Sample records for alkaline radioactive waste

  1. Alkaline chemistry of transuranium elements and technetium and the treatment of alkaline radioactive wastes

    Goal of this survey is to generalize the known data on fundamental physical-chemical properties of TRUs and Tc, methods for their isolation, and to provide recommendations that will be useful for partitioning them from alkaline high-level wastes

  2. Alkaline chemistry of transuranium elements and technetium and the treatment of alkaline radioactive wastes

    Delegard, C.H. [Westinghouse Hanford Co., Richland, WA (United States); Peretrukhin, V.F.; Shilov, V.P.; Pikaev, A.K. [Russian Academy of Sciences (Russian Federation). Inst. of Physical Chemistry


    Goal of this survey is to generalize the known data on fundamental physical-chemical properties of TRUs and Tc, methods for their isolation, and to provide recommendations that will be useful for partitioning them from alkaline high-level wastes.

  3. Removal of radioruthenium from alkaline intermediate level radioactive waste solution : a laboratory investigation

    Various methods were investigated in the laboratory for the removal of radioruthenium from alkaline intermediate level radioactive waste solutions of reprocessing plant origin. The methods included batch equilibration with different ion exchangers and sorbents, column testing and chemical precipitation. A column method using zinc-activated carbon mixture and a chemical precipitation method using ferrous salt along with sodium sulphite were found to be promising for plant scale application. (author). 10 refs., 3 figs., 7 tabs

  4. Biodegradation of the alkaline cellulose degradation products generated during radioactive waste disposal.

    Simon P Rout

    Full Text Available The anoxic, alkaline hydrolysis of cellulosic materials generates a range of cellulose degradation products (CDP including α and β forms of isosaccharinic acid (ISA and is expected to occur in radioactive waste disposal sites receiving intermediate level radioactive wastes. The generation of ISA's is of particular relevance to the disposal of these wastes since they are able to form complexes with radioelements such as Pu enhancing their migration. This study demonstrates that microbial communities present in near-surface anoxic sediments are able to degrade CDP including both forms of ISA via iron reduction, sulphate reduction and methanogenesis, without any prior exposure to these substrates. No significant difference (n = 6, p = 0.118 in α and β ISA degradation rates were seen under either iron reducing, sulphate reducing or methanogenic conditions, giving an overall mean degradation rate of 4.7 × 10(-2 hr(-1 (SE ± 2.9 × 10(-3. These results suggest that a radioactive waste disposal site is likely to be colonised by organisms able to degrade CDP and associated ISA's during the construction and operational phase of the facility.

  5. Technetium removal column flow testing with alkaline, high salt, radioactive tank waste

    This report describes two bench-scale column tests conducted to demonstrate the removal of Tc-99 from actual alkaline high salt radioactive waste. The waste used as feed for these tests was obtained from the Hanford double shell tank AW-101, which contains double shell slurry feed (DSSF). The tank sample was diluted to approximately 5 M Na with water, and most of the Cs-137 was removed using crystalline silicotitanates. The tests were conducted with two small columns connected in series, containing, 10 mL of either a sorbent, ABEC 5000 (Eichrom Industries, Inc.), or an anion exchanger Reillex trademark-HPQ (Reilly Industries, Inc.). Both materials are selective for pertechnetate anion (TcO4-). The process steps generally followed those expected in a full-scale process and included (1) resin conditioning, (2) loading, (3) caustic wash to remove residual feed and prevent the precipitation of Al(OH)3, and (4) elution. A small amount of Tc-99m tracer was added as ammonium pertechnetate to the feed and a portable GEA counter was used to closely monitor the process. Analyses of the Tc-99 in the waste was performed using ICP-MS with spot checks using radiochemical analysis. Technetium x-ray absorption spectroscopy (XAS) spectra of 6 samples were also collected to determine the prevalence of non-pertechnetate species [e.g. Tc(IV)

  6. Eichrom's ABEC trademark resins: Alkaline radioactive waste treatment, radiopharmaceutical, and potential hydrometallurgical applications

    Eichrom's ABEC trademark resins selectivity extract certain anions from high ionic strength acidic, neutral, or strongly alkaline media, and solute stripping can be accomplished by eluting with water. ABEC resins are stable to pH extreme and radiolysis and operate in high ionic strength and/or alkaline solutions where anion-exchange is often ineffective. Potential applications of the ABEC materials include heavy metal and ReO4- separations in hydrometallurgy and purification of perrhenate iodide, and iodate in radiopharmaceutical production. Separation of 99mTcO4- from its 99MoO42- parent and stripping with water or physiological saline solution have been demonstrated for radiopharmaceutical applications. Removal of 99TcO4- and 129I- from alkaline tank wastes has also been successfully demonstrated. The authors will discuss the scale-up studies, process-scale testing, and market development of this new extraction material

  7. Radioactive Wastes.

    Choudri, B S; Baawain, Mahad


    Papers reviewed herein present a general overview of radioactive waste activities around the world in 2014. These include safety assessments, decommission and decontamination of nuclear facilities, fusion facilities, transportation and management solutions for the final disposal of low and high level radioactive wastes (LLW and HLW), interim storage and final disposal options for spent fuel (SF), and tritiated wastes, with a focus on environmental impacts due to the mobility of radionuclides in water, soil and ecosystem alongwith other progress made in the management of radioactive wastes. PMID:26420096

  8. Radioactive Wastes.

    Choudri, B S; Baawain, Mahad


    Papers reviewed herein present a general overview of radioactive waste activities around the world in 2015. These include safety assessments, decommission and decontamination of nuclear facilities, fusion facilities, transportation and management solutions for the final disposal of low and high level radioactive wastes (LLW and HLW), interim storage and final disposal options for spent fuel (SF), and tritiated wastes, with a focus on environmental impacts due to the mobility of radionuclides in water, soil and ecosystem alongwith other progress made in the management of radioactive wastes. PMID:27620100

  9. Radioactive waste management

    This eighth chapter presents the radioactive wastes and waste disposal; classification of radioactive wastes; basis requests of the radioactive waste management; conditions for a radioactive waste disposal; registers and inventories; transport of radioactive wastes from a facility to another and the radioactive waste management plan

  10. Radioactive waste

    Focusing on radioactive waste management and disposal policies in the United Kingdom, Sweden and the Federal Republic of Germany, this book gives a detailed historical account of the policy process in these three countries, and draws out the implications for theory and public policy. This comparative approach underlines how profoundly different the policy process has been in different countries. By comparing the evolution of policy in three countries, fundamental questions about the formation and resolution of technical decisions under uncertainty are clarified. The analysis of nuclear strategy, the politics of nuclear power, and the shifting emphasis of government regulation redefines the issue of radwaste management and sets it at the heat of the current debate about power, the environment and society. The combination of up-to-date technological assessment with an account of the social and political implications of radwaste management makes'Radioactive Waste'particularly useful to students of environmental studies, geography and public administration. (author)

  11. Technetium in alkaline, high-salt, radioactive tank waste supernate: Preliminary characterization and removal

    This report describes the initial work conducted at Pacific Northwest National Laboratory to study technetium (Tc) removal from Hanford tank waste supernates and Tc oxidation state in the supernates. Filtered supernate samples from four tanks were studied: a composite double shell slurry feed (DSSF) consisting of 70% from Tank AW-101, 20% from AP-106, and 10% from AP-102; and three complexant concentrate (CC) wastes (Tanks AN-107, SY-101, ANS SY-103) that are distinguished by having a high concentration of organic complexants. The work included batch contacts of these waste samples with Reillex trademark-HPQ (anion exchanger from Reilly Industries) and ABEC 5000 (a sorbent from Eichrom Industries), materials designed to effectively remove Tc as pertechnetate from tank wastes. A short study of Tc analysis methods was completed. A preliminary identification of the oxidation state of non-pertechnetate species in the supernates was made by analyzing the technetium x-ray absorption spectra of four CC waste samples. Molybdenum (Mo) and rhenium (Re) spiked test solutions and simulants were tested with electrospray ionization-mass spectrometry to evaluate the feasibility of the technique for identifying Tc species in waste samples

  12. Catalytic decomposition of organic anions in alkaline radioactive wastes. 1. Oxidation of EDTA

    Decomposition of ethylenediaminetetraacetate in alkaline solutions by means of H2O2, Na2S2O8, NaClO, NaBrO is investigated by titrimetric method. It is established that EDTA is oxidized in heated over 60 Deg C solutions in the presence of cobalt salts in the case of step-by-step addition of H2O2 excess. Interaction of persulfate with EDTA is characterized by available induction period, which decreases with NaOH concentration, temperature increase and initial EDTA content decrease or in the presence of AgNO3, K4Fe(CN)6, NaNO2. Mechanism of the process includes thermal dissociation of persulfate ions on ion-radicals and following evolution of the chain reaction. Hypochlorite ions oxidize EDTA in 0.5-5.0 mol/l NaOH solutions in temperature range 25-60 Deg C. Efficiency of the process increases in the case of fractional addition of oxidizer in the presence of Co(II) or Ni(II) salts. EDTA oxidation in alkaline solutions by hypobromite ions takes place only in the case of temperature increase up to 95 Deg C. Co(II), Ni(II), Cu(II) salts accelerates the process

  13. Radioactive wastes

    Here are gathered 1)the decrees (99-686 and 99-687) of the 3 rd of August 1999 relative to the researches on radioactive waste management. A local committee of information and follow-up has to be established on the site of each underground facility. The composition of this committee is determined here (99-686). 3 people will from now on be jointly ordered by the Minister of Economy, Finance and Industry and by the Secretary of State of Industry to conduct a preliminary dialogue for the choice of one or several sites on which previous works should be made before the construction of an underground facility (99-687). They take the opinion of the people's representatives, the associations and the concerned population and inform the Ministers of Environment, Energy and Research of the collected information. 2)the decree of the 3 rd of August 1999 authorizing the 'Agence nationale pour la gestion des dechets radioactifs' (ANDRA) to install and exploit an underground facility located in Bure (Meuse) and intended to study the deep geological deposits where could be stored radioactive wastes. (O.M.)

  14. Column loading and elution behavior of rubidium during ion exchange separation of cesium from alkaline radioactive waste

    The uptake of fission product rubidium by Resorcinol Formaldehyde Polycondensate Resin (RFPR) from alkaline test solutions was studied in batch contact experiments. A column run was conducted to determine its loading and elution behaviour. In the context of recovery of 137Cs from reprocessing waste, the results of these experiments have been used to estimate the concentration of rubidium in the 137Cs solution obtained after elution. (author)

  15. Solidification of radioactive liquid wastes

    Purpose: To decrease the amount of surface active agents required for solidifying sodium sulfate-containing concentrated radioactive liquid wastes with asphalts. Method: Water soluble calcium compounds (calcium nitrate, etc.) are added to alkaline radioactive concentrated liquid wastes essentially consisting of sodium sulfate to adjust the pH value of the liquid wastes to 4.5 - 8.5. The addition amount of the water soluble calcium compounds (based on the weight of the calcium ions) is set to about 2 - 5% of the sulfate ions in the liquid wastes. Then, surface active agents are added by 3 - 10 weight % to the solid contents in the liquid wastes. (Ikeda, J.)

  16. Waterproofing improvement of radioactive waste asphalt solid

    Purpose: To improve the waterproofing of asphalt solid by adding an alkaline earth metal salt and, further, paraffin, into radioactive liquid waste when processing asphalt solidification of the radioactive liquid waste. Method: Before processing molten asphalt solidification of radioactive liquid waste, soluble salts of alkaline earth metal such as calcium chloride, magnesium chloride, or the like is added to the radioactive liquid waste. Paraffin having a melting point of higher than 600C, for example, is added to the asphalt, and waterproofing can be remarkably improved. The waste asphalt solid thus fabricated can prevent the swelling thereof, and can improve its waterproofing. (Yoshihara, H.)

  17. Radioactive Demonstration of Caustic Recovery from Low-Level Alkaline Nuclear Waste by an Electrochemical Separation Process

    Bench-scale radioactive tests successfully demonstrated an electrochemical process for the recovery of sodium hydroxide (caustic) from Decontaminated Salt Solution produced from the In-Tank Precipitation and Effluent Treatment Processes at the Savannah River Site (SRS). This testing evaluated two membranes: an organic-based membrane, Nafion Type 350, manufactured by E. I. duPont de Nemours ampersand Company, Inc. (DuPont) and an inorganic-based membrane, NAS D, being developed by Ceramatec. Both membranes successfully separated caustic from radioactive SRS waste.Key findings of the testing indicate the following attributes and disadvantages of each membrane. The commercially-available Nafion membrane proved highly conductive. Thus, the electrochemical cell can operate at high current density minimizing the number of cells at the desired volumetric processing rate. Testing indicated cesium transported across the Nafion membrane into the caustic product. Therefore, the caustic product will contain low-levels of radioactive cesium due to the presence of 134,137Cs in the waste feed. To meet customer requirements, a post treatment stage may prove necessary to remove radioactive cesium resulting in increased overall process costs and decreased cost savings. In contrast to the Nafion membrane, the NAS D membrane demonstrated the production of caustic with much lower levels of gamma radioactivity (137Cs activity was < 51 dpm/g). Therefore, the caustic product could possibly release for onsite/offsite use without further treatment. The NAS D membrane remains in the development stage and does not exist as a commercial product. Operating costs and long-term membrane durability remain unknown.Caustic recovery has been successfully demonstrated in a bench-scale, 2-compartment electrochemical reactor operated for brief periods of time with simulated and radioactive waste solutions and two different types of membranes. The next phase of testing should be directed at (1

  18. Radioactive wastes

    The execution of the Brazilian nuclear power program involves the generation of radwastes, some of which must be isolated, for several centuries, from human activities and environment. The Materials Directory from National Nuclear Energy Commission (CNEN) organized a project in order to collect information concerning the waste disposal practices that may fulfill national technical-social-economic conditions and to recommend them, if requested, to the competent authorities. The paper provides general information concerning the waste producers, the project organization, the regions in Brazil that should be investigated in more detail during the site selection studies, as well as the preliminary conclusion in waste management area

  19. Radioactive waste management

    This booklet is a publication by International Atomic Energy Agency for general awareness of citizens and policy-makers to clarify their concept of nuclear wastes. In a very simple way it tells what is radioactivity, radiations and radioactive wastes. It further hints on various medial and industrial uses of radiations. It discusses about different types of radioactive wastes and radioactive waste management. Status of nuclear power plants in Central and Eastern European countries are also discussed

  20. Influence of a hyper-alkaline solution on six different bentonites with potential use as buffer barriers for radioactive waste confinement

    The cementitious material in a nuclear waste repository will act as a source of alkaline fluids modifying the mineralogy, pH and physico-chemical properties of the bentonite barrier. A series of reactivity experiments were proposed to determine and compare the response of MX-80 and other five types of bentonite with potential use as buffer barriers. These materials are the Ca,Na-dominant FEBEX bentonite (considered as the reference buffer material in the Spanish concept of radioactive waste confinement), an homogenized in magnesium FEBEX sample, the Na-activated Bentonil C2 commercial bentonite, a saponite from the Madrid basin designated 'saponite from el Cerro del Aguila', and a montmorillonite- rich Na-bentonite from Chile. This study proves that the use of bentonite with saponitic character could be an alternative to the commonly accepted di-octahedral types of bentonite due to their mineralogical and physico-chemical stability under the alkaline cement influence at long term. The completion of these experiments of interaction between OPC (Ordinary Portland Cement) pore water and different types of bentonite helps to determine possible reaction paths in the early stage of cement leaching at the concrete - bentonite interface. (authors)

  1. Radioactive wastes and discharges

    The guide sets out the radiation safety requirements and limits for the treatment of radioactive waste. They shall be observed when discharging radioactive substances into the atmosphere or sewer system, or when delivering solid, low-activity waste to a landfill site without a separate waste treatment plan. The guide does not apply to the radioactive waste resulting from the utilisation of nuclear energy or natural resources

  2. Radioactive wastes and discharges



    The guide sets out the radiation safety requirements and limits for the treatment of radioactive waste. They shall be observed when discharging radioactive substances into the atmosphere or sewer system, or when delivering solid, low-activity waste to a landfill site without a separate waste treatment plan. The guide does not apply to the radioactive waste resulting from the utilisation of nuclear energy or natural resources.

  3. Understanding radioactive waste

    Murray, R.L.


    This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes). (ATT)

  4. Understanding radioactive waste

    This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes)

  5. Treatment of radioactive wastes

    This report is a review of some waste management activities including sources, system of collection and treatment of radioactive wastes. The report also includes methods and options used for treatment of liquid and solid radioactive wastes. (author). 26 refs., 5 figs., 6 tabs

  6. Predisposal Radioactive Waste Management

    Recognition of the importance of the safe management of radioactive waste means that, over the years, many well-established and effective techniques have been developed, and the nuclear industry and governments have gained considerable experience in this field. Minimization of waste is a fundamental principle underpinning the design and operation of all nuclear operations, together with waste reuse and recycling. For the remaining radioactive waste that will be produced, it is essential that there is a well defined plan (called a waste treatment path) to ensure the safe management and ultimately the safe disposal of radioactive waste so as to guarantee the sustainable long term deployment of nuclear technologies

  7. Controlling radioactive waste

    The guideline of the Ministry for Environmental Protection for controlling radioactive waste with a negligible development of heat defines in detail what data are relevant to the control of radioactive waste and should be followed up on and included in a system of documentation. By introducing the AVK (product control system for tracing the course of waste disposal) the operators of German nuclear power plants have taken the requirements of this guideline into account. In particular, possibilities for determining the degree of radioactivity of radioactive waste, which the BMU-guidelines call for, were put into practice by means of the programming technology of the product control system's module MOPRO. (orig.)

  8. Remediation of alkaline intermediate level radioactive aqueous liquid waste stored along with organic waste at PREFRE Tarapur for ion exchange process: a laboratory scale study

    Dibutyl phosphate (DBP) and monobutyl phosphate (MBP) are formed during reprocessing of spent fuel as degradation products of Tributyl phosphate (TBP). To maintain the efficiency of TBP solvent during its repeated use, the degraded products are removed by sodium carbonate washing of the solvent. This radioactive sodium carbonate solution is stored in a separate tank along with the exhausted TBP solvent. The presence of degraded products of TBP and their complexes, ion exchange treatment of this waste is creating problems during alpha decontamination step. The present paper deals with the remediation of the aqueous phase of the above waste. For the treatment of the aqueous phase of waste, first the TBP degraded products are required to be removed so that the normal ion exchange treatment can be adopted. (author)

  9. Radioactive waste management

    The purpose of this document is to set out the Government's current strategy for the long term in the management of radioactive wastes. It takes account of the latest developments, and will be subject to review in the light of future developments and studies. The subject is discussed under the headings: what are radioactive wastes; who is responsible; what monitoring takes place; disposal as the objective; low-level wastes; intermediate-level wastes; discharges from Sellafield; heat generating wastes; how will waste management systems and procedures be assessed; how much more waste is there going to be in future; conclusion. (U.K.)

  10. Radioactive waste disposal

    The current disposal concept for radioactive waste in the FRG was discussed in the framework of this seminar. In addition to this concept for the treatment of radioactive waste also the volume of this waste is indicated. The present state of the two repositories 'Konrad' and 'Gorleben' is explained, as well as the requirements on waste packages for transportation, intermediate and ultimate storage. The final part discusses the conditioning of this radioactive waste and the control of the barrels as regards the observance of the requirements. (orig.)

  11. Radioactive wastes and discharges

    According to the Section 24 of the Finnish Radiation Decree (1512/91), the Finnish Centre for Radiation and Nuclear Safety shall specify the concentration and activity limits and principles for the determination whether a waste can be defined as a radioactive waste or not. The radiation safety requirements and limits for the disposal of radioactive waste are given in the guide. They must be observed when discharging radioactive waste into the atmosphere or sewer system, or when delivering solid low-activity waste to a landfill site without a separate waste disposal plan. The guide does not apply to the radioactive waste resulting from the utilization of nuclear energy of natural resources. (4 refs., 1 tab.)

  12. ORNL radioactive waste operations

    Since its beginning in 1943, ORNL has generated large amounts of solid, liquid, and gaseous radioactive waste material as a by-product of the basic research and development work carried out at the laboratory. The waste system at ORNL has been continually modified and updated to keep pace with the changing release requirements for radioactive wastes. Major upgrading projects are currently in progress. The operating record of ORNL waste operation has been excellent over many years. Recent surveillance of radioactivity in the Oak Ridge environs indicates that atmospheric concentrations of radioactivity were not significantly different from other areas in East Tennesseee. Concentrations of radioactivity in the Clinch River and in fish collected from the river were less than 4% of the permissible concentration and intake guides for individuals in the offsite environment. While some radioactivity was released to the environment from plant operations, the concentrations in all of the media sampled were well below established standards

  13. Biotic and abiotic catalysis of nitrate reduction in alkaline environment of repository storage cell for long-lived intermediate-level radioactive wastes

    This study investigates the reactivity of nitrates at the bitumen-concrete interface with the aim of determining redox conditions inside a repository storage cell for long-lived intermediate-level radioactive wastes. The first part of the work aimed to identify, under abiotic conditions, the interactions between two components of the system: concrete (introduced as cement pastes in the system) and bitumen (represented by leachates composed of organic acids and nitrates). The second part of the study was conducted under biotic conditions with selected denitrifying heterotrophic bacteria (Pseudomonas stutzeri - Ps and Halomonas desiderata - Hd) and aimed to analyse the microbial reaction of nitrate reduction (kinetics, by-products, role of the organic matter) under neutral to alkaline pH conditions (i.e. imposed by a concrete environment). Results showed that strong interactions occurred between cementitious matrices and acetic and oxalic organic acids, likely reducing the bio-availability of this organic matter (oxalate in particular). Results also confirmed the stability of nitrates under these conditions. Under biotic conditions, nitrates were reduced by both Ps and Hd following an anaerobic denitrification metabolic pathway. Reduction kinetics was higher with Ps but the reaction was inhibited for pH ≥ 9. Hd was capable of denitrification at least up to pH 11. (authors)

  14. Radioactive waste disposal policy

    The responsibilities of the Minister of Agriculture, Fisheries and Food and Ministry policy on radioactive waste disposal are described. The disposal of solid radioactive waste at sea is subject to detailed safeguards developed within two international agreements to which the United Kingdom is a contracting party. The agreements are discussed together with a research and monitoring programme to provide scientific data for informed decisions on waste disposal authorisations and dumping licences. (U.K.)

