waste is one of the big issues of public acceptance of nuclear energy or nuclear uses in general. Nuclear waste is classified into high-level waste, transuranic waste and low-level waste. High level waste (HLW) can be transmuted into non-hazardous materials. Accelerator-driven system is used to transmute nuclear waste, moreover it can produce energy for generating electricity at the...
The purpose of this work was to develop a process of concentration and precipitation of Uranium contained in radioactive nitric liquid waste, in order to improve the conditions of conditioning and storage of these wastes.
Lab trials were performed using samples of radioactive nitric liquid waste that contain Natural Uranium, with a concentration of 2 [g/L], which were concentrated in a...
A variety of sealed radioactive sources, such as Co-57 and Ge-68/Ga-68, are used for the precise calibration of nuclear medicine systems. After their useful life, these sources need to be handled and kept into storage until they meet the general clearance criteria. For clearance after storage, it is necessary to determine the source activity by measurement. The only way is to evaluate the...
The industrial irradiation facility, type Product I from the former Soviet Union, was put into operation in Cuba in 1987, in the Research Institute for Food Industry. It was used for irradiation of foodstuffs and other types of products. According to the IAEA classification, this is a category II irradiator, panoramic irradiator with dry storage of the radioactive sources. The facility was...
The prime source of liquid radioactive waste generation in hospitals is high dose radionuclide therapy facilities, as high levels of activity is handled in such facilities. The most common radionuclide therapy world-wide is radioiodine therapy and the same is the case in India too. As per the existing regulations, radionuclide therapy using I-131 with activity more than 1.11 GBq is carried out...
Scrap steel metals have played an important role in the steel manufacturing industry because they can be recycled without any damage or degradation of its property. Like other countries, scrap steels are imported from abroad. Some were found radioactive contamination both natural and artificial radioisotopes. In case, once contaminated scrap steels are introduced into the melting process,...
Nowadays countries operating nuclear power plants have an ambitious goal – closing the nuclear fuel cycle. One of the major tasks is the management of spent nuclear fuel (SNF). Processing of mixed nitride uranium-plutonium SNF suggests the use of LiCl-KCl electrolyte in the pyrochemical or combined technology. However, the industrial application of pyrochemical processing cannot be implemented...
Treatment of contaminated metals by melting in Sweden started 1987 as a joint initiative by the licensee at that time (Studsvik) and the regulators in Sweden. Since 2016, the metal treatment facility is owned and operated by Cyclife Sweden, a company within the EDF Group.
Over the years the facility and the operations has developed, including extensions of the cutting and segregation areas, a...
Perovskite is proposed as a potential host for immobilizing the highly active short lived radionuclide strontium, which is discarded in the form of medical devices from the hospital. In the present work, strontium perovskite ceramic matrix has been successfully synthesized by employing microwave (MW) assisted method at MW power of 800W and at a frequency of 2.45GHz in multimode applicator. The...
The present research provided an optimal option for Disused Sealed Radioactive Sources (DSRS) management based on Monte Carlo simulation. The objective is to design the appropriate means for radioactive waste conditioning so as to avoid material and economic losses based on trials during the sources' dismantling. The Particle and Heavy Ion Transport code System (PHITS) was used to design waste...
The use of smart materials, especially the carbon-based nanomaterials is increasing each day. Among the several carbon-based nanomaterials, graphene quantum dots are one of the most impressive one, not only by its quantum behavior but due the adsorption quality conferred by electrostatic interactions from the negatively charged groups as the huge surface area (2.630 m2/g). In this study we...
During the last decades, the nuclear and non-nuclear industry has produced a considerable amount of low (LLW) and intermediate level (ILW) radioactive waste. Though the waste form and streams might be different, such radioactive waste must be safely disposed in a final repository under the same strict waste acceptance requirements (e.g. the radiological and material characterization) defined...
The safe storage of chemically reactive radioactive waste, under water cover within a robustly engineered system, for a prolonged period requires understanding of its history and the ability to predict future behaviour. Condition Monitoring and Inspection (CM&I) is seen as the final step in the hierarchy of controls used to demonstrate the longevity of interim stored waste. Such monitoring and...
A novel method published as patent WO2021019319 [1] was applied to denitrate a 3 M nitric acid stream of uranium, lanthanides, metals and non-metals which simulates the high level liquid waste (HLLW) arising from heavy water reactor (HWR) spent fuel reprocessing [2]. Once the denitration of the simulated HLLW was demonstrated a second and third set of tests were run by adding 50 wt.% or 90...