  15. Radioactive waste management

    First, some general informations are given about radioactive waste, e.g. arising of waste, classification, intermediate deposition and transport, as well as about the multi-barrier concept. Then, emphasis is laid on the internationally favoured vitrification of high-active waste. Safety requirements and the physical-chemical characteristics of the waste forms are described as are the different technical vitrification processes. Moreover, alternative solidification products such as ceramic materials and synthetic rocks were discussed. In addition, the worldwide technical concepts for the management and final disposal of radioactive waste are summarized. (orig./HP)

  16. Encapsulation of radioactive waste

    A method is described for encapsulating a particular radioactive waste which consists of suspending the waste in a viscous liquid encapsulating material, of synthetic resin monomers or prepolymers, and setting the encapsulating material by addition or condensation polymerization to form a solid material in which the waste is dispersed. (author)

  17. Classification of radioactive waste

    Radioactive wastes are generated in a number of different kinds of facilities and arise in a wide range of concentrations of radioactive materials and in a variety of physical and chemical forms. To simplify their management, a number of schemes have evolved for classifying radioactive waste according to the physical, chemical and radiological properties of significance to those facilities managing this waste. These schemes have led to a variety of terminologies, differing from country to country and even between facilities in the same country. This situation makes it difficult for those concerned to communicate with one another regarding waste management practices. This document revises and updates earlier IAEA references on radioactive waste classification systems given in IAEA Technical Reports Series and Safety Series. Guidance regarding exemption of materials from regulatory control is consistent with IAEA Safety Series and the RADWASS documents published under IAEA Safety Series. 11 refs, 2 figs, 2 tab

  18. Plastic solidification method for radioactive waste

    Condensed liquid wastes in radioactive wastes are formed by mixing and condensing several kinds of liquid wastes such as liquid wastes upon regeneration of ion exchange resins, floor draining liquid wastes and equipment draining liquid wastes. Accordingly, various materials are contained, and it is found that polymerization reaction of plastics is inhibited especially when reductive material, such as sodium nitrite is present. Then, in the present invention, upon mixing thermosetting resins to radioactive wastes containing reducing materials, an alkaline material is admixed to an unstaturated polyester resin. This can inactivate the terminal groups of unsaturated polyester chain, to prevent the dissociation of the reducing agent such as sodium nitrite. Further, if an unsaturated polyester resin of low acid value and a polymerization initiator for high temperature are used in addition to the alkaline material, the effect is further enhanced, thereby enabling to obtain a strong plastic solidification products. (T.M.)

  19. Radioactive waste management

    This book highlights the main issues of public concern related to radioactive waste management and puts them into perspective. It provides an overview of radioactive waste management covering, among other themes, policies, implementation and public communication based on national experiences. Its purpose is to assists in increasing the understanding of radioactive waste management issues by public and national authorities, organizations involved in radioactive waste management and the nuclear industry; it may also serve as a source book for those who communicate with the public. Even in the unlikely event that nuclear power does not further develop around the world, the necessity for dealing with nuclear waste from past usages, from uranium mining and milling, decontamination and decommissioning of existing nuclear facilities and from the uses of radioactive materials in medicine, industry and research would still exist. In many countries, radioactive waste management planning involves making effective institutional arrangements in which responsibilities and liabilities are well established for the technical operation and long term surveillance of disposal systems. Financing mechanisms are part of the arrangements. Continuous quality assurance and quality control, at all levels of radioactive waste management, are essential to ensure the required integrity of the system. As with any other human activity, improvements in technology and economics may be possible and secondary problems avoided. Improvements and confirmation of the efficiency of processes and reduction of uncertainties can only be achieved by continued active research, development and demonstration, which are the goals of many national programmes. International co-operation, also in the form of reviews, can contribute to increasing confidence in the ongoing work. The problem of radioactive wastes is not a unique one; it may be compared with other problems of toxic wastes resulting from many other

  20. Radioactive waste management

    This chapter discussed the basic subjects covered in the radioactive waste management. The subjects are policy and legislation, pre-treatment, classification, segregation, treatment, conditioning, storage, siting and disposal, and quality assurance

  1. Radioactive waste management

    Throughout this century, the application of nuclear energy has produced many benefits, in industry, in research, in medicine, and in the generation of electricity. These activities generate wastes in the same way as do other human activities. The primary objective of radioactive waste management is to protect human health and environment now and in the future without imposing undue burden on future generations, through sound, safe and efficient radioactive waste management. This paper briefly describes the different steps of the management of short lived low and intermediate level wastes, and presents and overview of the state of art in countries involved in nuclear energy, describing their organizations, methodologies used in the processing of these wastes and the final disposal concepts. It also presents the Argentine strategy, its technical and legal aspects. Worldwide experience during the past 50 years has shown that short lived low and intermediate level wastes can be successfully isolated from human and environment in near surface disposal facilities. (author)

  2. Disposal of Radioactive Waste

    This Safety Requirements publication applies to the disposal of radioactive waste of all types by means of emplacement in designed disposal facilities, subject to the necessary limitations and controls being placed on the disposal of the waste and on the development, operation and closure of facilities. The classification of radioactive waste is discussed. This Safety Requirements publication establishes requirements to provide assurance of the radiation safety of the disposal of radioactive waste, in the operation of a disposal facility and especially after its closure. The fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. This is achieved by setting requirements on the site selection and evaluation and design of a disposal facility, and on its construction, operation and closure, including organizational and regulatory requirements.

  3. Radioactive wastes management

    This article presents the French way to deal with nuclear wastes. 4 categories of radioactive wastes have been defined: 1) very low-level wastes (TFA), 2) low or medium-wastes with short or medium half-life (A), 3) low or medium-level wastes with long half-life (B), and 4) high-level wastes with long half-life (C). ANDRA (national agency for the management of radioactive wastes) manages 2 sites of definitive surface storage (La-Manche and Aube centers) for TFA-wastes. The Aube center allows the storage of A-wastes whose half-life is less than 30 years. This site will receive waste packages for 50 years and will require a regular monitoring for 300 years after its decommissioning. No definitive solutions have been taken for B and C wastes, they are temporarily stored at La Hague processing plant. Concerning these wastes the French parliament will have to take a decision by 2006. At this date and within the framework of the Bataille law (1991), scientific studies concerning the definitive or retrievable storage, the processing techniques (like transmutation) will have been achieved and solutions will be proposed. These studies are numerous, long and complex, they involve fresh knowledge in geology, chemistry, physics,.. and they have implied the setting of underground facilities in order to test and validate solutions in situ. This article presents also the transmutation technique. (A.C.)

  4. Management on radioactive wastes

    The basic philosophy governing the radioactive waste management activities in India is to concentrate and contain as much activity as possible and to discharge to the environment only such of these streams that have radioactive content much below the nationally and internationally accepted standards. The concept of ''Zero Release'' is also kept in view. At Tarapur, the effluents are discharged into coastal waters after the radioactivity of the effluents is brought down by a factor 100. The effluents fΩm Rajasthan reactors are discharged into a lake keeping their radioactivity well within permissible limits and a solar evaporation plant is being set up. The plant, when it becomes operational, will be a step towards the concept of ''Zero Release''. At Kalpakkam, the treated wastes are proposed to be diluted by circulating sea water and discharged away from the shore through a long pipe. At Narora, ion exchange followed by chemical precipitation is to be employed to treat effluents and solar evaporation process for total containment. Solid wastes are stored/dispsed in the concrete trenches, underground with the water proofing of external surfaces and the top of the trench is covered with concrete. Highly active wastes are stored/disposed in tile holes which are vaults made of steel-lined, reinforced concrete pipes. Gas cleaning, dilution and dispersion techniques are adopted to treat gaseous radioactive wastes. (M.G.B.)

  5. Radioactive waste storage issues

    In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state's boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected

  6. Radioactive waste storage issues

    Kunz, D.E.


    In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

  7. Radioactive waste management in Hungary

    Activities underway at various levels in Hungary in the field of the safe management and disposal of radioactive waste and spent fuel are outlined. Various specific aspects, including financing of radioactive waste management, handling of spent fuel, high level radioactive waste disposal, site selection for a disposal facility for low and intermediate level waste, and public information activities are described. (author)

  8. Radioactive wastes in Oklo

    The acceptance of the Nuclear Energy as electric power supply implies to give answer to the population on the two main challenges to conquer in the public opinion: the nuclear accidents and the radioactive wastes. Several of the questions that are made on the radioactive wastes, its are the mobility migration of them, the geologic stability of the place where its are deposited and the possible migration toward the aquifer mantels. Since the half lives of the radioactive waste of a Nuclear Reactor are of several hundred of thousands of years, the technical explanations to the previous questions little convince to the public in general. In this work summary the results of the radioactive waste generated in a natural reactor, denominated Oklo effect that took place in Gabon, Africa, it makes several thousands of millions of years, a lot before the man appeared in the Earth. The identification of at least 17 reactors in Oklo it was carried out thanks to the difference in the concentrations of Uranium 235 and 238 prospective, and to the analysis of the non-mobility of the radioactive waste in the site. It was able by this way to determine that the reactors with sizes of hardly some decimeter and powers of around 100 kilowatts were operating in intermittent and spontaneous form for space of 150,000 years, with operation cycles of around 30 minutes. Recent studies have contributed information valuable on the natural confinement of the radioactive waste of the Oklo reactors in matrixes of minerals of aluminum phosphate that caught and immobilized them for thousands of millions of years. This extracted information from the nature contributes guides and it allows 'to verify' the validity of the current proposals on the immobilization of radioactive wastes of a nuclear reactor. This work presents in clear and accessible form to the public in general on the secure 'design', operation, 'decommissioning' and 'storage' of the radioactive waste of the reactors that the nature put

  9. Radioactive waste processing method

    When granular materials comprising radioactive wastes containing phosphorus are processed at first in a fluidized bed type furnace, if the granular materials are phosphorus-containing activated carbon, granular materials comprising alkali compound such as calcium hydroxide and barium hydroxide are used as fluidizing media. Even granular materials of slow burning speed can be burnt stably in a fluidizing state by high temperature heat of the fluidizing media, thereby enabling to take a long burning processing time. Accordingly, radioactive activated carbon wastes can be processed by burning treatment. (T.M.)

  10. Radioactive waste management and handling

    In this paper, mainly from the radioactive solid waste separation, treatment details of Shaanxi uranium Enrichment Co., Ltd. the actual situation of radioactive waste management, and solid radioactive waste by raising the whole preparation, storage for planning. Through the planning to address the company's accumulation of radioactive waste, more and more waste repository issue of storage space is shrinking each year. Planning is mainly to establish compression volume reduction system, to be accumulated to a certain amount of radioactive waste, the compressed volume reduction package, packaged material blocks passing through the surface contamination testing was conducted after the weighing to measure, and paste the labels, establishing a database and record sets account, record the weight, type, date, etc. after the warehouse store. Would be a good package of radioactive solid waste brought to the state designated for storage of radioactive waste storage sites. By planning the company's radioactive solid waste control and management has been continued to improve. (authors)

  11. Radioactive waste processing device

    Liquid wastes are supplied to a ceramic filter to conduct filtration. In this case, a device for adding a powdery inorganic ion exchanger is disposed to the upstream of the ceramic filter. When the powdery inorganic ion exchanger is charged to the addition device, it is precoated to the surface of the ceramic filter, to conduct separation of suspended matters and separation of ionic nuclides simultaneously. Liquid wastes returned to a collecting tank are condensed while being circulated between the ceramic filter and the tank and then contained in a condensation liquid waste tank. With such a constitution, both of radioactive nuclides accompanied by suspended matters in the radioactive liquid wastes and ionic nuclides can be captured efficiently. (T.M.)

  12. Underground storage of radioactive wastes

    An introductory survey of the underground disposal of radioactive wastes is given. Attention is paid to various types of radioactive wastes varying from low to highly active materials, as well as mining techniques and salt deposits

  13. Method of packaging radioactive wastes

    Purpose: To decrease the leaching of radioactive waste in marine environment. Method: Fillers are placed between a drum can and an inner cage for charging radioactive wastes in order to prevent the leakage of the radioactive wastes from the drum can. Leaching inhibitors for radioactive materials are mixed with the fillers made of organic substance such as asphalts and plastics. The leaching inhibitors are made of materials in the similar chemical form to that of the radioactive materials in the wastes and mixed into the fillers to the saturation limit of dissolution. For the radioactive wastes containing spent adsorbents for iodine, the inhibitors are made of silver nitrates. (Ikeda, J.)

  14. Radioactive waste management

    The main issues of the radioactive waste safe management are covered in the monograph. The international knowledge, as well as the national experience in this field are summarized. The technologies and methods used for the safety objective achievement are described. The main attention is paid to the safety norms and rules, to the descriptions of the radwaste management facilities under operation

  15. Radioactive waste processing field

    Storing space for radioactive wastes (storage tunnels) are formed underground of the sea bottom along coast. A plurality of boreholes through which sea water flows are pored vertically in a direction intersecting underground streams of brine in the ground between the tunnels and seaside. Sea water introduction pipes are joined to the upper side walls of the boreholes. The sea water introduction pipes have introduction ports protruded under the sea level of the coastal sea area region. Since sea water flows from the introduction ports to the boreholes passing through the sea water introduction pipes, sea water is always filled in the boreholes. Therefore, brine is sufficiently supplied toward the land by sea water from the boreholes, the underground stream of brine is negligibly small. This can prevent radioactive contamination due to flow of the underground water when radioactive wastes are buried in the underground near coast. (I.N.)

  16. Radioactive waste management glossary

    The Waste Management Glossary defines over 300 terms in the English language that have special meanings when they are used in the context of radioactive waste management. The Glossary is intended to provide a consistent reference for these terms for specialists in this field. It also will assist non-specialists who read IAEA reports dealing with waste management. This is the second edition of the Glossary. It is intended to update and replace its predecessor, TECDOC-264, that was issued in 1982. (author)

  17. Radioactive waste management profiles

    In 1989, the International Atomic Energy Agency began development of the Waste Management Data Base (WMDB) to, primarily, establish a mechanism for the collection, integration, storage, and retrieval of information relevant to radioactive waste management in Member States. This report is a summary and compilation of the information contained in the data base. The WMDB contains information and data on several aspects of waste management and offer a ready source of information on such activities as R and D efforts, waste disposal plans and programmes, important programme milestones, waste volume projections, and national and regulatory policies. This report is divided into two parts. Part one describes the Waste Management Data Base system and the type of information it contains. The second part contains data provided by Member States between August 1989 and December 1990 in response to a questionnaire sent by the Agency. However, if a Member State did not respond to the questionnaire, data from IAEA sources, such as technical assistance mission reports, were used - where such data exist. The WMDB system became operational in January 1991. The type of information contained in the data base includes radioactive waste management plans, policies and activities in Member States

  18. Radioactive wastes handling facility

    There are disposed an area where a conveyor is disposed for separating miscellaneous radioactive solid wastes such as metals, on area for operators which is disposed in the direction vertical to the transferring direction of the conveyor, an area for receiving the radioactive wastes and placing them on the conveyor and an area for collecting the radioactive wastes transferred by the conveyor. Since an operator can conduct handling while wearing a working cloth attached to a partition wall as he wears his ordinary cloth, the operation condition can be improved and the efficiency for the separating work can be improved. When the area for settling conveyors and the area for the operators is depressurized, cruds on the surface of the wastes are not released to the outside and the working clothes can be prevented from being involved. Since the wastes are transferred by the conveyor, the operator's moving range is reduced, poisonous materials are fallen and moved through a sliding way to an area for collecting materials to be separated. Accordingly, the materials to be removed can be accumulated easily. (N.H.)

  19. Management of hospital radioactive wastes

    The general structure of a regulatory scheme for the management of hospital radioactive wastes is presented. The responsabilities of an institution in the radioactive waste management, and storage conditions are defined. The radioactive wastes are classified in physical terms, and the criteria for evaluating the activity of solid wastes are described. The container characteristics and, the types of treatments given to the wastes are specified. (M.C.K.)

  20. Radioactive waste management

    The OECD Nuclear Energy Agency (NEA) attaches considerable importance to its cooperation with Japan. It was said in the annual conference in 1977 that the presentation of the acceptable policy regarding radioactive waste management is the largest single factor for gaining public confidence when nuclear power is adopted with assurance. The risk connected with radioactive wastes was often presented as the major obstacle to the development of nuclear energy, however, an overall impression of optimism and confidence prevailed by the technical appraisal of the situation in this field by the committee of the NEA. This evolution can be easily explained by the significant progress achieved in radioactive waste management both at the technical level and with respect to the implementation of special legislation and the establishment of specialized institutions and financing schemes. More research will focus on the optimization of the technical, safety and economic aspects of specific engineering designs at specific sites on the long term isolation of wastes, and the NEA contributes to this general effort. The implementation of disposal programs is also in progress. (Kako, I.)

  1. The radioactive wastes management

    The different types of radioactive waste are presented in this paper in the frame of the official categories which take into account their dangerousness and the lifetimes of their radioactivity. It is indicated how the less dangerous of them are handled in France. The ways of protecting the environment from the more dangerous ones (high activity and long lifetimes) are object of studies. Scientific questions, in the field of chemistry and physical chemistry, related to the implementation of deep underground repository facilities with full respect of nuclear safety are presented. (authors)

  2. Categorizing operational radioactive wastes

    The primary objective of this publication is to improve communications among waste management professionals and Member States relative to the properties and status of radioactive waste. This is accomplished by providing a standardized approach to operational waste categorization using accepted industry practices and experience. It is a secondary objective to draw a distinction between operational waste categorization and waste disposal classification. The approach set forth herein is applicable to waste generation by mature (major, advanced) nuclear programmes, small-to-medium sized nuclear programmes, and programmes with waste from other nuclear applications. It can be used for planning, developing or revising categorization methodologies. For existing categorization programmes, the approach set forth in this publication may be used as a validation and evaluation tool for assessing communication effectiveness among affected organizations or nations. This publication is intended for use by waste management professionals responsible for creating, implementing or communicating effective categorization, processing and disposal strategies. For the users of this publication, it is important to remember that waste categorization is a communication tool. As such, the operational waste categories are not suitable for regulatory purposes nor for use in health and safety evaluations. Following Section 1 (Introduction) Section 2 of this publication defines categorization and its relationship to existing waste classification and management standards, regulations and practices. It also describes the benefits of a comprehensive categorization programme and fundamental record considerations. Section 3 provides an overview of the categorization process, including primary categories and sub-categories. Sections 4 and 5 outline the specific methodology for categorizing unconditioned and conditioned wastes. Finally, Section 6 provides a brief summary of critical considerations that

  3. Low level radioactive waste

    More than 10 new disposal facilities for low level radioactive waste are now under development in the USA. They were planned in the wake of the highly visible failures of three such sites and a widespread loss of public confidence, both in shallow burial technology and the federal government's ability to regulate commercial waste disposal enterprises. The development of new technology and active involvement of state governments presents the nuclear power industry with its best opportunity for regaining the public confidence that it lost during the 1970s. This paper critically explores the fundamental technical, economic, political and value issues at stake in this process. (author)

  4. Final disposal of radioactive waste

    Freiesleben H.


    In this paper the origin and properties of radioactive waste as well as its classification scheme (low-level waste – LLW, intermediate-level waste – ILW, high-level waste – HLW) are presented. The various options for conditioning of waste of different levels of radioactivity are reviewed. The composition, radiotoxicity and reprocessing of spent fuel and their effect on storage and options for final disposal are discussed. The current situation of final waste disposal in a selected number of c...

  5. Radioactive waste management policies

    Eight senior government representatives outlined the views and policies of their countries in the field of radioactive waste management at a 'scientific afternoon' during the 27th Regular Session of the General Conference of the IAEA in Vienna in October. The countries represented were Argentina, France, the Federal Republic of Germany, India, Japan, Sweden, the United Kingdom, and the USA; statements made by the participants are reproduced in this article

  6. Radioactive waste management glossary

    Terminology used in documents published by the IAEA is frequently defined in glossaries in the separate documents so that understanding is enhanced, particularly for terms having unique meanings in the field of radioactive waste management. This has been found to be a good practice but frequently a burdensome one, too. In addition, terms in various documents occasionally were used differently. Thus, a common glossary of terms for radioactive waste management documents is believed to have merit. This glossary has been developed for use in IAEA documentation on radioactive waste management topics. The individual items have been compiled by selecting terms and definitions from thirty sources, listed on the next page, and numerous people. An effort has been made to use the definitions in internationally-accepted glossaries (e.g. ICRP, ICRU, ISO), with minimum modification; similarly, definitions in recently published IAEA documents have been respected. Nevertheless, when modifications were believed appropriate, they have been made. The glossary, stored on magnetic tape, is intended to be used as a standard for terminology for IAEA use; it is hoped that some benefits of common international terminology may result from its use in IAEA documentation

  7. Argentina's radioactive waste disposal policy

    The Argentina policy for radioactive waste disposal from nuclear facilities is presented. The radioactive wastes are treated and disposed in confinement systems which ensure the isolation of the radionucles for an appropriate period. The safety criteria adopted by Argentina Authorities in case of the release of radioactive materials under normal conditions and in case of accidents are analysed. (M.C.K.)

  8. Radioactive waste: Issues and debates

    Waste management in general has always been in terms of regulation Environmental, a subject of attention but also voltages. Radioactive waste management is no exception to the rule and concentrates, sometimes irrationally, the vast majority industry fears nuclear. The first difficulty is to define radioactive waste, which raises further questions with regard to the case law on this topic and reactions of stakeholders. One of the other components of the debate on radioactive waste is the ability of different actors to ensure sustainable waste management Radioactive in optimum conditions in terms of nuclear safety.This results in the acceptance management solutions by the public.

  9. Storage of radioactive wastes

    Even if the best waste minimization measures are undertaken throughout radioisotope production or usage, significant radioactive wastes arise to make management measures essential. For developing countries with low isotope usage and little or no generation of nuclear materials, it may be possible to handle the generated waste by simply practicing decay storage for several half-lives of the radionuclides involved, followed by discharge or disposal without further processing. For those countries with much larger facilities, longer lived isotopes are produced and used. In this situation, storage is used not only for decay storage but also for in-process retention steps and for the key stage of interim storage of conditioned wastes pending final disposal. The report will serve as a technical manual providing reference material and direct step-by-step know-how to staff in radioisotope user establishments and research centres in the developing Member States without nuclear power generation. Considerations are limited to the simpler storage facilities. The restricted quantities and low activity associated with the relevant wastes will generally permit contact-handling and avoid the need for shielding requirements in the storage facilities or equipment used for handling. A small quantity of wastes from some radioisotope production cells and from reactor cooling water treatment may contain sufficient short lived activity from activated corrosion products to require some separate decay storage before contact-handling is suitable. 16 refs, 12 figs, 8 tabs

  10. Natural radioactivity of wastes

    By-products of the combustion of coal (wastes) are often used for various types of construction (dwellings, roads, etc.). The legal regulations (The Ordinance of the Council of Ministers of 2 January 2007 'On the requirements for the content of natural radioactive isotopes of potassium K-40, radium Ra-226 and thorium Th-228 in raws and materials used in buildings for the residence of people and livestock, as well as in the industrial by-products used in the construction, and the control of the content of the aforementioned isotopes' - Law Gazette no. 4/2007 item 29) are in force in Poland. The regulations permit the possibility of utilization of raws and by-products basing upon the level of the natural radioactivity of the examined raws and materials. The article is a survey of the results obtained during the measurements of many types of raws and building materials for almost 30 years by the network of the laboratories in Poland. It is based upon the results stored in the database of the Central Laboratory for Radiological Protection (CLRP), Warsaw. The article tends to outline the radioactivity of the waste materials with respect to other raws and materials used in the construction industry. The article shows the possibilities for the use of by-products originating in the power stations and heat- and power stations (mainly ashes, slag and hinter) in the construction of dwellings and roads. (authors)

  11. Management of radioactive wastes

    The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprises 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the synthesis of the round table debates which took place at Joinville, i.e. in the same area as the Bure underground laboratory of Meuse/Haute-Marne. Therefore, the discussion focuses more on the local impacts of the setting up of a waste disposal facility (environmental aspects, employment, economic development). (J.S.)

  12. National inventory of radioactive wastes

    There are in France 1064 sites corresponding to radioactive waste holders that appear in this radioactive waste inventory. We find the eighteen sites of E.D.F. nuclear power plants, The Cogema mine sites, the Cogema reprocessing plants, The Cea storages, the different factories and enterprises of nuclear industry, the sites of non nuclear industry, the Andra centers, decommissioned installations, disposals with low level radioactive wastes, sealed sources distributors, national defence. (N.C.)

  13. Regulation of radioactive waste management

    This bulletin contains information about activities of the Nuclear Regulatory Authority of the Slovak Republic (UJD). In this leaflet the regulation of radioactive waste management of the UJD are presented. Radioactive waste (RAW) is the gaseous, liquid or solid material that contains or is contaminated with radionuclides at concentrations or activities greater than clearance levels and for which no use is foreseen. The classification of radioactive waste on the basis of type and activity level is: - transition waste; - short lived low and intermediate level waste (LlLW-SL); - long lived low and intermediate level waste (LlLW-LL); - high level waste. Waste management (in accordance with Act 130/98 Coll.) involves collection, sorting, treatment, conditioning, transport and disposal of radioactive waste originated by nuclear facilities and conditioning, transport to repository and disposal of other radioactive waste (originated during medical, research and industrial use of radioactive sources). The final goal of radioactive waste management is RAW isolation using a system of engineered and natural barriers to protect population and environment. Nuclear Regulatory Authority of the Slovak Republic regulates radioactive waste management in accordance with Act 130/98 Coll. Inspectors regularly inspect and evaluate how the requirements for nuclear safety at nuclear facilities are fulfilled. On the basis of safety documentation evaluation, UJD issued permission for operation of four radioactive waste management facilities. Nuclear facility 'Technologies for treatment and conditioning contains bituminization plants and Bohunice conditioning centre with sorting, fragmentation, evaporation, incineration, supercompaction and cementation. Final product is waste package (Fibre reinforced container with solidified waste) acceptable for near surface repository in Mochovce. Republic repository in Mochovce is built for disposal of short lived low and intermediate level waste. Next

  14. Radioactive Waste Repositories Administration - SURAO

    The Atomic Act specifies, among other things, responsibilities of the government in the field of safe disposal of radioactive wastes. To satisfy this responsibility, the Ministry of Industry and Trade has established the Radioactive Waste Repositories Administration (SURAO). SURAO's major responsibilities include: (a) the preparation, construction, commissioning, operation, and decommissioning of radioactive waste repositories and the monitoring of their environmental impacts; (b) radioactive waste management; (c) spent or irradiated nuclear fuel processing into a form suitable for storage/disposal or reuse; (d) record-keeping of received radioactive wastes and their producers; (e) administration of fund transfers as stipulated by the Atomic Act, Article 27; (f) development of proposals for specification of fees to be paid to the Nuclear Account; (g) responsibility for and coordination of research and development in the field of radioactive waste handling and management; (h) supervision of licensees' margin earmarked for the decommissioning of their facilities; (i) providing services in radioactive waste handling and management; (j) handling and management of radioactive wastes that have been transferred to the Czech Republic from abroad and cannot be sent back; (k) interim administration of radioactive wastes that have become state property. The Statute of the Administration is reproduced in full. (P.A.)

  15. Radioactive waste: show time?

    The basic concept within both EC funded SAPIERR I and SAPIERR II projects (FP6) is that of one or more geological repositories developed in collaboration by two or more European countries to accept spent nuclear fuel, vitrified high-level waste and other long-lived radioactive waste from those partner countries. The SAPIERR II project (Strategic Action Plan for Implementation of Regional European Repositories) examines in detail issues that directly influence the practicability and acceptability of such facilities. This paper describes the work in the SAPIERR II project (2006-2008) on the development of a possible practical implementation strategy for shared, regional repositories in Europe and lays out the first steps in implementing that strategy. (authors)

  16. Radioactive waste: show time?

    Verhoef, E.V. [COVRA N.V., Spanjeweg 1, 4455 TW Nieuwdorp (Netherlands); McCombie, Charles; Chapman, Neil [Arius Association, Taefernstrasse 1, CH-4050 Baden (Switzerland)


    The basic concept within both EC funded SAPIERR I and SAPIERR II projects (FP6) is that of one or more geological repositories developed in collaboration by two or more European countries to accept spent nuclear fuel, vitrified high-level waste and other long-lived radioactive waste from those partner countries. The SAPIERR II project (Strategic Action Plan for Implementation of Regional European Repositories) examines in detail issues that directly influence the practicability and acceptability of such facilities. This paper describes the work in the SAPIERR II project (2006-2008) on the development of a possible practical implementation strategy for shared, regional repositories in Europe and lays out the first steps in implementing that strategy. (authors)

  17. Radioactive waste management in Canada

    Reports and other Canadian literature on radioactive waste processing and disposal covering the period 1953-1979 are listed. A selected list of international conferences relating to waste management (1959-1979) is attached. (LL)

  18. Regulation on radioactive waste management

    A national calculator control system for the metropolitan radioactive waste banks was developed in 1999. The NNSA reviewed by the regulations the feasibility of some rectification projects for uranium ore decommissioning and conducted field inspections on waste treating systems and radioactive waste banks at the 821 plant. The NNSA realized in 1999 the calculator control for the disposal sites of low and medium radioactive waste. 3 routine inspections were organized on the reinforced concrete structures for disposal units and their pouring of concrete at waste disposal site and specific requirements were put forth

  19. Radioactive waste engineering and management

    Nakayama, Shinichi


    This book describes essential and effective management for reliably ensuring public safety from radioactive wastes in Japan. This is the first book to cover many aspects of wastes from the nuclear fuel cycle to research and medical use, allowing readers to understand the characterization, treatment and final disposal of generated wastes, performance assessment, institutional systems, and social issues such as intergenerational ethics. Exercises at the end of each chapter help to understand radioactive waste management in context.

  20. Electrochemical treatment of alkaline nuclear wastes

    Large quantities of highly radioactive waste have been generated throughout the Department of Energy complex over the past 50 years as a result of the production of special nuclear materials for defense and space programs. These wastes have been stored in underground tanks. Some of the tanks have developed cracks that have allowed waste to leak out of the primary tank. Many of the tanks are operating beyond their design life. Processes are being developed to remove the waste from the storage tanks and permanently dispose of it in engineered wasteforms. The bulk of the radioactivity will be concentrated into approximately 1% of the total waste volume and vitrified. The highly radioactive borosilicate glass wasteform will be placed in the federal repository. The remaining waste, which still contains low concentrations of radioactivity, will be incorporated into a low-level wasteform (e.g., cement, glass, ceramic, polymer, etc.) and placed in a near surface facility at the DOE site. Electrochemical-based processes are being evaluated to destroy organic compounds that impact radionuclide separations processes, to destroy or to remove hazardous species in the waste such as nitrates, nitrites, hazardous metals, and radionuclides that can impact wasteform production and characteristics, recovery chemicals of value such as sodium hydroxide (caustic) that can be recycled. Major benefits of such processes include the destruction or removal of hazardous species, waste volume reduction and the recovery of valuable chemicals contained in the waste

  1. Neutronic measurements of radioactive waste

    This document presents the general matters involved in the radioactive waste management and the different non destructive assays of radioactivity. The neutronic measurements used in the characterization of waste drums containing emitters are described with more details, especially the active neutronic interrogation assays with prompt or delayed neutron detection: physical principle, signal processing and evaluation of the detection limit. (author)

  2. Public debate - radioactive wastes management

    Between September 2005 and January 2006 a national debate has been organized on the radioactive wastes management. This debate aimed to inform the public and to allow him to give his opinion. This document presents, the reasons of this debate, the operating, the synthesis of the results and technical documents to bring information in the domain of radioactive wastes management. (A.L.B.)

  3. Method of removing radioactive waste

    A paste prepared by mixing a mixed acid containing HF and at least one of HCl and HNO3 with a paste aid is coated at the surface of radioactive wastes, to dissolve the surface thereof. Water is jetted to remove the dissolved radioactive contaminants and the pastes from the surface of the radioactive wastes. Since the pastes are thus used, the amount of liquid wastes can be remarkably reduced compared with that in a conventional electrolysis method. Further, if it is confirmed that dose rate of the radioactive wastes after decontamination is lower than a predetermined level by adding a step of measuring the extent of contamination of the wastes before and after the steps, they can be handled hereinafter being regarded as ordinary wastes. (T.M.)

  4. Radioactive waste management in Argentina

    An overview is provided on the major nuclear facilities operating in Argentina and data are given on radioactive wastes arising from these operations. The respective legal framework and the nuclear activities, including research and development, are outlined. The programme for the management of the different categories of radioactive wastes is described. Main milestones for establishing geological repositories for intermediate level and high level waste are highlighted. (author)

  5. Process for packaging radioactive waste

    The waste is filled into auxiliary barrels made of sheet steel. It is compressed with the auxiliary barrels into steel jacket bodies. A number of steel jacket bodies are accommodated in storage barrels, which are simultaneously stiffened by them. The radioactive waste is therefore no longer free in the storage barrels, the storage barrels are reinforced and appreciably greater quantities of radioactive waste can be accommodated in the storage barrels and therefore in the stores. (orig./PW)

  6. Radioactive wastes on Kazakhstan territory

    Common amount of radioactive wastes in Kazakhstan makes up 235 million tons. In Semipalatinsk test site in the result of surface and underground explosions low-radioactive wastes have accumulated in the form of soils contaminated with radionuclides and these wastes could be buried during re-cultivation works. In the same time there are places contaminated with plutonium. These soils should be buried in special points. Volume of these wastes is estimated in 5,000 m3. In Kazakhstan there are one power nuclear reactor in Aktau, 3 research reactors on Semipalatinsk site territory and 1 in Almaty city. During operation of BN-350 power reactor in Aktau city till present day 10,000 m3 of different wastes have been accumulated. Great amount of wastes will appear in 2005 during the reactor decommissioning, common volume of processed and packaged wastes after BN-350 reactor out of operation will be estimated in 623,000 m3. In Kazakhstan system of gathering, processing, and transporting of radioactive wastes is not taken into operation yet. According of conception on radioactive wastes burial and IAEA recommendation part of wastes with volume 67,450 m3 (intermediate- and high-level radioactive wastes) are subjected to burial in points in geological formations

  7. Radioactive wastes. Management prospects

    This article describes the perspectives of management of radioactive wastes as defined in the French law from December 30, 1991. This law defines three ways of research: abatement of the radiotoxicity of wastes (first way), reversible geological storage (second way) or long duration geological disposal (third way). This article develops these three solutions: 1 - strategic perspectives; 2 - separation, transmutation and specific conditioning: isotopes to be separated (evolution of the radio-toxicity inventory of spent fuels, migration of long-living radionuclides, abatement of radio-toxicity), research on advanced separation (humid and dry way), research on transmutation of separate elements (transmutation and transmutation systems, realistic scenarios of Pu consumption and actinides transmutation, transmutation performances), research on materials (spallation targets, fuels and transmutation targets), research on conditioning matrices for separated elements; 3 - long-term storage: principles and problems, containers, surface and subsurface facilities; 4 - disposal: reversibility and disposal, geological disposal (principle and problems, site and concept selection), adaptation to reversibility, research on materials (bentonite and cements for geologic barrier, metals for containers), underground research and qualification laboratories, quantity of containers to be stored. (J.S.)

  8. Management of radioactive wastes

    When I first became concerned with radioactive waste management, in the early 1950's, very little was really known about the subject. There was a general feeling that it was a serious 'problem'. Articles were appearing in the press and talks were being given on the radio suggesting that the wastes generated by the proposed nuclear power reactors might be a serious menace to humanity. The prophets pointed with alarm to the enormous quantities of fission products that would accumulate steadily over the years in tank farms associated with reactor fuel reprocessing plants, and calculations were made of the possible results from rupture of the tanks due to corrosion, earthquakes or enemy attack. Responsible people suggested seriously that the waste disposal problem might be fatal to the development of a nuclear power industry, and this attitude was reinforced by the popular outcry that arose from experience with fallout from nuclear weapons testing. The Canadian nuclear power industry was not critically involved in this controversy because our heavy-water reactors are fuelled with natural uranium, and reprocessing of the fuel is not necessary. The spent fuel contains plutonium, a potential fuel, but the cost of recovering it was such that it was not competitive with natural uranium, which is not in short supply in Canada. Our spent fuel is not dissolved in acid - it is stored. still in its zirconium cladding, under water at the reactor site, or placed in sealed concrete-and-steel pipes below ground. If the price of uranium rises sufficiently it will become profitable to recover the plutonium, and only then shall we have an appreciable amount of waste from this source. However. during the first five or six years of research and development at Chalk River we did investigate fuel processing methods, and like everybody else we grad stainless steel tanks containing high and medium level wastes. These were located quite close to the Ottawa River, and we worried about what

  9. Radioactive waste disposal

    A deep gap, reflecting a persisting fear, separates the viewpoints of the experts and that of the public on the issue of the disposal of nuclear WASTES. The history of this field is that of the proliferation with time of spokesmen who pretend to speak in the name of the both humans and non humans involved. Three periods can be distinguished: 1940-1970, an era of contestation and confusion when the experts alone represents the interest of all; 1970-1990, an era of contestation and confusion when spokespersons multiply themselves, generating the controversy and the slowing down of most technological projects; 1990-, an era of negotiation, when viewpoints, both technical and non technical, tend to get closer and, let us be optimistic, leading to the overcome of the crisis. We show that, despite major differences, the options and concepts developed by the different actors are base on two categories of resources, namely Nature and Society, and that the consensus is built up through their 'hydridation'. we show in this part that the perception of nuclear power and, in particular of the underground disposal of nuclear wastes, involves a very deep psychological substrate. Trying to change mentalities in the domain by purely scientific and technical arguments is thus in vain. The practically instinctive fear of radioactivity, far from being due only to lack of information (and education), as often postulated by scientists and engineers, is rooted in archetypical structures. These were, without doubt, reactivated in the 40 s by the traumatizing experience of the atomic bomb. In addition, anthropological-linked considerations allow us to conclude that he underground disposal of wastes is seen as a 'rape' and soiling of Mother Earth. This contributes to explaining, beyond any rationality, the refusal of this technical option by some persons. However, it would naturally be simplistic and counter-productive to limit all controversy in this domain to these psychological aspects

  10. Radioactive wastes vitrification

    Borosilicate glass is capable to solidify the liquid wastes and to confine the radionuclides present in fission product solutions, not by coating, but thanks to the existence of chemical bonds with the glass oxides. Glass materials have a large chemical flexibility in comparison with crystal structures. In parallel to the studies of nuclear glass formulation, a continuous vitrification process has been developed in France which allows to generate glass in a highly radioactive environment. The first demonstration of the feasibility of this process was done at Marcoule in 1969 with the vitrification pilot system PIVER. The industrial vitrification facility of Marcoule started in 1978 for the confinement of spent fuel reprocessing wastes. This process was implemented at the R7 and T7 facilities of La Hague in 1989 and 1992, respectively. The process used today at La Hague comprises two steps: a calcination of fission products liquid solutions at 400 deg. C and a melting at 1100 deg. C in a crucible heated by magnetic induction. The molten mixture of glass and fission products is cast and solidified in 400 kg containers. Other vitrification processes have been developed like the cold crucible vitrification process and the vitrification in electrode heated ceramic melter. This article presents: 1 - the formulation of nuclear glasses: constraints, choice of vitreous systems, chemical reactivity between the waste and the vitrification catalyst, some basic properties of nuclear glasses, confining properties, perspectives of evolution of glass compositions; 2 - vitrification processes: vitrification with induction-heated metal crucible, with cold crucible, with electrode-heated ceramic melters; 3 - conclusion. (J.S.)

  11. Final disposal of radioactive waste

    Freiesleben H.


    Full Text Available In this paper the origin and properties of radioactive waste as well as its classification scheme (low-level waste – LLW, intermediate-level waste – ILW, high-level waste – HLW are presented. The various options for conditioning of waste of different levels of radioactivity are reviewed. The composition, radiotoxicity and reprocessing of spent fuel and their effect on storage and options for final disposal are discussed. The current situation of final waste disposal in a selected number of countries is mentioned. Also, the role of the International Atomic Energy Agency with regard to the development and monitoring of international safety standards for both spent nuclear fuel and radioactive waste management is described.

  12. Method of solidifying radioactive waste

    Purpose: To obtain satisfactory plastic solidification products rapidly and more conveniently from radioactive wastes. Method: liquid wastes contain, in addition to sodium sulfate as the main ingredient, nitrates hindering the polymerizing curing reactions and various other unknown ingredients, while spent resins contain residual cationic exchange groups hindering the polymerizing reaction. Generally, as the acid value of unsaturated liquid polyester resins is lower, the number of terminal alkyd resins is small, formation of nitrates is reduced and the polymerizing curing reaction is taken place more smoothly. In view of the above, radioactive wastes obtained by dry powderization or dehydration of radioactive liquid wastes or spent resins are polymerized with unsaturated liquid polyester resins with the acid value of less than 13 to obtain plastic solidification. Thus, if the radioactive wastes contain a great amount of polymerization hindering material such as NaNO2, they can be solidified rapidly and conveniently with no requirement for pre-treatment. (Kamimura, Y.)

  13. Radioactive waste: show time? - 16309

    Time will render radioactive waste harmless. How can we manage the time radioactive substances remain harmful? Just 'wait and see' or 'marking time' is not an option. We need to isolate the waste from our living environment and control it as long as necessary. For the situation in the Netherlands, it is obvious that a period of long term storage is needed. Both the small volume of waste and the limited financial possibilities are determining factors. Time is needed to let the volume of waste grow and to let the money, needed for disposal, grow in a capital growth fund. An organisation such as COVRA - the radioactive waste organisation in the Netherlands - can only function when it has good, open and transparent relationship with the public and particularly with the local population. If we tell people that we safely store radioactive waste for 100 years, they often ask: 'That long?' How can we explain the long-term aspect of radioactive waste management in a way people can relate to? In this paper, an overview is given of the activities of COVRA on the communication of radioactive waste management. (authors)

  14. Method and techniques of radioactive waste treatment

    This study illustrates the characterization of radioactive wastes produced by the application of radioisotopes in industry and research. The treatment methods of such radioactive wastes, chemical co-precipitation and ion exchange depending on the technical state of radioactive waste management facility in Syria were described. The disposal of conditioned radioactive wastes, in a safe way, has been discussed including the disposal of the radioactive sources. The characterizations of the repository to stock conditioned radioactive wastes were mentioned. (author)

  15. Management of radioactive waste: A review

    Luis Paulo Sant'ana; Taynara Cristina Cordeiro


    The issue of disposal of radioactive waste around the world is not solved by now and the principal reason is the lack of an efficient technologic system. The fact that radioactive waste decays of radioactivity with time are the main reasons for setting nuclear or radioactive waste apart from the other common hazardous wastes management. Radioactive waste can be classified according to the state of matter and level of radioactivity and this classification can be differently interpreted from co...