Japan Atomic Energy Agency (JAEA) has stored much of its waste generated from R&D activities related to nuclear science and technology. A part of these wastes contains compressed waste without prior radiological, chemical or physical characterization assessed, as well as mixed waste containing lead and mercury with little information about its contents.
Such problematic wastes have been...
Safe and secure management of disused sealed radioactive sources (DSRSs) represent a challenging topic in the field of radioactive waste management. In particular the end of life-cycle management of these sources is not a straightforward problem due to the variability of the radioactivity content and the half-lives. Among the different end of life cycle management strategies for these sources,...
During the processing of liquid radioactive waste (LRW) at nuclear power facilities, concentrates (high-salt LRW) and spent filter materials are produced, the main of which are ion exchange resins (IER). The available volumes for their storage at all Russian facilities are almost exhausted.
A significant share of IER in the total amount of accumulated LRW excludes the possibility of their...
International Conference on Radioactive Waste Management: Solutions for a Sustainable Future
IAEA Headquarters 1-5 November, 2021
Topic # 3: Solutions for Specific Wastes
POLYMER TECHNOLOGIES for the SOLIDIFICATION OF COMPLEX L/ILW LIQUID RADIOACTIVE WASTE: GLOBAL CASE STUDIES of APPLICATIONS AND DISPOSAL OPTIONS
Dennis Kelley, Vista Nuclear Solutions, USA
...
Regarding innovative solution findings for specific nuclear waste, especially in the field of treatment of used nuclear fuel (UNF), the idea of recovery instead of storage and usage of UNF in liquid fuel reactors will be of significantly increasing importance in the future. Recycling by separation and reuse of UNF via chlorination of UNF and target-oriented back feeding into a liquid...
This document has suggested a conceptual design for an infrastructure to recover, handle and condition SHARS for long-term storage.The stumbling block on the international level was the management of Spent High Activity Radioactive Sources (SHARS) because of its high potential radiological risk. Based on the design concept of IAEA and the practice of NECSA, with slightly different design...
Nuclear decontamination processes generate a wide range of radioactive waste to be properly managed. Spent ion-exchange resins (IER) are a large component of radioactive low and intermediate level waste. The development of suitable treatment and conditioning processes is an urgent task to address, as the challenging waste nature (flammability, dispersivity, swelling), high radionuclides...
Spent ion exchange resins (IERs) represent an important waste stream that is generated during the operation of nuclear power reactors and research facilities reactors. Over the past 70 years of nuclear activity, Argentina has accumulated near 400 m3 of spent IERs that remains storage for an adequate conditioning before disposal. An optimal processing option must involve volume...
Incineration technology is one of the most effective ways to treat radioactive combustible waste, with high capacity reduction ratio, stable products, strong economy and mature technology. China Institute for Radiation Protection has been conducting research on radioactive waste incineration technology since the 1970s, and has developed ZRF series pyrolysis incineration technology, ZKF series...
IRWA is designated by the AEOI and Iran Nuclear Regulatory Authority (INRA) as the Central Waste Management Organization in Iran to be responsible for performing all aspects of Radioactive Waste (RW) management activities for fuel cycle facilities and minor waste generators, long-term storage and disposal of all radioactive wastes including operational and decommissioning wastes are the most...
At the geological repository for short-lived waste (SFR) at the Forsmarks NPP, radioactive operational waste from NPP:s and similar waste from other nuclear facilities in Sweden is disposed. This includes short-lived waste from e.g. research and industry treated at the facilities in Studsvik. SFR, operated by Swedish Nucelar Fuel and Waste Management Co, is located at a depth of about 50...
Hazards associated with ionizing radiation are deleterious to all living organisms and the environment in general. Sealed radioactive sources are the major sources of anthropogenic ionizing radiation in Ghana. They are applied in hospitals for x-ray imaging, cancer diagnosis and treatment; in industry and civil constructions for moisture and level gauge determination; and in agriculture for...
Waste Technology Development Centre (WasTeC) of the Malaysian Nuclear Agency has been managing various forms of radioactive wastes since 1984. Among liquid wastes managed at the centre, the type that is most challenging is perhaps the mixed organic liquid waste. This kind of wastes consist of a multitude of scintillation liquids, mineral processing solvents, and medical radiotherapy fluids....
Notwithstanding the advantages of environmentally-friendly nuclear power plants in the new energy industry, efficient disposal of radioactive nuclear wastes is still lacking. Up-to-date, encapsulation of radioactive ion-exchange resins with green and cost-effectiveness packages such as geopolymer has recently emerged. In this contribution, geopolymer packages were elaborated up to 42 wt.% of...