  16. Radioactive waste programme in Latvia

    An overview is made on the use of radioactive sources and waste management in Latvia. Brief overview of the development of national legal documents - the framework law of environmental protection; international agreements; the new law on radiation safety and nuclear safety; regulation of the Cabinet of Ministers - is given. The regulatory infrastructure in the nearest future is outlined. The institutional framework for radioactive waste management is described. Basic design of the repository and radioactive waste inventory are also given. The activities on the EU DG Environment project CASIOPEE are reported

  17. Low level radioactive waste management

    This talk is an overview of the problem of radioactive waste management in general as a step in dealing with the issues it presents to emergency preparedness. Major topics covered include the following: types of radioactive waste; Low-level radioactive waste including an overview of regulations and the problems/possibilities of developing disposal sites; Barriers to LLRW disposal site development including technical issues, not in my backyard, not in my term of office, and legal issues; impacts created by lack of disposal; and possible solutions

  18. Krsko NPP radioactive waste characteristics

    In May 2005 Krsko NPP initiated the Radioactive Waste Characterization Project and commissioned its realization to the consulting company Enconet International, Zagreb. The Agency for Radwaste Management was invited to participate on the Project. The Project was successfully closed out in August 2006. The main Project goal consisted of systematization the existing and gathering the missing radiological, chemical, physical, mechanical, thermal and biological information and data on radioactive waste. In a general perspective, the Project may also be considered as a part of broader scope of activities to support state efforts to find a disposal solution for radioactive waste in Slovenia. The operational low and intermediate level radioactive waste has been structured into 6 waste streams that contain evaporator concentrates and tank sludges, spent ion resins, spent filters, compressible and non-compressible waste as well as specific waste. For each of mentioned waste streams, process schemes have been developed including raw waste, treatment and conditioning technologies, waste forms, containers and waste packages. In the paper the main results of the Characterization Project will be briefly described. The results will indicate that there are 17 different types of raw waste that have been processed by applying 9 treatment/conditioning technologies. By this way 18 different waste forms have been produced and stored into 3 types of containers. Within each type of container several combinations should be distinguished. Considering all of this, there are 34 different types of waste packages altogether that are currently stored in the Solid Radwaste Storage Facility at the Krsko NPP site. Because of these findings a new identification system has been recommended and consequently the improvement of the existing database on radioactive waste has been proposed. The potential areas of further in depth characterization are indicated. In the paper a brief description on the

  19. Radioactive Waste Management Objectives

    considered and the specific goals to be achieved at different stages of implementation, all of which are consistent with the Basic Principles. The four Objectives publications include Nuclear General Objectives, Nuclear Power Objectives, Nuclear Fuel Cycle Objectives, and Radioactive Waste Management and Decommissioning Objectives. This publication sets out the objectives that need to be achieved in the area of radioactive waste management, including decommissioning and environmental remediation, to ensure that the Nuclear Energy Basic Principles are satisfied.

  20. Radioactive waste management in Tanzania

    Radioactive waste, like many other hazardous wastes, is of great concern in Tanzania because of its undesirable health effects. The stochastic effects due to prolonged exposure to ionizing radiation produce cancer and hereditary effects. The deterministic effects due to higher doses cause vomiting, skin reddening, leukemia, and death to exposed victims. The aim of this paper is to give an overview of the status of radioactive wastes in Tanzania, how they are generated and managed to protect humans and the environment. As Tanzania develops, it is bound to increase the use of ionizing radiation in research and teaching, industry, health and agriculture. Already there are more than 42 Centers which use one form of radioisotopes or another for these purposes: Teletherapy (Co-60), Brach-therapy (Cs-137, Sr-89), Nuclear Medicine (P-32, Tc-99m, 1-131, 1-125, Ga-67, In-111, Tl-206), Nuclear gauge (Am-241, Cs- 137, Sr-90, Kr-85), Industrial radiography (Am-241, C-137, Co-60, lr-92), Research and Teaching (1-125, Am241/Be, Co-60, Cs-137, H-3 etc). According to IAEA definition, these radioactive sources become radioactive waste if they meet the following criteria: if they have outlived their usefulness, if they have been abandoned, if they have been displaced without authorization, and if they contaminate other substances. Besides the origin of radioactive wastes, special emphasis will also be placed on the existing radiation regulations that guide disposal of radioactive waste, and the radioactive infrastructure Tanzania needs for ultimate radioactive waste management. Specific examples of incidences (theft, loss, abandonment and illegal possession) of radioactive waste that could have led to serious deterministic radiation effects to humans will also be presented. (author)

  1. Radioactive liquid waste processing device

    The present invention provides a device for processing radioactive liquid wastes generated in a facility of a nuclear power plant, especially suitable to liquid wastes at relatively high electroconductivity and solid content concentration. Namely, the device comprises a vessel for receiving radioactive liquid wastes, a device for concentrating the radioactive liquid wastes and a device for solidifying the liquid wastes. The concentrated liquid wastes can be charged from the concentration device to the receiving container. The concentration device has a precipitation separation function and comprises a supernatant withdrawing section and a solid content withdrawing section. In addition, the concentration device is connected with the receiving device for transferring the supernatant in the concentration device. Further, the receiving device is connected to the solidification device by way of a solid content transferring line, and the precipitated and separated solid content is transferred to a cement solidification device, plastic solidification device, asphalt solidification device, a glass solidification device etc. (I.S.)

  2. Treatment of Radioactive Gaseous Waste

    Radioactive waste, with widely varying characteristics, is generated from the operation and maintenance of nuclear power plants, nuclear fuel cycle facilities, research laboratories and medical facilities. The waste needs to be treated and conditioned as necessary to provide waste forms acceptable for safe storage and disposal. Although radioactive gaseous radioactive waste does not constitute the main waste flow stream at nuclear fuel cycle and radioactive waste processing facilities, it represents a major source for potential direct environmental impact. Effective control and management of gaseous waste in both normal and accidental conditions is therefore one of the main issues of nuclear fuel cycle and waste processing facility design and operation. One of the duties of an operator is to take measures to avoid or to optimize the generation and management of radioactive waste to minimize the overall environmental impact. This includes ensuring that gaseous and liquid radioactive releases to the environment are within authorized limits, and that doses to the public and the effects on the environment are reduced to levels that are as low as reasonably achievable. Responsibilities of the regulatory body include the removal of radioactive materials within authorized practices from any further regulatory control — known as clearance — and the control of discharges — releases of gaseous radioactive material that originate from regulated nuclear facilities during normal operation to the environment within authorized limits. These issues, and others, are addressed in IAEA Safety Standards Series Nos RS-G-1.7, WS-G-2.3 and NS-G-3.2. Special systems should be designed and constructed to ensure proper isolation of areas within nuclear facilities that contain gaseous radioactive substances. Such systems consist of two basic subsystems. The first subsystem is for the supply of clean air to the facility, and the second subsystem is for the collection, cleanup and

  3. Leaching tests of cemented organic radioactive waste

    The use of radioisotopes in research, medical and industrial activities generates organic liquid radioactive wastes. At Centro de Desenvolvimento da Tecnologia Nuclear (CDTN) are produced organic liquid wastes from different sources, one of these are the solvent extraction activities, whose the waste volume is the largest one. Therefore a research was carried out to treat them. Several techniques to treat organic liquid radioactive wastes have been evaluated, among them incineration, oxidation processes, alkaline hydrolysis, distillation, absorption and cementation. Laboratory experiments were accomplished to establish the most adequate process in order to obtain qualified products for storage and disposal. Absorption followed by cementation was the procedure used in this study, i.e. absorbent substances were added to the organic liquid wastes before mixing with the cement. Initially were defined the absorbers, and evaluated the formulation in relation to the compressive strength of its products. Bentonite from different suppliers (B and G) and vermiculite in two granulometries (M - medium and F - small) were tested. In order to assess the product quality the specimens were submitted to the leaching test according the Standard ISO 6961 and its results were evaluated. Then they were compared with the values established by Standard CNEN NN 6.09 Acceptance criteria for waste products to be disposed, to verify if they meet the requirements for safely storage and disposal. Through this study the best formulations to treat the organic wastes were established. (author)

  4. Radioactive waste management in Austria

    Neubauer Josef


    At the Austrian Research Centers Seibersdorf, there are several facilities in stalled for treatment of waste of low and intermediate radioactivity level (radwaste). A separate company within Centers, Nuclear Engineering Seibersdorf, has been formed recently, acting as a centralized facility for treatment, conditioning and storing of such waste within the country. The relevant treatment technology is applied depending on the waste category. In total about 6900 m3 of solid waste of low and inte...

  5. From uranium to radioactive waste

    A brief outline is given of the fuel cycle of conventional thermal reactors explaining the role of the individual stages leading from the uranium enrichment stage to fuel elements reprocessing and radioactive waste disposal. (S.R.)

  6. Radioactive waste processing and disposal

    This compilation contains 4144 citations of foreign and domestic reports, journal articles, patents, conference proceedings, and books pertaining to radioactive waste processing and disposal. Five indexes are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number

  7. National radioactive waste management strategy

    This article briefs out the strategic management of radioactive wastes in Malaysia. The criteria and methods discussed are those promoted by UTN (Nuclear Energy Unit) which has been given the authority to carry out local research programs in nuclear energy

  8. NRI's research on radioactive wastes

    A survey is given (including 41 references) of work carried out at the Nuclear Research Institute. Discussed are sorption processes (a selective sorbent for 90Sr based on BaSO4, etc.), sorption on inorganic ion exchangers (heteropolyacid salts, ferrocyanides for 137Cs capture), on organic cation exchangers (separation of lanthanides), electrocoagulation. The process is described of vitrification of highly radioactive wastes, the arrest of emissions, the deposition of radioactive wastes and surface decontamination. (M.K.)

  9. Radioactive Waste Management in Romania

    In Romania, the radioactive waste results from nuclear industry and from the applications of the nuclear energy in research, medicine, industry and agriculture. The main producers of radioactive waste are: - Nuclear Power Plant - Unit 1 and 2 of Cernavoda NPP; - Nuclear Research Reactors - WWR-S IFIN-HH and TRIGA INR-Pitesti; - The Factory for production of nuclear fuel, FCN-Pitesti; - Mining facilities and uranium processing facilities - The Uranium National Company; - Hospitals using radioisotopes in medical applications (radiology, oncology); - Classical industry, as a consequence of the industrial applications (the use of radioactive, sources in weld testing, leak detection, wall thickness measurements, etc). According to the Romanian legislation in force, the licensees producing radioactive waste are responsible for the safe management of the radioactive waste up to the moment of disposal. National Agency Radioactive Waste ANDRAD was created on the basis of Governmental Ordinance No.11/2003 on the 28th of August 2004. ANDRAD is responsible for the disposal of the radioactive waste and the spent nuclear fuel. In order to achieve this objective ANDRAD has to develop a lot of activities, defined in the Governmental Ordinance No. 11/2003 modified and completed in 2007. The paper deals with the most important aspects of radioactive waste and spent nuclear fuel management and the ANDRAD responsibilities in this area. Last year by the Governmental Ordinance a task was approved regarding the management of nuclear waste produced in nuclear power stations. There are finalized safety studies for LILW final repository and licensing procedures are in progress. (authors)

  10. Progress on Radioactive Waste Treatment Facilities Construction


    In 2011, five projects were undertaken by radioactive waste projects management department, which are "Cold Commissioning of the Pilot Project on Radioactive Waste Retrieval and Conditioning (abbreviation 'Pilot Project')", "Radioactive Ventilation Project Construction (abbreviation 'Ventilation

  11. Radioactive wastes problem in Poland

    The localization of CSOP Near Surface Repository of radioactive wastes in Rozan (Poland) and description of storage facilities was presented. This place is systematically controlled (e.g. measurements of radioactive contamination of the surface air, ground water, soil, grass and cereals). Contamination by tritium near by storage facilities was observed

  12. Overview of radioactive waste management

    The question of what to do with radioactive wastes is discussed. The need to resolve this issue promptly is pointed out. Two significant events which have occurred during the Carter administration are discussed. An Interagency Review Group (IRG) on waste management was formed to formulate recommendations leading to the establishment of a National policy for managing radioactive wastes. The technical findings in the IRG report are listed. The author points out some issues not addressed by the report. President Carter issued a national policy statement on Radioactive Waste Management in February 1980. The most significant elements of this statement are summarized. The cancellation of the Waste Isolation Pilot Plant is currently meeting opposition in Congress. This and other items in the National Policy Statement are discussed

  13. Radioactive waste management in Romania

    In Romania, the radioactive waste results from nuclear industry and from the applications of the nuclear energy in research, medicine, industry and agriculture. The main producers of radioactive waste are: Nuclear Power Plant - Unit 1 and 2 of Cernavoda Nuclear Power Plant; Nuclear Research Reactors - VVRS IFIN-HH and TRIGA SCN-Pitesti; The Factory which produces nuclear fuel Nuclear Fuel Plant (FCN-Pitesti Mining facilities and uranium processing facilities - The Uranium National Company; Hospitals which use applications of the radioisotopes in medical field (radiology, oncology); Classical industry, as a consequence of the industrial applications (the use of radioactive, sources in weld testing, leak detection, wall thickness measurement, etc.). According to the Romanian legislation in force, the licensees who produce radioactive waste are responsible for the safe management of the radioactive waste up to the moment of disposal. National Agency Radioactive Waste ANDRAD was created on the basis of the Governmental Ordinance No.11/2003 on the 28. of August 2004. ANDRAD is responsible for the disposal of the radioactive waste and the spent nuclear fuel. In order to achieve this objective ANDRAD has to develop a lot of activities, defined in the Governmental Ordinance No. 11/2003 modified and completed in 2007. The paper deals with the most important aspects of radioactive waste and spent nuclear fuel management, the ANDRAD responsibilities in this area. The main nuclear waste management facilities the National Nuclear Waste Repository (DNDR) Baita, the nuclear waste storage, treatment and conditioning plants are presented. The Low and Intermediate Level Waste (LILW) storage facility (DIDR) and spent fuel storage (DICA) are presented, also. ANDRAD is responsible for the future LILW DFDSMA which is to be built at Saligny, near Cernavoda NPP site and future High Level Waste (HLW) and spent fuel repository (DFCA). This year was approved by the Governmental Ordinance the

  14. Characterization of a ceramic waste form encapsulating radioactive electrorefiner salt

    Moschetti, T. L.; Sinkler, W.; DiSanto, T.; Noy, M.; Warren, A. R.; Cummings, D. G.; Johnson, S. G.; Goff, K. M.; Bateman, K. J.; Frank, S. M.


    Argonne National Laboratory has developed a ceramic waste form to immobilize radioactive waste salt produced during the electrometallurgical treatment of spent fuel. This study presents the first results from electron microscopy and durability testing of a ceramic waste form produced from that radioactive electrorefiner salt. The waste form consists of two primary phases: sodalite and glass. The sodalite phase appears to incorporate most of the alkali and alkaline earth fission products. Other fission products (rare earths and yttrium) tend to form a separate phase and are frequently associated with the actinides, which form mixed oxides. Seven-day leach test results are also presented.

  15. Characterization of radioactive hazardous waste

    The characterization of radioactive hazardous waste, also known as transuranic 'mixed waste' has to be completed before it can be classified for proper treatment (incinerator, mechanical compaction or thermal treatment), packing, and transport. The characterization of the TRU mixed waste is not only complex process but rather an expensive undertaking. The process knowledge is the basic foundation of characterization. It is the documented knowledge of processes and materials that generated the waste. The transuranic waste Quality Assurance Program Plan (QAPP) defines the Data Quality Objectives (DQO's) and provides the scope of analytical parameters and methods required to accurately characterize the radioactive mixed waste. Based on the historical data and process knowledge a sampling and analysis plan can be developed to characterize the radioactive hazardous waste. Based on the characterization, an assessment of the regulatory status can be made before the waste could be accepted for disposal at the WIPP facility. The Waste Acceptance Criteria (WAC) developed by WIPP defines the parameters for receiving and final disposal of the TRU waste. The sets of criteria, such as: heat generated, fissile gram equivalent (FGE), plutonium-equivalent (PE) curies, and specifications of a dose rate have to be met before the waste is accepted for deep geological disposal. The characterization of radioactive waste becomes even more complex due to the presence of iron base metals/alloys, aluminum base metals/alloys, organic, chelating agents that are mixed with plastic, rubber, cellulose, soils and cement. Some of the modern characterization technologies that are under development and currently used for TRU mixed wastes are: nondestructive examination, nondestructive assay, headspace gas analysis, and drum coring for Resources Conservation Recovery Act (RCRA) sampling. (author)

  16. Radioactive waste management in Canada

    This bibliography is an up-date to AECL-6186(Rev 3), 1952-1982, 'Radioactive Waste Management in Canada AECL Publications and Other Literature' compiled by Dianne Wallace. Canadian publications from outside contractors concerning the Canadian Nuclear Fuel Waste Management Program are included in addition to Atomic Energy of Canada Limited reports and papers. 252 refs

  17. Decontamination method for radioactive waste

    Metallic radioactive wastes are immersed in a liquid nitrogen vessel above a freezing crusher and they are frozen to about -196degC. Then, impact shocks are applied to crush the radioactive wastes frozen by a rotary shearing shock crusher disposed below the freezing crusher. The thus obtained crushed materials are sent to a decontamination device and decontaminated. In this case, since the objective materials are crushed, any of a blast decontamination method, an electrolytic polishing decontamination method, a redox decontamination method and a chemical agent immersion decontamination method can be applied. Thereafter, the dose of remaining radioactivity of the decontaminated crushed materials is measured. With such procedures, the decontamination and the subsequent measurement for the radiation contamination dose can easily and certainly be conducted for metallic radioactive wastes such as pipes of a small diameter and complicated structures. (I.N.)

  18. Environmental aspects of commercial radioactive waste management

    Volume 2 contains chapters 6 through 10: environmental effects related to radioactive waste management associated with LWR fuel reprocessing - mixed-oxide fuel fabrication plant; environmental effects related to transporting radioactive wastes associated with LWR fuel reprocessing and fabrication; environmental effects related to radioactive waste management associated with LWR fuel reprocessing - retrievable waste storage facility; environmental effects related to geologic isolation of LWR fuel reprocessing wastes; and integrated systems for commercial radioactive waste management

  19. Environmental aspects of commercial radioactive waste management


    Volume 2 contains chapters 6 through 10: environmental effects related to radioactive waste management associated with LWR fuel reprocessing - mixed-oxide fuel fabrication plant; environmental effects related to transporting radioactive wastes associated with LWR fuel reprocessing and fabrication; environmental effects related to radioactive waste management associated with LWR fuel reprocessing - retrievable waste storage facility; environmental effects related to geologic isolation of LWR fuel reprocessing wastes; and integrated systems for commercial radioactive waste management. (LK)

  20. Radioactive waste shredding: Preliminary evaluation

    The critical constraints for sizing solid radioactive and mixed wastes for subsequent thermal treatment were identified via a literature review and a survey of shredding equipment vendors. The types and amounts of DOE radioactive wastes that will require treatment to reduce the waste volume, destroy hazardous organics, or immobilize radionuclides and/or hazardous metals were considered. The preliminary steps of waste receipt, inspection, and separation were included because many potential waste treatment technologies have limits on feedstream chemical content, physical composition, and particle size. Most treatment processes and shredding operations require at least some degree of feed material characterization. Preliminary cost estimates show that pretreatment costs per unit of waste can be high and can vary significantly, depending on the processing rate and desired output particle size

  1. Hydrothermal alkaline stability of bentonite barrier by concrete interstitial wastes

    At present, the main source of High Level radioactive Waste (HLW) is the electrical energy production during all the steps of developing. In almost all the countries with nuclear programs, the option for the final management of HLW is the Deep Geological Repository (DGR) based on the concept of multi barrier. According to this concept, the waste is isolated from biosphere by the interposition of confinement barriers. Two of the engineering barriers in the Spanish design of DGR in granitic rock are compacted bentonite and concrete. The bentonite barrier is the backfilling and sealing material for the repository gallery, because of its mechanical and physico-chemical properties. The main qualities of concrete as a component of a multi barrier system are its low permeability, mechanical resistance and chemical properties. With regard to chemical composition of concrete, the alkaline nature of cement pore water lowers the solubility of many radioactive elements. However, structural transformation in smectite, dissolution or precipitation of minerals and, consequently, changes in the bentonite properties could occurs in the alkaline conditions generated by the cement degradation. The main objective of the present work is to evaluate the effect of concrete in the stability of Spanish reference bentonite (La Serrata of Nijar, Almeria, Spain) in conditions similar to those estimated in a DGR in granitic rock. Because of the main role of bentonite barrier in the global performance of the repository, the present study is essential to guarantee its security. (Author)

  2. Optimisation and adoption of slag based cement for conditioning of intermediate level alkaline radioactive liquid waste in CLEAR-V campaign

    The ILW is normally treated by resorcinol formaldehyde special type of resin. Another method for management of ILW is by conditioning in cement matrix. Various waste to cement ratios have been tried at lab and plant scale by taking slag based cement and ordinary portland cement. The cement waste products were evaluated for various properties. The final selected waste to cement ratio has been successfully adopted on the plant scale for conditioning of 140 m3 of ILW at SWMF. (author)

  3. Plastic solidification of radioactive wastes

    Over 20 years have elapsed after the start of nuclear power development, and the nuclear power generation in Japan now exceeds the level of 10,000 MW. In order to meet the energy demands, the problem of the treatment and disposal of radioactive wastes produced in nuclear power stations must be solved. The purpose of the plastic solidification of such wastes is to immobilize the contained radionuclides, same as other solidification methods, to provide the first barrier against their move into the environment. The following matters are described: the nuclear power generation in Japan, the radioactive wastes from LWR plants, the position of plastic solidification, the status of plastic solidification in overseas countries and in Japan, the solidification process for radioactive wastes with polyethylene, and the properties of solidified products, and the leachability of radionuclides in asphalt solids. (J.P.N.)

  4. Research programme on radioactive wastes

    This report for the Swiss Federal Department of the Environment, Transport, Energy and Communication (DETEC) takes a look at work done within the framework of the research programme on radioactive wastes. The paper discusses the development of various projects and the associated organisations involved. Both long-term and short-term topics are examined. The long-term aspects of handling radioactive wastes include organisation and financing as well as the preservation of know-how and concepts for marking the repositories. Communication with the general public on the matter is looked at along with public perception, opinion-making and acceptance. Waste storage concepts are looked at in detail and aspects such as environmental protection, monitoring concepts, retrievability and encasement materials are discussed. Finally, ethical and legal aspects of radioactive waste repositories are examined. The paper is completed with appendixes dealing with planning, co-ordination and the responsibilities involved

  5. Radioactive waste management in Slovenia

    The problem of radioactive waste management is both scientifically and technically complex and also deeply emotional issue. In the last twenty years the first two aspects have been mostly resolved up to the point of safe implementation. In the Republic of Slovenia, certain fundamentalist approaches in politics and the use of radioactive waste problem as political marketing tool, make things even more complex. Public involvement in planning and development of radioactive waste management program must be perceived as essential for the success of the program. Education is a precursor to public comprehension and confidence which lead to adequate waste management decisions that will protect the public health, safety and environment without jeopardizing further progress and development. (author)

  6. Underground radioactive waste disposal concept

    The paper presents some solutions for radioactive waste disposal. An underground disposal of radioactive waste is proposed in deep boreholes of greater diameter, fitted with containers. In northern part of Croatia, the geological data are available on numerous boreholes. The boreholes were drilled during investigations and prospecting of petroleum and gas fields. The available data may prove useful in defining safe deep layers suitable for waste repositories. The paper describes a Russian disposal design, execution and verification procedure. The aim of the paper is to discuss some earlier proposed solutions, and present a solution that has not yet been considered - lowering of containers with high level radioactive waste (HLW) to at least 500 m under the ground surface.(author)

  7. Standardization of radioactive waste categories

    A large amount of information about most aspects of radioactive waste management has been accumulated and made available to interested nations in recent years. The efficiency of this service has been somewhat hampered because the terminology used to describe the different types of radioactive waste has varied from country to country and indeed from installation to installation within a given country. This publication is the outcome of a panel meeting on Standardization of Radioactive Waste Categories. It presents a simple standard to be used as a common language between people working in the field of waste management at nuclear installations. The purpose of the standard is only to act as a practical tool for increasing efficiency in communicating, collecting and assessing technical and economical information in the common interest of all nations and the developing countries in particular. 20 refs, 1 fig., 3 tabs

  8. Clays in radioactive waste disposal

    Delage, Pierre; CUI, Yu-Jun; Tang, Anh-Minh


    Clays and argillites are considered in some countries as possible host rocks for nuclear waste disposal at great depth. The use of compacted swelling clays as engineered barriers is also considered within the framework of the multi-barrier concept. In relation to these concepts, various research programs have been conducted to assess the thermo-hydro-mechanical properties of radioactive waste disposal at great depth. After introducing the concepts of waste isolation developed in Belgium, Fran...

  9. Management of radioactive waste: A review

    Luis Paulo Sant'ana


    Full Text Available The issue of disposal of radioactive waste around the world is not solved by now and the principal reason is the lack of an efficient technologic system. The fact that radioactive waste decays of radioactivity with time are the main reasons for setting nuclear or radioactive waste apart from the other common hazardous wastes management. Radioactive waste can be classified according to the state of matter and level of radioactivity and this classification can be differently interpreted from country to country. Furthermore, microbiological procedures, plasma vitrification process, chemical precipitation, ion exchange, evaporation and reverse osmosis are strategies used for the treatment of radioactive wastes. The major challenge is to manage these radioactive substances after being used and discharged. This report brings data from the literature published worldwide from 2009 to 2014 on radioactive waste management studies and it covers production, classification and management of radioactive solid, liquid and gas waste.

  10. Radioactive liquid waste processing system

    The present invention provides a system for processing radioactive liquid wastes containing laundry liquid wastes, shower drains or radioactive liquid wastes containing chemical oxygen demand (COD) ingredients and oil content generated from a nuclear power plant. Namely, a collecting tank collects radioactive liquid wastes. A filtering device is connected to the exit of the collective tank. A sump tank is connected to the exit of the filtering device. A powdery active carbon supplying device is connected to the collecting tank. A chemical fluid tank is connected to the collecting tank and the filtering device by way of chemical fluid injection lines. Backwarding pipelines connect a filtered water flowing exit of the filtering device and the collecting tank. The chemical solution is stored in the chemical solution tank. Then, radioactive materials in radioactive liquid wastes generated from a nuclear power plant are removed by the filtering device. The water quality standard specified in environmental influence reports can be satisfied. In the filtering device, when the filtering flow rate is reduced, the chemical fluid is supplied from the chemical fluid tank to the filtering device to recover the filtering flow rate. (I.S.)

  11. Disposal of radioactive waste material

    Radioactive waste is disposed below ground at a position adjacent the coast line such that, 1. drainage of any water which has flowed through the disposal volume can be drained to the sea, or 2. the waste is disposed below the foreshore or coastal shallow water. Disposal facilities are described which advantageously include surrounding the waste with absorber to increase protection against migration of radionuclides. An example of a radioactive waste disposal facility is shown and includes a number of cells formed from concrete walls and floors, the cells being loaded successively with drums containing the waste, each cell being roofed with concrete after filling, there being absorber placed beneath the floors between the walls and after complete filling, above the said roof, with a soil mound surmounting. Drainage channels extend to sea via monitoring means. (author)

  12. Radioactive waste gas processing systems

    Purpose: To effectively separate and remove only hydrogen from hydrogen gas-containing radioactive waste gases produced from nuclear power plants without using large scaled facilities. Constitution: From hydrogen gas-enriched waste gases which contain radioactive rare gases (Kr, Xe) sent from the volume control tank of a chemical volume control system, only the hydrogen is separated in a hydrogen separator using palladium alloy membrane and rare gases are concentrated, volume-decreased and then stored. In this case, an activated carbon adsorption device is connected at its inlet to the radioactive gas outlet of the hydrogen separator and opened at its outlet to external atmosphere. In this system, while only the hydrogen gas permeates through the palladium alloy membrane, other gases are introduced, without permeation, into the activated carbon adsorption device. Then, the radioactive rare gases are decayed by the adsorption on the activated carbon and then released to the external atmosphere. (Furukawa, Y.)

  13. Radioactive waste processing by incineration

    Since 1986, low-level combustible radioactive waste has in Czechoslovakia been burnt in an experimental facility of a capacity of 40 kg/h. A modified two-stage SPG02 furnace is installed as the incinerator. It is a fixed-grate furnace with mechanical removal of solid residues. Propane-butane is used as the fuel. A 100 kg/h incinerator has been designed using the experience gained with the above type. The new prototype incinerator has two chambers and its operation is based on pyrolysis: radioactive waste is distilled at partial access of air, the evolving gas is then burnt thus obtaining a dry coke residue which will be fired in the furnace. Both chambers of the furnace are heated with one light fuel oil burner and one burner for contaminated oils and liquid radioactive wastes. The whole process is remote-controlled. (Z.M.). 6 figs., 3 refs

  14. Radioactive liquid waste processing device

    In a radioactive liquid waste processing device comprising a freeze-drying vessel for freezing and then vacuum drying acidic liquid wastes containing radioactive materials and a cold trap condensing steams evaporated in the freeze-drying vessel, a dust collecting electrode of an electric dust collector is disposed in the freeze-drying vessel for capturing fine solid particles and inorganic salts in steams. With such a constitution, upon sublimation of the water content contained in a freezing product of an acidic solution, since fine solid particles and inorganic salts entrained by steams are collected by the dust collecting electrode, radioactive materials entrained by recovered steams are almost eliminated, decontamination efficiency of the liquid waste processing device can be increased. Further, heat for the sublimation can be supplied to the solution-freezing product by a radiation heat caused by electric discharge of the dust collecting electrode, thereby enabling to eliminate the heater which was unnecessary so far. (T.M.)

  15. Public debate on radioactive wastes

    The definition and implementation of safe and perennial solutions for the management of radioactive wastes is a necessity from the point of view of both the nuclear industrialists and the public authorities, but also of the overall French citizens. For the low- or medium-level or short living radioactive wastes, some solutions have been defined are are already implemented. On the other hand, no decision has been taken so far for the long living medium to high-level radioactive wastes. Researches are in progress in this domain according to 3 ways of research defined by the law from December 30, 1991: separation-transmutation, disposal in deep underground, and long duration surface or sub-surface storage. This paper presents in a digest way, the principle, the results obtained so far, and the perspectives of each of the three solutions under study. (J.S.)

  16. Method of solidifying radioactive wastes

    Purpose: To prevent radioactive leaching and to attain excellent heat-dissipating and mechanical performances of radioactive wastes. Method: Solution or powder of radioactive wastes is dispersed, for example, into molten borosilicate glass or phosphate glass of about 70 to 30 % by weight per the dried oxides of the wastes and then molded into glass spheres of 2 - 50 mm in diameter. The surface of the glass solidified particles are made with electroconductive membranes by way of electroless plating, sputtering, vapor deposition, paste sintering or the like, thereafter, formed with membranes of metals such as copper, nickel, iron and silver by way of electroplating. The particles are sintered at a temperature between glass-softening point and metal-melting point. (Horiuchi, T.)

  17. Radioactive wastes, disposal sites wanted

    Two towns that were selected by the French government to home a disposal site for low-level radioactive wastes, have withdrawn their bid. ANDRA (French national agency for the management of radioactive wastes) attributes this withdrawal to the unbearable pressure made by the opponents on the city councils despite the public information meetings that were held in the 2 cities. The selection rules included the presence of clay layers with a thickness of at least 50 m, the absence of seismic activity and zones containing exploitable resources like petroleum or metal ores were barred in order to avoid future unexpected drilling. (A.C.)

  18. Radioactive waste disposal and constitution

    The radioactive waste disposal has many dimensions with regard to the constitutional law. The central problem is the corret delimitation between adequate governmental precautions against risks and or the permitted risk which the state can impose on the citizen, and the illegal danger which nobody has to accept. The solution requires to consider all aspects which are relevant to the constitutional law. Therefore, the following analysis deals not only with the constitutional risks and the risks of the nuclear energy, but also with the liberal, overall-economic, social, legal, and democratic aspects of radioactive waste disposal. (HSCH)

  19. Radioactive waste integrated management system

    In this paper, we present an integrated management system for radioactive waste, which can keep watch on the whole transporting process of each drum from nuclear power plant temporary storage house to radioactive waste storage house remotely. Our approach use RFID(Radio Frequency Identification) system, which can recognize the data information without touch, GSP system, which can calculate the current position precisely using the accurate time and distance measured from satellites, and the spread spectrum technology CDMA, which is widely used in the area of mobile communication

  20. Management of Radioactive Wastes in Developing Countries

    The management of radioactive wastes is one area of increasing interest especially in developing countries having more and more activities in the application of radioisotopes in medicine, research and industry. For a better understanding of radioactive waste management in developing countries this work will discuss the following items:Classification of countries with respect to waste management programs. Principal Radionuclides used in medicine, biological research and others and the range of radioactivity commonly used. Estimation of radioactive waste volumes and activities. Management of liquid wastes Collection. Treatment. Management of small volumes of organic liquid waste. Collection Treatment. Packaging and storage of radioactive wastes

  1. Solidifying method for radioactive waste

    Purpose: To obtain stable solidifying material capable of solidifying pellet-like radioactive waste intermediate storing products or miscellaneous solid wastes such of metals into uniform solidification products with no gaps. Method: In this method, radioactive wastes are solidified integrally by means of solidifying material comprising water-curable inorganic compound, aggregate, inorganic fluidizing material and reaction suppressing agent for suppressing the coagulating reaction between these materials. Aluminum lactate which is a basic metal salt is used as the reaction suppressing agent and lithium citrate is used together as an auxiliary agent for the reaction suppressing agent. Thus, particles constituting solidifying material are uniformly dispersed into added water and in a easily movable state. Accordingly, the solidifying material easily flows to the surface of wastes as the processing object upon packing the solidifying material, can easily fill the container for the package of solidification product with no gaps, to thereby from stable package for the solidification products. (Takahashi, M.)

  2. Recent approach in treatment of liquid radioactive waste: membrane methods

    have good stability with a contact of radioactive solutions and they can operate in full pH range. Easiness of washing with alkaline and acidic solutions allow long and stable membrane operation. The hybrid UF/complexation process allows the purification of the waste, as well as selective separation of some specific compounds present in the solution. Thermal process, namely membrane distillation (MD) with use of resistant, porous membranes manufactured from PTFE was proposed and tested for radioactive waste concentration. The results collected in laboratory and in pilot plant experiments allowed to consider the process usable for small installations operated with utilization of cheap energy sources or waste heat. The method is characterized by high decontamination factors and big volume reduction. Distillate produced in one-stage process has a purity sufficient for safe discharge to the environment. The paper refers to the study on these membrane methods, giving the comparison with commonly used conventional methods of liquid radioactive waste processing. (author)

  3. Radioactive waste management in Albania

    The policy and strategy of radioactive waste management in Albania are described in the Ministers Council's Decree No. 83, 1971. According to this Decree the liquid waste are all contaminated liquids with concentrations 10-100 times higher than maximal permissible concentrations for ordinary water. The management of liquid waste is done through their collection in special tanks without any treatment and subsequent discharge to sewer. The principal radioisotopes in liquid waste are I-131 and Tc-99m. The solid waste are all materials, which contain of or are contaminated with radioisotopes up to levels greater than exempted quantities. The management of solid waste is done through its safe storage in the premises, where radioactive decay occurs, especially for short lived radionuclides. Last years, many spent radiation sources were gathered in the Institute of Nuclear Physics (INP) for conditioning and interim storage. For conditioning 200 litres standard drums with steel bars and concrete filling having a hole in the centre are used. Spent radiation sources were emplaced in the hole until the activity of 20 GBq has been reached. Interim storage of conditioned sources is carried out in the engineering facility near the INP with trenches of capacity 5 cubic meters each. Last year a national inventory of sealed radiation sources begin to compile. A national programme for radioactive waste management in the future has been developed, taking into account the future extension of production and use of radioisotopes and radiopharmaceuticals and the participation of Albania in the IAEA Interregional Model Project on Radioactive Waste Management. (author). 6 refs, 2 figs, 2 tabs

  4. Radioactive Waste management - v. 1

    The state of the art for each stage and activities correlated to the nuclear fuel cycle, describing the activities of main countries of the world in this area, is presented. In this volume, the principles which described the several sources of radioactive wastes from nuclear industry, the standardization of waste categories, the strategies adopted for treatment and disposal, the repository types and the practices and proposals of several countries in this field, are presented. (M.C.K.)

  5. Nuclear power and radioactive waste

    The gap between the relative perceptions in the area of nuclear waste is wide. The broad view of the industry is that the disposal of nuclear waste is not a serious technical problem, and that solutions are already available to provide safe disposal of all our waste. The broad view of those who oppose the industry is that radioactive waste is so unpleasant, and will remain lethal for so long, that no acceptable policy will ever be developed, and so production of such waste (except, oddly, the significant amounts arising from uses of radioactive materials in medicine, agriculture, industrial safety research, etc) should stop immediately. This booklet will not attempt to describe in great detail the technicalities of the United Kingdom nuclear industry's current approach to radioactive waste: such issues are described in detail in other publications, especially those by Nirex. It is our intention to outline some of the main issues involved, and to associate these issues with the divergence in perceptions of various parties. (author)

  6. Sorting method for radioactive waste

    This paper describes a method for detecting radioactive components in dry active waste, comprising the steps of: providing a substantially airtight housing, withdrawing air from the housing, reducing the waste to pieces of substantially uniform size, providing a first conveyor in the housing, the first conveyor having a receiving portion and a discharge portion, discharging the pieces of reduced waste onto the first conveyor, flattening the pieces of reduced waste, detecting radiation emanating from the pieces of reduced waste from a position closely overlying the first conveyor, after the pieces are flattened, removing from the first conveyor the pieces of reduced waste from which radioactive radiation above a determined level is detected, providing a second conveyor in the housing, the second conveyor having a receiving portion and a discharge portion, disposing the second conveyor so that its receiving portion is below and spaced from the discharge portion of the first conveyor, discharging the pieces of reduced waste from the discharge portion of the first conveyor so that they fall onto the receiving portion of the second conveyor; the space between the last named discharge portion and the last named receiving portion being sufficiently great so that the pieces of reduced waste are substantially overturned and dispersed as they fall to the last named receiving portion

  7. Indian programme on radioactive waste management

    P K Wattal


    The primary objective of radioactive waste management is protection of human health, environment and future generation. This article describes, briefly, the Indian programme on management of different radioactive wastes arising in the entire nuclear fuel cycle adhering to this objective.

  8. Chemical decontamination of radioactive waste

    Radioactive wastes are generated in a number of different kinds of facilities and arise in a wide range of concentrations of radioactive materials and in a variety of physical and chemical forms. There is also a variety of alternatives for treatment and conditioning of the wastes prior disposal. The importance of treatment of radioactive waste for protection of human and environment has long been recognized and considerable experience has gained in this field. Generally, the methods used for treatment of radioactive wastes can be classified into three type's biological, physical and chemical treatment this physical treatment it gives good result than biological treatment. Chemical treatment is fewer hazards and gives good result compared with biological and physical treatments. Chemical treatment is fewer hazards and gives good result compared with biological and physical treatments. In chemical treatment there are different procedures, solvent extraction, ion exchange, electro dialysis but solvent extraction is best one because high purity can be optioned on the other hand the disadvantage that it is expensive. Beside the solvent extraction technique one can be used is ion exchange which gives reasonable result, but requires pretreatment that to avoid in closing of column by colloidal and large species. Electro dialysis technique gives quite result but less than solvent extraction and ion exchange technique the advantage is a cheep.(Author)

  9. Method of separating useful radioactive nuclide in radioactive liquid waste

    Purpose: To separate useful radioactive nuclides from radioactive liquid wastes for reducing the amount of radioactive secondary wastes generated upon disposal of radioactive liquid wastes. Method: Nitric acid is added to radioactive liquid wastes containing radioactive metal ions, iron ions, nickel ion, chromium ions and oxidative tetravalent serium ions dissolved therein, to convert tetravalent serium ions into complex ions. The liquid wastes are circulated through an ion exchange resin column. This enables to efficiently recover tetravalent serium ions which are useful oxidative nuclides thereby enabling the reuse of serium. Further, since the oxidative nature of the radioactive liquid wastes is eliminated, there is no requirement of adding a reducing agent and it is possible for drying treatment and solidification processing such as plastic solidification. (Takahashi, M.)

  10. Specified radioactive waste final disposal act

    Radioactive wastes must be finally and safely disposed far from human activities. Disposal act is a long-range task and needs to be understood and accepted by public for site selection. This paper explains basic policy of Japanese Government for final disposal act of specified radioactive wastes, examination for site selection guidelines to promote residential understanding, general concept of multi-barrier system for isolating the specific radioactive wastes, and research and technical development for radioactive waste management. (S. Ohno)

  11. Radioactive waste management - a safe solution

    This booklet sets out current United Kingdom government policy regarding radioactive waste management and is aimed at reassuring members of the public concerned about the safety of radioactive wastes. The various disposal or, processing or storage options for low, intermediate and high-level radioactive wastes are explained and sites described, and the work of the Nuclear Industry Radioactive Waste Executive (NIREX) is outlined. (UK)

  12. Radioactive waste management. UK policy examined

    This book presents the papers given at a conference on radioactive waste management in the United Kingdom. Topics considered at the conference included the UK Radioactive Waste Inventory, radioactive waste management and disposal strategies in the European Community, radioactive waste disposal in the Federal Republic of Germany, environmental options for waste disposal and storage, marine disposal, public opinion, the reduction of BNFL discharges, planning aspects, the ALARA principle, air pollution from fossil-fuel power plants, United Kingdom government policy with regard to radioactive wastes, and the role of the media in the public over the UK nuclear industry

  13. Geomechanical problems in study of radioactive wastes disposal

    Methods for both low-intermediate level radioactive wastes disposal and high level radioactive waste disposal were introduced briefly. Geomechanical problems in radioactive wastes disposal were discussed. Some suggestions were proposed for the radioactive wastes disposal in China

  14. Radioactive waste disposal in Greece

    Radioactive waste is any material which contains or is contaminated by radionuclides and for which no use is foreseen. According to this definition, a large number of sources, solid, liquid and gaseous, within the Greek territory can be - and, actually, is - declared as waste. The types of such solid sources are presented. It is estimated that these solid sources represent above 90% of all disused sources in Greece. The medical sources of Co-60 and Cs-137 were used in Teletherapy units, while the Ra-226 ones are in the form of needles or tubes used in Brachytherapy. All the industrial sources had been used for measuring moisture, density, thickness, elementary composition, etc. The small sources used by research labs are mainly in the form of discs. The above sources had been imported a long time ago (even 3 decades ago), had been used, and then stored as useless inside the user's premises. Since 1990 all the users of radioactive sources are obliged to return them back to the suppliers when they are no longer in use. In fact, no source is imported unless there is a written declaration of acceptance by its producer. A project concerning the export of all disused sealed sources is in progress. For every source a certificate will be issued, proper container will be purchased and all the necessary documents will be prepared so that it can be transported for final disposal or reuse in a foreign repository facility. Apart from this 'old generated' waste, unsealed radionuclides have always been used in nuclear medicine producing waste. The above radionuclides are used either in vivo (injected or ingested by patients) or in vitro (labeling of blood and other cells). Both uses leave some radioactive waste inside the needles, the tubes, or other material. Since 1991, Greece has a well-established regulatory system for controlling waste from nuclear medicine labs, so that disposing such solid or liquid waste does no harm to the environment. A revision of these regulations has

  15. Maintaining knowledge of radioactive waste

    Full text: [Knowledge - 'awareness or familiarity gained by experience (of a person, fact or thing)... a person's range of information ... the sum of what is known ... true, justified belief; certain understanding, as opposed to opinion.' The Oxford Concise English Dictionary.] Organisations responsible for the safe and effective management of radioactive waste will be aware of the value of information characterising the waste and the need for its preservation. In the United Kingdom the principal legal instrument controlling nuclear site activities is the Nuclear Installations Act (1990), which requires certain licence conditions to be fulfilled. One of the 35 conditions of the nuclear site licence demands that operators ensure that adequate records are kept relating to, inter alia, 'the location of all radioactive material, including nuclear fuel and radioactive waste'. Through the application of this licence condition, the relevant nuclear regulator, Nuclear Installations Inspectorate (NII), requires licensees to make arrangements for recording and preserving all the information that may be required in the future to ensure the safe management of radioactive material and radioactive waste. The majority of operators responsible for the long-term management of radioactive waste will establish systems for preserving information. In order for the system to deliver real benefits, there must be absolute clarity concerning what information is to be preserved, the reasons why it must be preserved, how it is to be managed over the long-term and who is responsible for its management. However, the decisive characteristic of this information management system that could make the difference between preserved liability and valued asset is the ability to access and interpret the information now and in the future. On first inspection, this characteristic appears obvious but how often are these systems established with the primary objective of preserving information when it should