Sorption of selected radionuclides from liquid radioactive wastes by sorbents of the biological origin.
Introduction
Radioactive waste-waters that contain radioactive metal ions, e.g. Cs(I), Sr(II), Co(II), and/or Am(III) are dangerous for people and for the environment. There are several methods to remove them from the wastewaters. A promising method of eliminating the radioactive...
Sorption on inorganic sorbents supported by ultrafiltration - hybrid method for treatment of radioactive liquid waste.
Introduction
In accordance with the law in force, it is forbidden to dilute radioactively contaminated liquids and discharge them into the environment. Therefore, it is necessary to process them into a product that is safe for humans and the environment, with the aim to...
The decommissioning of UNGG (“Uranium Naturel Graphite Gaz” or “Natural Uranium Gas Graphite” in English) reactors inevitably creates the issue of managing the arising irradiated graphite, both from the reactor pile and from the sleeves surrounding the fuel elements. The irradiated graphite is considered as a long lived intermediate level waste in France and is not contact handle able.
In...
Metallic uranic fuel has been used in the United Kingdom’s Magnox fleet of reactors since the 1950s, with the Magnox reprocessing plant at Sellafield forming a key part in the management of spent fuel with over 54,000 tonnes reprocessed to date. Following the retirement of the Magnox reactor fleet and planned completion of reprocessing, the UK will possess an inventory of several hundred...
In India, Low Level (LLW) Solid Radio-Active Wastes (RAW) contributes more than 90% of the total RAW generated from regular Operation and Maintenance of a typical Nuclear Fuel Cycle facilities. The volume generated from a typical nuclear facility ranges from 200 to 600 M3 depending on type and number of the facilities at a site. These wastes, in general are segregated as combustible,...
Radioactive ion exchange resin is one of the main low-intermediate level waste(LILW) generated by nuclear facilities, and it has always been a hot and difficult point in the safety management of radioactive waste. At present, the waste resin treatment technology of cement solidification process used in China can not meet the increasingly stringent requirements of waste minimization due to its...
There is a large inventory of disused sealed radioactive sources (DSRS) that have been accumulated in various Member States, and it is likely to continue increasing over time, given the current and future potential use of sealed radioactive sources worldwide. In the context of the safe management of DSRS, an important and emerging issue of immediate concern is the management of Depleted...
Cement materials have attracted great research interest as potential matrixes for the immobilization of high-level waste (HLW) due to their good mechanical properties and thermal stability. However, the effect of radiation on a cement compound containing HLW has not been enough studied.
Therefore, the purpose of the research is to assess the regulated properties, composition and structure of...
In the UK, currently the preferred method of immobilising intermediate level waste (ILW) is through the use of Portland cement (PC) based grouts, to produce a passively safe waste package. However, certain types of ILW present a challenge to this method, with the result that this immobilisation matrix may not represent the optimum mechanism available. Such challenges are related to either...
This research is performed in the framework of the MACH3 project, which is funded by the French PIA (Future Investment Plan). MACH3 contributes to the management of radioactive waste containing liquid and gaseous tritium. The reference conditioning process for these waste is cementation, i.e. the immobilisation of the waste using a hydraulic binder. The acceptance of tritiated waste on storage...
Polish research laboratories and hospitals produce liquid organic waste among which are organic solvent waste and aqueous waste contaminated with organic pollutants (waste with high COD), sometimes containing long-lived alpha emitters that require different treatment pathways. The presence of organic substances affects further stages of radioactive waste processing and the safety of its final...
The nuclear fuel cycle operates producing uranium in power generation, in use in medicine and industry, among other areas. This cycle produces various kinds of radioactive waste. Among these, uranyl nitrate solutions with enriched uranium are produced, mainly in the chemical decontamination of parts and materials with fixed contamination. Uranyl nitrate, as addressed in this paper, has...
With the population growth and the technological advances, the demand for efficient and environmentally friendly electric power sources is a certainty that all countries will face in a near future. Despite the usual concepts of green energy, one must agree that nuclear energy is one of the few technologies current available with low carbon emissions and is highly efficient. The raw material...
Spent ion exchange resins were generated from TRIGA PUSPATI Reactor (RTP). Spent resins were used in water purification in nuclear facilities. Spent resins can be classified low level waste and intermediate-low level radioactive waste depend on concentration activity for water treatment and time taken for treatment Generally, these spent ion exchange resins are used 10 – 15 times in nuclear...