  16. Automatic radioactive waste recycling

    The production of a plutonium ingot by calcium reduction process at CEA/Valduc generates a residue called 'slag'. This article introduces the recycling unit which is dedicated to the treatment of slags. The aim is to separate and to recycle the plutonium trapped in this bulk on the one hand, and to generate a disposable waste from the slag on the other hand. After a general introduction of the facilities, some elements will be enlightened, particularly the dissolution step, the filtration and the drying equipment. Reflections upon technological constraints will be proposed, and the benefits of a fully automatic recycling unit of nuclear waste will also be stressed. (authors)

  17. Management of small quantities of radioactive waste

    The main objective of this publication is to provide practical guidance primarily to developing Member States on the predisposal management of small quantities of radioactive waste arising from hospitals, laboratories, industries, institutions, research reactors and research centres.The publication covers the management of liquid, solid and gaseous radioactive wastes at the users' premises and gives general guidance on procedures at a centralized waste management facility. Predisposal management of radioactive waste includes handling, treatment, conditioning, storage and transportation. This publication provides information and guidance on the following topics: national waste management framework; origin and characteristics of radioactive waste arising from users generating small quantities of waste; radioactive waste management concepts appropriate for small quantities; local waste management; the documentation and approval necessary for the consignment of waste to a centralized waste management facility; centralized waste management; exemption of radionuclides from the regulatory body; transportation; environmental monitoring; quality assurance for the whole predisposal process; regional co-operation aspects

  18. Radioactive waste management: Spanish experiences

    Radioactive waste generation began in Spain during the 1950's, in association with the first applications of radioactive isotopes in industry, medicine and research. Spain's first nuclear power plant began its operations in 1968. At present, there are in operation some one thousand installations possessing the administrative authorization required to use radioactive isotopes (small producers), nine nuclear groups and a tenth is now entering the dismantling phase. There are also activities and installations pertaining to the front end of the nuclear fuel cycle (mining, milling and the manufacturing of fuel elements). Until 1985, the research center Junta de Energia Nuclear (now CIEMAT) rendered radioactive waste removal, and subsequent conditioning and temporary storage services to the small producers. Since the beginning of their operations the nuclear power plants and fuel cycle facilities have had the capacity to condition and temporarily store their own radioactive wastes. ENRESA (Empresa Nacional de Residuos Radiactivos, S. A.) began its operations in the second half of 1985. It is a state-owned company created by the Government in accordance with a previous parliamentary resolution and commissioned to establish a system for management of such wastes throughout Spain, being in charge also of the dismantling of nuclear power plants and other major installations at the end of their operating lifetimes. Possibly the most outstanding characteristic of ENRESA's evolution over these last seven years has been the need to bring about a compromise between solving the most immediate and pressing day-to-day problems of operation (the first wastes were removed at the beginning of 1986) and establishing the basic organization, resources, technology and installations required for ENRESA to operate efficiently in the long term. (author)

  19. Management of radioactive waste

    The text comprises three sections, i.e. theological and moral aspects, scientific and technical aspects, and administrative and political aspects. The book informs on the scientific and legal situation concerning nuclear waste management and intends to give some kind of decision aid from a theological point of view. (PW)

  20. Public attitudes about radioactive wastes

    Public attitudes about radioactive waste are changeable. That is the author's conclusion from eight years of social science research which the author has directed on this topic. The fact that public attitudes about radioactive waste are changeable is well-known to the hands-on practitioners who have opportunities to talk with the public and respond to their concerns--practitioners like Ginger King who is sharing the podium with me today. The public's changeability and open-mindedness are frequently overlooked in studies that focus narrowly on fear and dread. Such studies give the impression that the outlook for waste disposal solutions s dismal. The author believes that impression is misleading, and in this paper shares research findings that give a broader perspective

  1. Public attitudes about radioactive waste

    Public attitudes about radioactive waste are changeable. That is my conclusion from eight years of social science research which I have directed on this topic. The fact that public attitudes about radioactive waste are changeable is well-known to the hands-on practitioners who have opportunities to talk with the public and respond to their concerns-practitioners like Ginger King, who is sharing the podium with me today. The public's changeability and open-mindedness are frequently overlooked in studies that focus narrowly on fear and dread. Such studies give the impression that the outlook for waste disposal solutions is dismal. I believe that impression is misleading, and I'd like to share research findings with you today that give a broader perspective

  2. Radioactive waste examination pilot plant

    The Stored Waste Examination Pilot Plant (SWEPP) is a contact-handled radioactive waste examination pilot facility at the Department of Energy's Idaho National Engineering Laboratory. The plant determines through computerized nondestructive examination (NDE) whether transuranic waste now stored at the INEL qualifies for shipment to DOE's Waste Isolation Pilot Plant in New Mexico or whether it needs further processing. As a container proceeds through the plant it is weighed, x-rayed with real-time radiography to determine actual contents, assayed to determine fissile contents, ultrasonically examined to determine container integrity, and surveyed for surface radiation and contamination. Because the facility handles transuranic waste, proper information management is essential. A microprocessor-based data management system has been developed for this purpose; a key feature is its direct communication with the computerized NDE equipment and with a mainframe computer on which the data is stored permanently. 4 references, 2 figures

  3. Storage of Radioactive Waste. Safety Guide

    Radioactive waste is generated in a broad range of activities involving a wide variety of materials. The wastes arising from these activities have differing physical, chemical and radiological characteristics. This publication gives guidance on the storage of solid, liquid and gaseous radioactive wastes in a wide range of facilities, including those at which waste is generated, treated and conditioned. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Roles and responsibilities; 4. Common safety considerations for waste storage facilities; 5. Design and operation of small storage facilities for radioactive waste; 6. Design and operation of large storage facilities for radioactive waste; Appendix.

  4. Treatment and conditioning of historical radioactive waste

    The paper describes the management of historical radioactive waste from the storage facility of Radioactive Waste Treatment Plant. The historical waste stored into storage facility of IFIN-HH consists of spent sealed radioactive sources, empty contaminated containers, wooden radioactive waste, low specific activity radioactive waste, contaminated waste as well as radioactive waste from operation of WWR-S research reactor. After decommissioning of temporary storage facility about 5000 packages with radioactive waste were produced and transferred to the disposal facility. A large amount of packages have been transferred and disposed of to repository but at the end of 2000 there were still about 800 packages containing cement conditioned radioactive waste in an advanced state of degradation declared by authorities as 'historical waste'. During the management of historical waste campaign there were identified: radium spent radioactive sources, containers containing other spent sealed radioactive sources, packages containing low specific activity waste consist of thorium scrap allow, 30 larger packages (316 L), packages with activity lower than activity limit for disposal, packages with activity higher than activity limit for disposal. At the end of 2008, the whole amount of historical waste which met the waste acceptance criteria has been conditioned and transferred to disposal facility. (authors)

  5. Radioactive Waste Management BasisApril 2006

    Perkins, B K


    This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  6. Geologic disposal of radioactive waste

    The heat dissipation arising from the radioactive decay constitutes an important problem of the geological disposal of high level radioactive waste. A heating experiment was carried out in a clay quarry near Monterotondo (Rome), at 6.4 M in depth by means of a heater whose thermal power ranged from 250 to 500 watt. The experimental results fit well the theoretical values and show that the clay is a homogeneous and isotropic medium. The clay thermal conductivity, which was deducted by means of the ''curve fitting'' method, ranges from 0.015 to 0.017 watt/C

  7. Innocuous management of radioactive wastes

    The relations between peaceful uses and bellicose uses of the nuclear energy are complexes in relation to international establishment of norms to control the destiny of the radioactive materials, above all in the context of the existing international legislation of respect to the autonomy of the countries, and in the determination of the institution or institutions upon the ones that would fall on. The nuclear safeguards of materials and the possibilities of performing their function. Important efforts have been done to unify, to help and to impose international measures on the behalf of an environmentally harmless processing of the radioactive wastes

  8. Status of radioactive waste management in Zambia

    Zambia being part of the world community clearly understands that careless handling of radioactive waste would cause problems - worldwide - for human health, for the environment and natural resources management. It is for this reason that the Radiation Protection Board has initiated a Radioactive Waste Management Programme covering the following areas: (i) Legislation of Radioactive Waste Management; (ii) Immobilization of spent sealed radioactive sources; and (iii) Siting and construction of an interim storage facility. (author)

  9. Radioactive waste management at KANUPP

    This paper describes the existing radioactive waste management scheme of KANUPP. The radioactive wastes generated at KANUPP are in solid, liquid and gaseous forms. The spent fuel of the plant is stored underwater in the Spent Fuel Bay. For long term storage of low and intermediate level solid waste, 3m deep concrete lined trenches have been provided. The non-combustible material is directly stored in these trenches while the combustible material is first burnt in an incinerator and the ash is collected, sealed and also stored in the trenches. The low-level liquid and gaseous effluents are diluted and are discharged into the sea and the atmosphere. The paper also describes a modification carried out in the spent resin collection system in which a locally designed removable tank replaced the old permanent tanks. Presently the low level combustible solid waste is incinerated and stored, but it is planned to replace the present method by using compactor and storing the compacted waste in steel drums underground. (author)

  10. Radioactive waste and public acceptance

    Radioactive waste just happens to be the major issue in the public eye now--it could be replaced by another issue later. A survey is quoted to prove that wastes are not really one of the burning national issues of the day. The people opposing the nuclear program cannot be said to represent the public. The taste of the press for the melodramatic is pointed out. The issue needs to be presented with the proper perspective, in the context of the benefits and risks of nuclear power

  11. Radioactive waste management in Canada

    This bibliography is a review of the Canadian literature on radioactive waste management from 1953 to the present. It incorporates the references from the previous AECL--6186 revisions, and adds the current data and some of the references that had been omitted. Publications from outside organizations of concern to the Canadian Nuclear Fuel Waste Program are included in addition to AECL Research reports and papers. This report is intended as an aid in the preparation of the Concept Assessment Document and is complementary to AECL Research's internal document-ready references on the MASS-11 word processing systems

  12. Chemical treatment of radioactive wastes

    This is the third manual of three commissioned by the IAEA on the three principal techniques used in concentrating radioactive liquid wastes, namely chemical precipitation, evaporation and ion exchange. The present manual deals with chemical precipitation by coagulation-flocculation and sedimentation, commonly called ''chemical treatment'' of low-activity wastes. Topics discussed in the manual are: (i) principles of coagulation on flocculation and sedimentation and associated processes; (ii) process and equipment; (iii) conditioning and disposal of flocculation sludge; (iv) sampling and the equipment required for experiments; and (v) factors governing the selection of processes. 99 refs, 17 figs, 4 tabs

  13. Shallow disposal of radioactive waste

    A review and evaluation of computer codes capable of simulating the various processes that are instrumental in determining the dose rate to individuals resulting from the shallow disposal of radioactive waste was conducted. Possible pathways of contamination, as well as the mechanisms controlling radionuclide movement along these pathways have been identified. Potential transport pathways include the unsaturated and saturated ground water systems, surface water bodies, atmospheric transport and movement (and accumulation) in the food chain. Contributions to dose may occur as a result of ingestion of contaminated water and food, inhalation of contaminated air and immersion in contaminated air/water. Specific recommendations were developed regarding the selection and modification of a model to meet the needs associated with the prediction of dose rates to individuals as a consequence of shallow radioactive waste disposal. Specific technical requirements with regards to risk, sensitivity and uncertainty analyses have been addressed

  14. Radioactive lightning rods waste treatment

    Full text: In this paper, we present alternative processes that could be adopted for the management of radioactive waste that arises from the replacement of lightning rods with attached Americium-241 sources. Lightning protectors, with Americium-241 sources attached to the air terminals, were manufactured in Brazil until 1989, when the regulatory authority overthrew the license for fabrication, commerce, and installation of radioactive lightning rods. It is estimated that, during the license period, about 75,000 such devices were set up in public, commercial and industrial buildings, including houses and schools. However, the policy of CNEN in regard to the replacement of the installed radioactive rods, has been to leave the decision to municipal governments under local building regulations, requiring only that the replaced rods be sent immediately to one of its research institutes to be treated as radioactive waste. As a consequence, the program of replacement proceeds in a low pace and until now only about twenty thousand rods have reached the waste treatment facilities The process of management that was adopted is based primarily on the assumption that the Am-241 sources will be disposed of as radioactive sealed sources, probably in a deep borehole repository. The process can be described broadly by the following steps: a) Receive and put the lightning rods in initial storage; b) Disassemble the rods and pull out the sources; c) Decontaminate and release the metal parts to metal recycling; d) Store the sources in intermediate storage; e) Package the sources in final disposal packages; and f) Send the sources for final disposal. Up to now, the disassembled devices gave rise to about 90,000 sources which are kept in storage while the design of the final disposal package is in progress. (author)

  15. Classification of Radioactive Waste. General Safety Guide

    This publication is a revision of an earlier Safety Guide of the same title issued in 1994. It recommends revised waste management strategies that reflect changes in practices and approaches since then. It sets out a classification system for the management of waste prior to disposal and for disposal, driven by long term safety considerations. It includes a number of schemes for classifying radioactive waste that can be used to assist with planning overall national approaches to radioactive waste management and to assist with operational management at facilities. Contents: 1. Introduction; 2. The radioactive waste classification scheme; Appendix: The classification of radioactive waste; Annex I: Evolution of IAEA standards on radioactive waste classification; Annex II: Methods of classification; Annex III: Origin and types of radioactive waste

  16. Vitrification of hazardous and radioactive wastes

    Vitrification offers many attractive waste stabilization options. Versatility of waste compositions, as well as the inherent durability of a glass waste form, have made vitrification the treatment of choice for high-level radioactive wastes. Adapting the technology to other hazardous and radioactive waste streams will provide an environmentally acceptable solution to many of the waste challenges that face the public today. This document reviews various types and technologies involved in vitrification

  17. Public Education and Radioactive Waste

    Throughout the country the mention of anything nuclear or the word radiation ignites fear in the minds of many Americans. Political hype, news stories and the lack of basic understanding about nuclear power and radiation causes many people to reject what they do not understand. Often little, if any, thought may have been given to nearby nuclear weapons facilities where family members and neighbors were gainfully employed at these sites. As older nuclear facilities are closed being a result of the end of the Cold War, with indications that radioactive materials might be transported to other parts of the country, the public in expressing concern. It is important that the public have an understanding of how these materials are handled to insure public safety. It becomes important that both the companies handling these materials and the U.S. Department of Energy create an environment that will involve community participation in developing strategies that will promote and support an understanding of how radioactive wastes will be packaged, transported, and disposed. This is being performed in Oak Ridge, TN. through the efforts of the Oak Ridge Site Specific Advisory Board (ORSSAB). The ORSSAB is a DOE sponsored board of private citizens from all walks of life and professionalism's. The objective of this paper is to offer suggestions as to how public confidence, through education about nuclear, radioactive and associated and wastes are effectively handle the problems related to waste disposal, removal or on-site storage. It is essential that the public fully understand and become involved in the need for the reduction of the waste stream volumes and the technical problems being faced in reaching this goal. The effort of gaining public understanding and support of this important task cannot be limited to just those within close proximity to the facility presently housing these materials, but must extend to those outlying areas and along any potential route that might be

  18. Final storage of radioactive waste

    As explained in the present article, operators of nuclear power plants are responsible for the safe final disposal of the radioactive wastes they produce on the strength of the polluter pays principle. To shift the burden of responsibility for safe disposal to society as a whole would violate this principle and is therefore not possible. The polluter pays principle follows from more general principles of the fair distribution of benefits and burdens. Instances of its implementation are to be found in the national Atomic Energy Law as well as in the European Radioactive Waste and Spent Fuel Management Directive. The polluters in this case are in particular responsible for financing the installation and operation of final disposal sites. The reserves accumulated so far for the decommissioning and dismantling of nuclear power plants and disposal of radioactive wastes, including the installation and operation of final disposal sites, should be transferred to a public-law fund. This fund should be supplemented by the polluters to cover further foreseeable costs not covered by the reserves accumulated so far, including a realistic cost increase factor, appropriate risk reserves as well as the costs of the site selection procedure and a share in the costs for the safe closure of the final disposal sites of Morsleben and Asse II. This would merely be implementing in the sphere of atomic law that has long been standard practice in other areas of environmental law involving environmental hazards.

  19. Media analysis of radioactive wastes

    The radioactive waste cleanup community has not effectively utilized its most powerful communications tool to inform the general public; the print and broadcast media. Environmental interest groups have known of the value of accessing the media for their message for years and have used it effectively. The radioactive waste cleanup community's efforts to date have not been focused on education of the media so that they in turn can inform the public of our cleanup mission. Their focus must be to learn of the importance of the media, develop training programs that train technical people in how to know and respond to the media's needs for information, and then incorporate that training into a comprehensive program of public information in which access to the media is a key communications tool. This paper discusses how media education and access is a cost-effective means of accomplishing community relations goals of public information and public participation in radioactive waste cleanup and has been effectively utilized at the Weldon Spring Site Remedial Action Project

  20. Predisposal management of high level radioactive waste

    The objective of this safety guide is to provide guidance on predisposal management of high-level radioactive waste to meet the safety requirements spelt out in the safety code on 'management of radioactive waste'. This safety guide provides recommendations to the waste generator/manager at various stages in the predisposal management of high level radioactive waste for ensuring safety of the occupational workers, public and the environment

  1. Radioactive liquid waste processing method

    Radioactive liquid wastes containing radioactive materials and sodium compounds are dried into a dried material, and then, the dried material is heated to form molten salts, which is used as a anolyte. Electrolysis is conducted having a sodium ion conductive β-alumina as a diaphragm. When a molten material containing sodium hydroxide is used as a catholyte, electrolysis is conducted while supplying steams or steams and oxygen to the catholyte. Extremely low radioactive and highly pure (solid) metal sodium or sodium hydroxide can be formed on the side of the cathode by the electrolysis. The radioactive materials are gradually concentrated on the side of the anode along with the progress of the electrolysis. After the lapse of a predetermined time, the concentrated radioactive materials on the side of the anode is taken out from the device and treated into a harmless form by an optional means such as confinement with cement or the like. With such procedures, highly purified metal sodium or sodium hydroxide can be recovered at a high electric efficiency. (T.M.)

  2. Radioactive Waste and Clean-up Division

    The main objectives of the Radioactive Waste and Clean-up division of SCK-CEN are outlined. The division's programme consists of research, development and demonstration projects and aims to contribute to the objectives of Agenda 21 on sustainable development in the field of radioactive waste and rehabilitation of radioactively contaminated sites

  3. Filler for solidifying radioactive waste

    In an existent filler for solidifying radioactive wastes, fine powders generated upon pulverizing concrete waste materials and recovering coarse aggregates and fine aggregates are used as substitutes for a portion of cements and/or at least a portion of sands. Namely, the concrete waste materials are crushed by a crusher, and sieved to recover grains having a grain size of not less than 5mm as regenerated aggregate materials. Further, grains having a grain size of not more than 5mm are selectively collected as fine aggregate materials. Since a large quantity of fine powders and mortar are contained in the fine aggregate materials, they are cleaned by a recovering device. In this case, grains having a grain size of about 0.3mm are separately recovered as fine powders. Since the fine powders are porous and have good water retainability, fillers for radioactive wastes highly flowable and having excellent material-solidifying resistance can be obtained by using the fine powders. Further, they can also contribute with a view point of recycling of sources. (T.M.)

  4. Plastic or asphalt solidification product of radioactive wastes and production method therefor

    When radioactive wastes are water-containing liquids, such as condensed liquid wastes, an active silicic acid is added to the condensed liquid wastes under an alkaline condition before conducting plastic solidification or asphalt solidification. With such procedures, silanol groups are formed in the condensed liquid wastes, to which radioactive nuclides are adsorbed. If the condensed liquid wastes are solidified as they are dried and into powders of plastic or asphalt, the amount of radioactive nuclides leaked from the solidification products is extremely reduced. Further, when the radioactive wastes are solidification products not containing water, silanol groups are not formed and radioactive nuclides are not adsorbed. However, when the solidification products are subsequently brought into contact with water, silanol groups are formed rapidly at the surface of the solidification products being in contact with water, and ionized radioactive nuclides are adsorbed. With such procedures, the leakage of radioactive nuclides from the solidification products can be prevented. (T.M.)

  5. Solidification method for radioactive waste

    As a method for processing low level radioactive wastes, it has been known that they are solidified by using inorganic solidifying materials such as cement and water glass. In the present invention, it is considered that not only the low level wastes but also middle level wastes are solidified by cement or the like and then put to land disposal. Therefore, hydrophobic materials such as oils and silicon are coated in the solidification vessel, and solidification is conducted subsequently. With such procedures, even if water intrudes by some causes from the outside, since thin layers made of hydrophobic materials have a permanent water-repellent effect, the intrusion of water to the inside of the solidification material can be prevented as much as possible. Accordingly, integrity of the solidification materials can further be improved. (T.M.)

  6. Regional radioactive waste account and control system

    Regional structure of the state system of radioactive waste account and control for Moscow Region is suggested. Problems, information contacts, the role of the inter-regional information and analytical centre and approaches to ensure radioactive waste account in terms of the mentioned systems are discussed. Approach to control waste production based on the observance of the temporal storage standards and limits and on the time-appropriate disposal of radioactive waste is suggested. Algorithm of the efficient planning of radioactive waste disposal with regard to the observance of the radiation safety requirements is given

  7. Aspects of radioactive waste management research institutions

    In Brazil, data recovered from the last follow-up survey (2006) from researchers that hold authorization for handling radioactive materials shows that considerable quantities of radioactive waste from laboratories was not enough minimized. In the present paper, some measurements for reducing the impact of improper waste management are presented including the discussion of a comprehensive waste management program, named PROGER (in Portuguese, for Radioactive Waste Management Program for Research Institutions) implemented by CNEN for educating and advising the staff of research institutions, on how to develop their own radioactive waste management programs on a safe and technically sound manner.

  8. Radioactive waste management - an educational challenge

    University Radioactive Waste Management educational programs are being actively advanced by the educational support activities of the Offices of Civilian Radioactive Waste Management (OCRWM) and Environmental Restoration and Waste Management (ERWM) of the DOE. The DOE fellowship program formats of funding students and requiring a practical research experience (practicum) at a DOE site has helped to combine the academic process with a practical work experience. Support for faculty in these programs is augmenting the benefits of the fellowship programs. The many job opportunities and funding sources for students which currently exists in the radioactive waste management area are fueling an increase in academic programs seeking recognition of their radioactive waste management curriculums

  9. Cements in Radioactive Waste Disposal

    The use of cement and concrete to immobilise radioactive waste is complicated by the wide- ranging nature of inorganic cementing agents available as well as the range of service environments in which cement is used and the different functions expected of cement. For example, Portland cement based concretes are widely used as structural materials for construction of vaults and tunnels. These constructions may experience a long pre-closure performance lifetime during which they are required to protect against collapse and ingress of water: strength and impermeability are key desirable characteristics. On the other hand, cement and concrete may be used to form backfills, ranging in permeability. Permeable formulations allow gas readily to escape, while impermeable barriers retard radionuclide transport and reduce access of ground water to the waste. A key feature of cements is that, while fresh, they pass through a fluid phase and can be formed into any shape desired or used to infiltrate other materials thereby enclosing them into a sealed matrix. Thereafter, setting and hardening is automatic and irreversible. Where concrete is used to form structural elements, it is also natural to use cement in other applications as it minimises potential for materials incompatibility. Thus cement- mainly Portland cement- has been widely used as an encapsulant for storage, transport and as a radiation shield for active wastes. Also, to form and stabilise structures such as vaults and silos. Relative to other potential matrices, cement also has a chemical immobilisation potential, reacting with and binding with many radionuclides. The chemical potential of cements is essentially sacrificial, thus limiting their performance lifetime. However performance may also be required in the civil engineering sense, where strength is important, so many factors, including a geochemical description of service conditions, may require to be assessed in order to predict performance lifetime. The

  10. Law on the management of radioactive waste

    This law regulate the relations of legal persons, enterprises without the rights of legal persons, and natural persons in the management of radioactive waste in Lithuania and establish the legal grounds for the management of radioactive waste. Thirty one article of the law deals with the following subjects: principles of radioactive waste management, competence of the Government, State Nuclear Power Safety Inspectorate, Ministry of Economy, Ministry of Environment and Radiation Protection Center in the sphere of regulation of the radioactive waste management, activities subject to licensing, issue of licences and authorisations, duties and responsibilities of the waste producer, founding of the radioactive waste management agency, its basic status and principles of the activities, functions of the agency, management of the agency, transfer of the radioactive waste to the agency, assessment of the existing waste management facilities and their past practices, siting, design and construction, safety assessment, commissioning and operation of the radioactive waste management facilities, radiation protection, quality assurance, emergency preparedness, decommissioning of radioactive waste storage and other facilities, post-closure surveillance of the repository, disused sealed sources, transportation, export and transit of radioactive waste

  11. Thermal treatment of organic radioactive waste

    The organic radioactive waste which is generated in nuclear and isotope facilities (power plants, research centers and other) must be treated in order to achieve a waste form suitable for long term storage and disposal. Therefore the resulting waste treatment products should be stable under influence of temperature, time, radioactivity, chemical and biological activity. Another reason for the treatment of organic waste is the volume reduction with respect to the storage costs. For different kinds of waste, different treatment technologies have been developed and some are now used in industrial scale. The paper gives process descriptions for the treatment of solid organic radioactive waste of low beta/gamma activity and alpha-contaminated solid organic radioactive waste, and the pyrolysis of organic radioactive waste

  12. Instructive for radioactive solid waste management

    An instructive is established for the management system of radioactive solid residues waste of the Universidad de Costa Rica, ensuring the collection, segregation, storage and disposal of waste. The radioactive solid waste have been segregated and transferred according to features and provisions of the Universidad de Costa Rica and CICANUM

  13. Note from the Radioactive Waste Section

    TS Department


    The Radioactive Waste Section of the Radiation Protection Group wishes to announce that the radioactive waste treatment centre will be closed on Friday, 19 December. In addition, waste reception will be limited to a strict minimum on Thursday, 18 December. Users of the centre are requested to adjust their plans accordingly. For more information, call 73875.

  14. Process for fixation of radioactive waste

    Fixation of radioactive waste comprises mixing of the water saturated waste with a resin and a monomer in order to form an emulsion. By addition of a hydraulic binder, formation of concrete is achieved. This process enables the fixation of the waste in a stable manner without release of radioactivity

  15. Mixed radioactive and chemotoxic wastes (RMW)

    During the first decades of development of nuclear energy, organizations involved in the management of nuclear wastes had their attention focused essentially on radioactive components. The impression may have prevailed that, considering the severe restrictions on radioactive materials, the protection measured applied for radioactive components of wastes would be more than adequate to cope with potential hazards from non radioactive components associated with radioactive wastes. More recently it was acknowledged that such interpretation is not necessarily justified in all cases since certain radioactive wastes also contain non-negligible amounts of heavy metals or hazardous organic components which, either, do not decay, or are subject to completely different decay (decomposition) mechanisms. The main purposes of the present study are to analyze whether mixed radioactive wastes are likely to occur in Europe and in what form, whether one needs a basis for integration for evaluating various forms of toxicity and by which practical interventions possible problems can be avoided or at least reduced. (au)

  16. Operation of the radioactive waste treatment facility

    The radioactive wasted generated at Korea Atomic Energy Research Institute (KAERI) in 1996 are about 118m3 of liquid waste and 204 drums of solid waste. Liquid waste were treated by the evaporation process, the bituminization process, and the solar evaporation process. In 1996, 100.5m3 of liquid waste was treated. (author). 84 tabs., 103 figs

  17. Operation of the radioactive waste treatment facility

    Kim, Kil Jeong; Ahn, Seom Jin; Lee, Kang Moo; Lee, Young Hee; Sohn, Jong Sik; Bae, Sang Min; Kang, Kwon Ho; Lim, Kil Sung; Sohn, Young Joon; Kim, Tae Kook; Jeong, Kyung Hwan; Wi, Geum San; Park, Seung Chul; Park, Young Woong; Yoon, Bong Keun


    The radioactive wasted generated at Korea Atomic Energy Research Institute (KAERI) in 1996 are about 118m{sup 3} of liquid waste and 204 drums of solid waste. Liquid waste were treated by the evaporation process, the bituminization process, and the solar evaporation process. In 1996, 100.5m{sup 3} of liquid waste was treated. (author). 84 tabs., 103 figs.

  18. The Radioactive Waste Management at Studsvik

    The report was originally prepared as a contribution to the discussions in an IAEA panel on economics of radioactive waste management held in Vienna from 13 - 17 December 1965. It contains the answers and comments to the questions of a questionnaire for the panel concerning the various operations associated with the management (collection, transport, treatment, discharge, storage, and operational monitoring) of: - radioactive liquid wastes, except high-level effluents from reactor fuel recovering operations; - solid wastes, except those produced from treatment of high level wastes; - gaseous wastes produced from treatment of the foregoing liquid and solid wastes; - equipment decontamination facilities and radioactive laundries

  19. Radioactive waste packaging and transport in Argentina

    This article is aimed at summarising the activities related to the transport of radioactive materials carried out in Argentina and, especially, with regard to the transport of radioactive wastes. In particular, the legislation applicable within the national territory is described. Additionally, figures are provided on the features and amounts of transported radioactive materials, including radioactive wastes, concerning both the nuclear fuel cycle and activities related to their industrial and medical applications. (Author)

  20. Device for radioactive waste processing

    Object: To remove burr on the pellet surface obtained by pelletizing radioactive powder by the use of a rotatable roller type pellet molding machine, to prevent occurrence of powder from the pellets. Structure: Condensed radioactive liquid waste is vaporized and dried into powder form, which is fed to a granulator. The powder is forced in by means of a screw nad pelletized by a rotating roll. Pellets are charged into a rotating cage through a hopper, and rotation of the cage causes pellets to be rubbed with each other and to contact with meshes of the cage to remove burr, whereby they are formed into shaped pellets when the latter come out of the cage, which pellets are transported towards the drum filler via the hopper. Incomplete pellets or burr drop onto the lower hopper through the meshes of the cage and are turned to the granulator again. (Yoshino, Y.)

  1. Nuclear energy from radioactive waste

    The global energy demand is increasing. Sound forecasts indicate that by the year 2020 almost eight thousand million people will be living on our planet, and generating their demand for energy will require conversion of about 20 thousand million tonnes of coal equivalents a year. Against this background scenario, a new concept for energy generation elaborated by nuclear scientists at CERN attracts particular interest. The concept describing a new nuclear energy source and technology intends to meet the following principal requirements: create a new energy source that can be exploited in compliance with extremely stringent safety requirements; reduce the amount of long-lived radioactive waste; substantially reduce the size of required radwaste repositories; use easily available natural fuels that will not need isotopic separation; prevent the risk of proliferation of radioactive materials; process and reduce unwanted actinides as are generated by the operation of current breeder reactors; achieve high efficiency both in terms of technology and economics. (orig./CB)

  2. Underground disposal of radioactive wastes

    This report is an overview document for the series of IAEA reports dealing with underground waste disposal to be prepared in the next few years. It provides an introduction to the general considerations involved in implementing underground disposal of radioactive wastes. It suggests factors to be taken into account for developing and assessing waste disposal concepts, including the conditioned waste form, the geological containment and possible additional engineered barriers. These guidelines are general so as to cover a broad range of conditions. They are generally applicable to all types of underground disposal, but the emphasis is on disposal in deep geological formations. Some information presented here may require slight modifications when applied to shallow ground disposal or other types of underground disposal. Modifications may also be needed to reflect local conditions. In some specific cases it may be that not all the considerations dealt with in this book are necessary; on the other hand, while most major considerations are believed to be included, they are not meant to be all-inclusive. The book primarily concerns only underground disposal of the wastes from nuclear fuel cycle operations and those which arise from the use of isotopes for medical and research activities

  3. Financing of radioactive waste disposal

    Waste disposal is modelled as a financial calculus. In this connection the particularity is not primarily the dimension to be expected of financial requirement but above all the uncertainty of financial requirement as well as the ecological, socio-economic and especially also the temporal dimension of the Nuclear Waste Disposal project (disposal of spent fuel elements from light-water reactors with and without reprocessing, decommissioning = safe containment and disposal of nuclear power plants, permanent isolation of radioactive waste from the biosphere, intermediate storage). Based on the above mentioned factors the author analyses alternative approaches of financing or financial planning. He points out the decisive significance of the perception of risks or the evaluation of risks by involved or affected persons - i.e. the social acceptance of planned and designed waste disposal concepts - for the achievement and assessment of alternative solutions. With the help of an acceptance-specific risk measure developed on the basis of a mathematical chaos theory he illustrates, in a model, the social influence on the financing of nuclear waste disposal. (orig./HP)

  4. Management of the radioactive waste treatment facility

    Kim, Kil Jeong; An, Sum Jin; Lee, Kang Mu; Jeong, Kyeong Hwan; Lee, Young Hee; Sohn, Jong Sik; Bae, Sang Min; Kang, Kwon Ho; Yim, Kil Sung; Ui, Keum San; Kim, Tae Kuk; Sohn, Young Jun; You, Young Keol; Park, Young Yoong; Yoon, Bong Keun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)


    The radioactive wastes generated in Korea Atomic Energy Research Institute (KAERI) in 1993 are about 107 m{sup 3} of liquid waste and 169 drums of solid waste. Liquid waste is treated by the evaporation process, the bituminization process, and the solar evaporation process. The solid waste is treated by the compaction process and the cementation process. The radioactive wastes treated in 1993 are about 194 m{sup 3} of liquid waste and 31 drums of solid waste, respectively. 28 tabs., 12 figs. (Author) .new.

  5. Radioactive waste disposal: Global experience and challenges

    This document discusses radioactive waste disposal practices followed in various countries. Various technical factors like geology, hydrogeology, seismicity, etc, are taken into account during site selection. Then the sites are prepared for disposal. After disposal and closure of, the disposal facility, the site needs to be regularly monitored. This document presents various issues linked to the disposal facilities and radioactive wastes, for example, classification of radioactive wastes, design of the disposal facility, licensing procedure, disposal costs, public acceptance issues etc

  6. Radioactive wastes management: what is the situation?

    This presentation takes stock on the situation of the radioactive wastes management in France. It gives information on the deep underground disposal, the public information, the management of the radioactive wastes in France, the researches in the framework of the law of the 30 december 1991, the underground laboratory of Meuse/Haute-Marne, the national agency for the radioactive wastes management (ANDRA) and its sites. (A.L.B.)

  7. Management of radioactive wastes produced by users of radioactive materials

    This report is intended as a document to provide guidance for regulatory, administrative and technical authorities who are responsible for, or are involved in, planning, approving, executing and reviewing national waste management programmes related to the safe use of radioactive materials in hospitals, research laboratories, industrial and agricultural premises and the subsequent disposal of the radioactive wastes produced. It provides information and guidance for waste management including treatment techniques that may be available to establishments and individual users

  8. Chemical decontamination method for radioactive metal waste

    The invention relates to a decontamination method for radioactive metal waste products derived from equipment that handles radioactive materials whose surfaces have been contaminated; in particular it concerns a decontamination method that reduces the amount of radioactive waste by decontaminating radioactive waste substances to a level of radioactivity in line with normal waste products. In order to apply chemical decontamination to metal waste products whose surfaces are divided into carbon steel waste and stainless steel waste; the carbon steel waste is treated using only a primary process in which the waste is immersed in a sulfuric acid solution, while the stainless steel waste must be treated with both the primary process and then electrolytically reduces it for a specific length of time and a secondary process that uses a solution of sulfuric acid mixed with oxidizing metal salts. The method used to categorize metal waste into carbon steel waste and stainless steel waste involves determining the presence, or absence, of magnetism. Voltage is applied for a fixed duration; once that has stopped, electrolytic reduction repeats the operative cycle of applying, then stopping voltage until the potential of the radioactive metal waste is retained in the active region. 1 fig. 2 tabs

  9. The management of radioactive waste treatment facility

    The radioactive wastes generated at Korea Atomic Energy Research Institute (KAERI) in 1994 are about 56 m3 of liquid waste and 323 drums of solid waste. Liquid waste were treated by the evaporation process, the bituminization process, and the solar evaporation process. The solid wastes were treated in 1994 are about 87 m3 of liquid waste and 81 drums of solid waste, respectively. 2 tabs., 26 figs., 12 refs. (Author) .new

  10. Equipment for radioactive waste treatment

    The equipment is used for the concentration, calcination, possibly denitration of high, medium and low level radioactive wastes. It is provided with a heated body and driving mechanism. In the heated body there is a horizontal or oblique shaft with a system of vanes, possibly with a screw. On one side of the heated body there is an opening for drop and vapour extraction. A lead screen may be placed in this area, opposite to it a shielding and between them a deactivation slot. The advantage of the discovery is in that the shaft including the bearings are placed outside of the working part of the equipment. (M.D.)

  11. SHS immobilization of radioactive wastes

    Samples of mineral-like ceramics based on perovskite and model radioactive wastes were synthesized and studied. Influence of aluminum, silicon and titanium oxides additives on the properties of the obtained ceramics was investigated. It was shown, that cesium losses decreased during the synthesis while aluminum, silicon and titanium oxides content in the initial mixture was increased, and cesium uniform distribution by the sample volume was achieved. It was found, that the synthesized ceramics was characterized by dense structure and fine chemical stability; it contained mainly a perovskite phase of a present composition. (orig.)

  12. Radioactive waste management in FR Yugoslavia

    Results presented in this paper represent the nowadays status of the radioactive waste management, especially quality testing methods, which are in common with radioactive waste solidification processes, performing in the Institute of nuclear sciences ''Vinca'' in Belgrade. These investigations represent the part of important activity in a ten years mortar and concrete testing project and research work that is dealing with the radioactive waste mixture forms. The data obtained in these investigations are intended to use during the designing of the proposed central radioactive waste materials repository in FR Yugoslavia. (author)




    The policy and principles on management of radioactive wastes are stipulated.Cement solidification and bituminization unit has come into trial run.Solid radioactive waste is stored in tentative storage vault built in each of nuclear facilities.Seventeen storages associated with applications of nuclear technology and radioisotopes have been built for provinces.Disposal of low and intermediate level radioactive wastes pursues the policy of “regional disposal”.Four repositories have been planned to be built in northwest.southwest,south and east China respectively.A program for treatment and disposal of high level radioactive waste has been made.

  14. Microbiological treatment of radioactive wastes

    The ability of microorganisms which are ubiquitous throughout nature to bring about information of organic and inorganic compounds in radioactive wastes has been recognized. Unlike organic contaminants, metals cannot be destroyed, but must be either removed or converted to a stable form. Radionuclides and toxic metals in wastes may be present initially in soluble form or, after disposal may be converted to a soluble form by chemical or microbiological processes. The key microbiological reactions include (i) oxidation/reduction; (ii) change in pH and Eh which affects the valence state and solubility of the metal; (iii) production of sequestering agents; and (iv) bioaccumulation. All of these processes can mobilize or stabilize metals in the environment

  15. Supercompaction of radioactive waste at NPP Krsko

    The problem of radioactive waste management is both scientifically and technically complex and also deeply emotional issue. In the last twenty years the first two aspects have been mostly resolved up to the point of safe implementation. In the Republic of Slovenia, certain fundamentalist approaches in politics and the use of radioactive waste problem as a political tool, brought the final radioactive repository siting effort to a stop. Although small amounts of radioactive waste are produced in research institutes, hospitals and industry, major source of radioactive waste in Slovenia is the Nuclear Power Plant Krsko. When Krsko NPP was originally built, plans were made to construct a permanent radioactive waste disposal facility. This facility was supposed to be available to receive waste from the plant long before the on site storage facility was full. However, the permanent disposal facility is not yet available, and it became necessary to retain the wastes produced at the plant in the on-site storage facility for an extended period of time. Temporary radioactive storage capacity at the plant site has limited capacity and having no other options available NPP Krsko is undertaking major efforts to reduce waste volume generated to allow normal operation. This article describes the Radioactive Waste Compaction Campaign performed from November, 1994 through November, 1995 at Krsko NPP, to enhance the efficiency and safety of storage of radioactive waste. The campaign involved the retrieval, segmented gamma-spectrum measurement, dose rate measurement, compaction, re-packaging, and systematic storage of radioactive wastes which had been stored in the NPP radioactive waste storage building since plant commissioning. (author)

  16. Controlling low-level radioactive waste

    This series of information sheets describes at a popular level the sources of low-level radioactive wastes, their associated hazards, methods of storage, transportation and disposal, and the Canadian regulations that cover low-level wastes

  17. Microbiology and radioactive waste disposal

    The present Nirex Safety Assessment Research Programme on microbiology is based on experimental as well as theoretical work. It has concentrated on the study of how mixed, natural populations of microbes might survive and grow on the organic component of Low Level Radioactive Wastes (LLW) and PCM (Plutonium Contaminated Waste) in a cementitious waste repository. The present studies indicate that both carbon dioxide and methane will be produced by microbial action within the repository. Carbon dioxide will dissolve and react with the concrete to a limited extent so methane will be the principal component of the produced gas. The concentration of hydrogen, derived from corrosion, will be depressed by microbial action and that this will further elevate methane levels. Actual rates of production will be lower than that in a domestic landfill due to the more extreme pH. Microbial action will clearly affect the aqueous phase chemistry where organic material is present in the waste. The cellulosic fraction is the main determinant of cell growth and the appearance of soluble organics. The structure of the mathematical model which has been developed, predicts the general features which are intuitively expected in a developing microbial population. It illustrates that intermediate compounds will build up in the waste until growth of the next organism needed for sequential degradation is initiated. The soluble compounds in the pore water and the mixture of microbes present in the waste will vary with time and sustain biological activity over a prolonged period. Present estimates suggest that most microbial action in the repository will be complete after 400 years. There is scope for the model to deal with environmental factors such as temperature and pH and to introduce other energy sources such as hydrogen. (author)

  18. Integrated radioactive defense waste management plan

    The plan for controlling the releases of radioactivity and ensuring the safe storage of radioactive wastes generated by past, present, and future operation of the Savannah River Plant (SRP) is presented. The waste was categorized as solid, liquid, and gaseous, and the different waste management operations are categorized as treatment, storage, and release operations. Following a summary of the environmental effects of SRP emissions, the document includes in succession (1) a description of processes that generate wastes, (2) a description of the various waste treatment techniques, (3) a description of the waste holding facilities, and (4) a description of the plant's waste storage facilities

  19. Communication from the Radioactive Waste Service


    The Radioactive Waste service of the Radiation protection Group informs you that as of 15 April 2011 radioactive waste can be delivered to the waste treatment centre (Bldg. 573) only during the following hours: Mon- Thu: 08:00 – 11:30 / 13:30 – 16:00 Fri : 08:00 – 11:30 An electronic form must be filled in before the arrival of the waste at the treatment centre: for further information, please call 73171.

  20. Radioactive waste management strategy in Argentina

    In this paper, an outline is given concerning the treatment, conditioning, characterization, storage, transport and final disposal of radioactive wastes arising in the fuel cycle, radioisotopes production plant, research centers, etc. The overall strategy of the Argentina program is to plan, develop and implement the technology and provide the facilities for the permanent isolation of commercially generated wastes, with the aim that this waste not compromise the health and safety of the general public. To implement all these activities, CNEA has established in 1986 a Radioactive Waste Management Program. This long term project is aimed at meeting all the requirements for the radioactive waste management of Argentina

  1. Quantities and sources of radioactive waste

    Radioactive waste inventories have increased appreciably over the years and now require application of known technologies for their effective management. The largest remaining steps to be taken in handling these radioactive waste inventories are the appropriate way to manage spent fuel, initiation of reprocessing technology on a commercial basis, siting, construction, licensing, and operation of geologic repositories, concurrent conversion of high-level waste to solid forms appropriate for geologic repositories, and siting of low-level waste disposal areas

  2. Radioactive Waste in Oil Exploration

    Naturally occurring radioactive material commonly known as NORM composes the majority of the dose received by a person each year at approximately 80% of the total amount. However, there is a noticeably higher concentration of radioisotopes present in technologically enhanced NORM, often called TENORM, which results directly from human industrial activities. NORM is formed in the process of mineral mining including phosphate production, where the end goal is to concentrate high quantities of metals or elements (e.g. phosphorous). However, NORM has also become a widely recognized problem in the oil and gas industry. It is approximately one hundred and fifty years since oil was discovered in the continental United States and the mention of radioactivity in mineral oils and natural gases occurred in 1904, just eight years after the discovery of radioactivity by Henri Bequerel in 1896. In just over three decades the problems from naturally occurring radioactive material (NORM) wastes arising from the oil and gas industry have been much more scrutinized. In the 1980’s 226Ra began to be noticed when scrap metal dealers would detect unacceptably high levels of radiation from oil-field piping1. In 1991 Raloff2 published an article on the new hot wastes in NORM and in 1992 Wilson et. al3 described the health physics aspects of radioactive petroleum piping scale. NORM will develop in high concentrations in by-product oil and gas waste streams4-7. The NORM will chemically separate from other piped material in the process of the extraction of oil, resulting in high concentrations of 226Ra, 228 Ra and 210Pb and other radioisotopes in a densely caked layer on the inner surfaces of the piping1 . The activity of the 226Ra from NORM ranges from 185 to several tens of thousands Bq/kg of sample. By comparison, the NORM concentrations of radium in rock and soil is, at a natural level, 18.5 - 185 Bq/kg1. Disposal of NORM becomes more problematic as higher concentrations of

  3. Storage of radioactive waste. Safety guide

    The objective of this Safety Guide is to provide regulatory bodies and the operators that generate and manage radioactive waste with recommendations on how to meet the safety requirements for the safe storage of radioactive waste. The guidance provided is applicable to all storage facilities, although there are separate sections for small and large storage facilities. The storage of radioactive waste means the holding of radioactive waste in a facility that provides for its containment, with the intention of retrieval. This Safety Guide applies to the storage of solid, liquid and gaseous radioactive wastes in a wide range of facilities, including those at which waste is generated, treated and conditioned. The storage facility could range from a secure cupboard or closet in a laboratory, through to larger designated areas such as rooms or buildings, up to and including a large site dedicated to the storage of radioactive waste. This Safety Guide provides guidance that is specific to small and to large storage facilities and guidance that is common to both small and large facilities. Sections 2 and 3 address, respectively, the protection of human health and the environment, and roles and responsibilities. Section 4 outlines general safety considerations in the storage of radioactive waste that are common to both small and large storage facilities. Sections 5 and 6 provide guidance on safety in the design and operation of small and large storage facilities, respectively. Information on safety assessment as applied to the storage of radioactive waste is provided in the Appendix

  4. Environmental chemistry of radioactive waste disposal

    Duffield, J.R.; Williams, D.R.


    In this review the environmental chemistry problems associated with radioactive waste disposal are considered from the point of view of the threat to man of waste disposal, contamination pathways, the chemistry of waste containment, speciation of radio-isotopes, chemisorption, risk assessment and computerized simulation of waste disposal phenomena. A strategy for the future is discussed.

  5. Radioactive wastes management development in Chile

    A Facility for immobilizing and conditioning of radioactive wastes generated in Chile, has recently started in operation. It is a Radioactive Wastes Treatment Plant, RWTP, whose owner is Comision Chilena de Energia Nuclear, CCHEN. A Storgement Building of Conditioned Wastes accomplishes the facility for medium and low level activity wastes. The Project has been carried with participation of chilean professionals at CCHEN and Technical Assistance of International Atomic Energy Agency, IAEA. Processes developed are volume reduction by compaction; immobilization by cementation and conditioning. Equipment has been selected to process radioactive wastes into a 200 liters drum, in which wastes are definitively conditioned, avoiding exposition and contamination risks. The Plant has capacity to treat low and medium activity radioactive wastes produced in Chile due to Reactor Experimental No. 1 operation, and annex Laboratories in Nuclear Research Centers, as also those produced by users of nuclear techniques in Industries, Hospitals, Research Centers and Universities, in the whole country. With the infrastructure developed in Chile, a centralization of Radioactive Wastes Management activities is achieved. A data base system helps to control and register radioactive wastes arising in Chile. Generation of radioactive wastes in Chile, has found solution for the present production and that of near future

  6. Treatment of radioactive wastes by incineration

    Great part of the radioactive wastes of low and intermediate level generated during the nuclear fuel cycle, in laboratories and other sites where the radionuclides are used for the research in the industry, in medicine and other activities, are combustible wastes. The incineration of these radioactive wastes provides a very high reduction factor and at the same time converts the wastes in radioactive ashes and no-flammable residuals, chemically inert and much more homogeneous that the initial wastes. With the increment of the costs in the repositories and those every time but strict regulations, the incineration of radioactive wastes has been able to occupy an important place in the strategy of the wastes management. However, in a particular way, the incineration is a complex process of high temperature that demands the execution of safety and operation requirements very specific. (author)

  7. Common errors in transport of radioactive waste

    The transport of radioactive waste is a stage of the waste management and must fit the same protection and safety requirements of any radioactive material shipment. In Brazil, the radioactive waste shipments must comply with the national regulations for transport of dangerous goods and the specific regulation for the safe transport of radioactive material of the nuclear regulatory authority. In these regulations, the consignor is responsible for the safety during the transport, however, the unload operations are consignee's responsibility. The Radioactive Waste Laboratory of the Nuclear and Energy Research Institute, IPEN-CNEN/SP, receives institutional radioactive waste from several radioactive facilities in the country. During the unload operations, protection and safety items are verified, such as the data written into the transport documents and the maximum levels of radiation on packages. The records show that almost all shipments of radioactive waste presented irregularities that varied from mistakes in fulfilling transport documents, up to the total disregard to the regulations. The shipments that could result in radiological risk to the operators of IPEN-CNEN/SP gave origin to reports that had been sent to the nuclear regulatory authority to take steps to prevent new occurrences and to enforce consignors and carriers. The adoption of this procedure in any type of occurrence, as well as its institutionalization in all radioactive waste management facilities of the nuclear regulatory authority could be an improvement against the errors observed in this type of transport. (author)

  8. Low level radioactive waste disposal

    The Mochovce National Radwaste Repository is a near surface multi-barrier disposal facility for disposal of processed low and very low level radioactive wastes (radwastes) resulting from the operation and decommissioning of nuclear facilities situated in the territory of the Slovak Republic and from research institutes, laboratories, hospitals and other institutions (institutional RAW) which are in compliance with the acceptance criteria. The basic safety requirement of the Repository is to avoid a radioactive release to the environment during its operation and institutional inspection. This commitment is covered by the protection barrier system. The method of solution designed and implemented at the Repository construction complies with the latest knowledge and practice of the repository developments all over the world and meets requirements for the safe radwaste disposal with minimum environmental consequences. All wastes are solidified and have to meet the acceptance criteria before disposal into the Repository. They are processed and treated at the Bohunice RAW Treatment Centre and Liquid RAW Final Treatment Facility at Mochovce. The disposal facility for low level radwastes consists of two double-rows of reinforced concrete vaults with total capacity 7 200 fibre reinforced concrete containers (FCCs) with RAW. One double-row contains 40 The operation of the Repository was started in year 2001 and after ten years, in 2011 was conducted the periodic assessment of nuclear safety with positive results. Till the end of year 2014 was disposed to the Repository 11 514 m3 RAW. The analysis of total RAW production from operation and decommissioning of all nuclear installation in SR, which has been carried out in frame of the BIDSF project C9.1, has showed that the total volume estimation of conditioned waste is 108 thousand m3 of which 45.5 % are low level waste (LLW) and 54,5 % very low level waste (VLLW). On the base of this fact there is the need to build 7.5 double

  9. Method of processing radioactive wastes

    Purpose: After removing clads from radioactive wastes, to dry and pulverize the same thereby to reduce hazard of radiation exposure and to obtain a large volume reduction ratio. Method: Regenerated liquid wastes, sludges and spent ion-exchange resin slurries within the tanks are respectively introduced into separation tanks, and the regenerated liquid wastes are sent into a mixing tank after clads within the separation tanks have been precipitated and separated. The sludges are applied with a supersonic wave in the separation tanks, and thereafter are passed through an electromagnetic filter. Then, clads are removed from the sludges, and thereafter the sludges are sent into the mixing tank. The spent ion-exchange resin slurries are applied with a supersonic wave and stirred in the separation tanks, and sent into the mixing tank after the clads have been precipitated and separated. The mixture which has been prepared in the mixing tank is dried and pulverized by a centrifugal film drier, and mixed with burnt ashes discharged from a hopper. Then, the mixture is pelletized and asphalt-hardened. (Yoshino, Y.)

  10. Management of radioactive waste from nuclear applications

    Radioactive waste arises from the generation of nuclear energy and from the production of radioactive materials and their applications in industry, agriculture, research and medicine. The importance of safe management of radioactive waste for the protection of human health and the environment has long been recognized and considerable experience has been gained in this field. Technical expertise is a prerequisite for safe and cost-effective management of radioactive waste. A training course is considered an effective tool for providing technical expertise in various aspects of waste management. The IAEA, in co-operation with national authorities concerned with radioactive waste management, has organized and conducted a number of radioactive waste management training courses. The results of the courses conducted by the IAEA in 1991-1995 have been evaluated at consultants meetings held in December 1995 and May 1996. This guidance document for use by Member States in arranging national training courses on the management of low and intermediate level radioactive waste from nuclear applications has been prepared as the result of that effort. The report outlines the various requirements for the organization, conduct and evaluation of training courses in radioactive waste management and proposes an annotated outline of a reference training course

  11. DOE reassesses civilian radioactive waste management program

    This article reports on the announcement by the Department of Energy (DOE) that the opening of a high-level radioactive nuclear waste repository site will be delayed for seven years. The article discusses DOE's reassessment plan, the restructuring of the Office of Civilian Radioactive Waste Management, site access and evaluation, the Monitored Retrievable Storage Commission proposal, and the industry's response

  12. The computerized follow up of radioactive wastes

    After a short introduction about the goals and missions of the Andra, the French agency for the management of radioactive wastes, this educational booklet describes the principle and the different steps of the computerized follow up of radioactive waste containers: labelling, identification file, control, follow up during transport, compacting and storage. (J.S.)

  13. Probabilistic safety assessment in radioactive waste disposal

    Probabilistic safety assessment codes are now widely used in radioactive waste disposal assessments. This report gives an overview of the current state of the field. The relationship between the codes and the regulations covering radioactive waste disposal is discussed and the characteristics of current codes is described. The problems of verification and validation are considered. (author)

  14. Geomechanics of clays for radioactive waste disposal

    Clay formations have been studied for many years in the European Community as potential disposal media for radioactive waste. This document brings together results of on-going research about the geomechanical behaviour of natural clay bodies, at normal and elevated temperatures. The work is carried out within the third Community R and D programme on Management and storage of radioactive waste

  15. The conditioning of radioactive waste by bitumen

    The separation of radioactive sludge and waste by bitumen is studied. Results are given concerning various trials carried out on the lixiviation of the final product by water as a function of the pH, of the time, and of the composition. The conditions for carrying out this process of coating the waste are controlled from a radioactive point of view. (author)

  16. Repository for radioactive waste from petroleum operations

    In March 2008, the Norwegian Radiation Protection Authority (NRPA) gave the first authorisation to a new repository for radioactive waste from the petroleum industry on the Norwegian continental shelf. The authorisation is for four years initially. The repository will be the final storage destination for radioactive waste which contains enhanced levels of naturally occurring radioactive substances from petroleum extraction operations. Thus, it gives a safe and final storage facility for radioactive waste temporarily stored in facilities along the Norwegian coast. The repository is the first of its kind in Norway and is situated at Stangeneset Industrial Site in Gulen, Sogn og Fjordane County

  17. Management of radioactive waste in Israel

    Radioactive materials are used extensively in Israel in labelled chemicals in hospitals, research laboratories, industrial and agricultural premises and for environmental studies. A by products of many of these methods is radioactive waste (RW). The responsible authority for RW management in Israel is the Chief Radiation Executive (CRE). Each RW producing institute in Israel has to acquire a license for its operation. This license limits the amount to radioactive materials purchased by the institute and approves the nomination of a radiation officer. Radiation waste disposal services are offered by the IAEC's Nuclear Research Center-Negev (NRCN) which operates and monitors a National Radioactive Waste Disposal Site (NRWDS). 2 figs, 4 tabs

  18. A contribution to the problem of solidifying liquid radioactive wastes

    Radioactive waste solutions must be processed to a solid end product before transport or storage. Solidification should be performed as near as possible to the source of the solutions. A process will be described where weak and moderately active liquid wastes can be solidified without hazard. In contrast to previously employed methods based on concrete vermiculite, use of our method permits the solidification of acidic as well as alkaline solutions without neutralization. In addition, aqueous solutions contaminated with organic solvents can be processed. (orig.)

  19. Radioactive waste treatment technology at Czech nuclear power plants

    This presentation describes the main technologies for the treatment and conditioning of radioactive wastes at Czech nuclear power plants. The main technologies are bituminisation for liquid radioactive wastes and supercompaction for solid radioactive wastes. (author)

  20. Establishment of Radioactive Waste Running Safely in Whole Year


    <正>In 2008, the radioactive wastes treatment and operation center received about 90 m3 of radioactiveliquid waste, about 30 m3 of radioactive solid waste, and about 160 million m3 of treated radioactive

  1. Management of radioactive wastes of iodine therapy

    The main objective of waste radioactive management is to ensure the protection of man and the preservation of the environment. The regulation that established the basis for the good radioactive waste management was elaborated by the Comissao Nacional de Energia Nuclear (CNEN), in 1985. It is the CNEN-NE-6:05: 'Management radioactive waste in radioactive facilities', which although it an important standard related to radioactive waste management and help largely in the design of a management system in radioactive facilities of radioisotope users, covers the topics in a general way and does not consider individuals aspects of the different plants, as is the case of nuclear medicine units. The main objective of this study is to show the segregation and safe packaging, avoiding unnecessary exposure of professionals involved and public individuals in general

  2. Technology applications for radioactive waste minimization

    The nuclear power industry has achieved one of the most successful examples of waste minimization. The annual volume of low-level radioactive waste shipped for disposal per reactor has decreased to approximately one-fifth the volume about a decade ago. In addition, the curie content of the total waste shipped for disposal has decreased. This paper will discuss the regulatory drivers and economic factors for waste minimization and describe the application of technologies for achieving waste minimization for low-level radioactive waste with examples from the nuclear power industry

  3. The Guatemala Programme of radioactive waste management

    Guatemala aims at ensuring safety of present and future generations as well as the environment, this is to be achieved by preventing the release of radioactive substances contained in radioactive wastes into the environment. The main activities that produce radioactive wastes in Guatemala are medical practices (radiodiagnostic and radiotherapy), wastes are also generated in industry and research, but to lesser extent. The most frequently used radioisotopes are cesium-137, cobalt-60, iodine-131, technetium-99m. Some spent sources are radium-226, cobalt-60 and contaminated material generated in medicine and research. The radioactive wastes generated are basically low and intermediate level wastes. The collection of the wastes is done periodically, the users must deliver them correctly packed and marked. When the radioactive wastes are short lived the user must manage them himself, as in the case of technetium-99m. Presently, Guatemala is trying to achieve by means of National Centre of Radioactive Wastes (CENDRA) the adequate practices in managing, storing and subsequent disposal of radioactive wastes. 3 figs

  4. Evidence of the generation of isosaccharinic acids and their subsequent degradation by local microbial consortia within hyper-alkaline contaminated soils, with relevance to intermediate level radioactive waste disposal.

    Simon P Rout

    Full Text Available The contamination of surface environments with hydroxide rich wastes leads to the formation of high pH (>11.0 soil profiles. One such site is a legacy lime works at Harpur Hill, Derbyshire where soil profile indicated in-situ pH values up to pH 12. Soil and porewater profiles around the site indicated clear evidence of the presence of the α and β stereoisomers of isosaccharinic acid (ISA resulting from the anoxic, alkaline degradation of cellulosic material. ISAs are of particular interest with regards to the disposal of cellulosic materials contained within the intermediate level waste (ILW inventory of the United Kingdom, where they may influence radionuclide mobility via complexation events occurring within a geological disposal facility (GDF concept. The mixing of uncontaminated soils with the alkaline leachate of the site resulted in ISA generation, where the rate of generation in-situ is likely to be dependent upon the prevailing temperature of the soil. Microbial consortia present in the uncontaminated soil were capable of surviving conditions imposed by the alkaline leachate and demonstrated the ability to utilise ISAs as a carbon source. Leachate-contaminated soil was sub-cultured in a cellulose degradation product driven microcosm operating at pH 11, the consortia present were capable of the degradation of ISAs and the generation of methane from the resultant H2/CO2 produced from fermentation processes. Following microbial community analysis, fermentation processes appear to be predominated by Clostridia from the genus Alkaliphilus sp, with methanogenesis being attributed to Methanobacterium and Methanomassiliicoccus sp. The study is the first to identify the generation of ISA within an anthropogenic environment and advocates the notion that microbial activity within an ILW-GDF is likely to influence the impact of ISAs upon radionuclide migration.

  5. Evidence of the generation of isosaccharinic acids and their subsequent degradation by local microbial consortia within hyper-alkaline contaminated soils, with relevance to intermediate level radioactive waste disposal.

    Rout, Simon P; Charles, Christopher J; Garratt, Eva J; Laws, Andrew P; Gunn, John; Humphreys, Paul N


    The contamination of surface environments with hydroxide rich wastes leads to the formation of high pH (>11.0) soil profiles. One such site is a legacy lime works at Harpur Hill, Derbyshire where soil profile indicated in-situ pH values up to pH 12. Soil and porewater profiles around the site indicated clear evidence of the presence of the α and β stereoisomers of isosaccharinic acid (ISA) resulting from the anoxic, alkaline degradation of cellulosic material. ISAs are of particular interest with regards to the disposal of cellulosic materials contained within the intermediate level waste (ILW) inventory of the United Kingdom, where they may influence radionuclide mobility via complexation events occurring within a geological disposal facility (GDF) concept. The mixing of uncontaminated soils with the alkaline leachate of the site resulted in ISA generation, where the rate of generation in-situ is likely to be dependent upon the prevailing temperature of the soil. Microbial consortia present in the uncontaminated soil were capable of surviving conditions imposed by the alkaline leachate and demonstrated the ability to utilise ISAs as a carbon source. Leachate-contaminated soil was sub-cultured in a cellulose degradation product driven microcosm operating at pH 11, the consortia present were capable of the degradation of ISAs and the generation of methane from the resultant H2/CO2 produced from fermentation processes. Following microbial community analysis, fermentation processes appear to be predominated by Clostridia from the genus Alkaliphilus sp, with methanogenesis being attributed to Methanobacterium and Methanomassiliicoccus sp. The study is the first to identify the generation of ISA within an anthropogenic environment and advocates the notion that microbial activity within an ILW-GDF is likely to influence the impact of ISAs upon radionuclide migration. PMID:25748643

  6. Storage facility for radioactive wastes

    Canisters containing high level radioactive wastes are sealed in overpacks in a receiving building constructed on the ground. A plurality of storage pits are formed in a layered manner vertically in multi-stages in deep underground just beneath the receiving building, for example underground of about 1000m from the ground surface. Each of the storage pits is in communication with a shaft which vertically communicates the receiving building and the storage pits, and is extended plainly in a horizontal direction from the shaft. The storage pit comprises an overpack receiving chamber, a main gallery and a plurality of galleries. A plurality of holes for burying the overpacks are formed on the bottom of the galleries in the longitudinal direction of the galleries. A plurality of overpack-positioning devices which run in the main gallery and the galleries by remote operation are disposed in the main gallery and the galleries. (I.N.)

  7. Radioactive waste disposal in granite

    Within the framework of completing its knowledge of various rock formations, the Federal Government also considers the suitability of granite for radioactive waste disposal. For this purpose, the Federal Minister of Research and Technology participated from 1983 to 1990 in relevant research and development activities in the NAGRA rock laboratory at Grimsel, Switzerland. After about 17 field tests, it can be stated that the understanding of basic connections and interactions between the mechanical behaviour of the rock, which is determined, for instance, by natural or artificially induced rock movements, and the hydrogeological or rock hydraulic relations could be clearly improved. So far, the German share in the project costs amounts to a total of approximately DM 20.7 million. Till the end of 1993, further activities are scheduled to be carried out which will require financial funds of about DM 6.3 million. (orig./HSCH)

  8. Storage facility for radioactive waste

    An ion stream is formed at the surface of a metal container tube for containing radioactive wastes to promote heat transfer. That is, radiation energy is converted into an electric voltage by using photovoltaic elements which produce voltage by irradiation of radiation rays. Ion blows are caused by a corona discharge without relying on an external electric power source, to cause small air fluctuations. Since this air is an uprising air stream by convection, it moves upwardly and intersects electrode wires where they are laid along other directions and undergo stirring. Heat transfer by air convection between the surface of the metal container tube and the cooling air can be improved while keeping safety due to natural convection. (T.M.)

  9. Radioactive wastes. Management prospects. Appendixes

    These appendixes complete the article BN3661 entitled 'Radioactive wastes. Management prospects'. They develop the principles of the different separation processes under study and make a status of the conditioning matrices that are envisaged: 1 - principles of advanced separation (separation of U, Np, Pu, Tc and I; separation of Am and Cm in two extraction steps (Diamex and Sanex processes); separation of Am and Cm in a single extraction step (Paladin process); separation of Am and Cm (Sesame process); separation of Cs (Calixarene process); 2 - principles of separation in pyro-chemistry: separation under inert atmosphere (non-oxidizing); separation in oxidizing conditions; 3 - conditioning matrices under study for separate elements: objectives and methodology, matrices for iodine, for cesium and for actinides. (J.S.)

  10. Liquid Radioactive Wastes Treatment: A Review

    Yung-Tse Hung


    Full Text Available Radioactive wastes are generated during nuclear fuel cycle operation, production and application of radioisotope in medicine, industry, research, and agriculture, and as a byproduct of natural resource exploitation, which includes mining and processing of ores, combustion of fossil fuels, or production of natural gas and oil. To ensure the protection of human health and the environment from the hazard of these wastes, a planned integrated radioactive waste management practice should be applied. This work is directed to review recent published researches that are concerned with testing and application of different treatment options as a part of the integrated radioactive waste management practice. The main aim from this work is to highlight the scientific community interest in important problems that affect different treatment processes. This review is divided into the following sections: advances in conventional treatment of aqueous radioactive wastes, advances in conventional treatment of organic liquid wastes, and emerged technological options.