Radioactive sodium waste treatment and conditioning. Review of main aspects

International Nuclear Information System (INIS)

2007-01-01

This publication reviews the main aspects relating to the treatment and conditioning of radioactive sodium waste. This waste arises from the operation of liquid metal fast reactors (LMFRs). In this type of reactor, sodium (Na) or sodium-potassium alloys (NaK) are used as a low-effect neutron moderating coolant medium for extracting and transferring thermal energy from the core and they represent a significant technical and safety challenge during operation and decommissioning. This publication provides the reader with technologically oriented information on the present status of sodium waste management approaches and recent achievements related to treatment and conditioning, with the objective of facilitating planning and preparatory work for the decommissioning of LMFRs. This publication provides a comprehensive review of the hazards associated with sodium waste management. Given the large quantities of sodium waste arising during decommissioning or reactor refurbishment, as well as the challenges and varied techniques associated with removal of 100% of all sodium and NaK bulk quantities and residues during decommissioning, a hazards review and analysis is a critical component in planning the dismantling and waste management activities. Roughly half of this publication focuses on sodium waste generating, handling and treatment processes. This includes draining sodium and NaK from plant systems; in situ treatment of residual sodium; cutting techniques for pumps, valves, piping and other components; cleaning of components; potential reuse of sodium; and removal of selected radionuclides from sodium waste with the objective of reducing the waste classification or converting it to exempt waste. The focus is on proven techniques and technologies, and each discussed method includes a review of the associated principle or theory, practical applications, advantages and disadvantages, limitations, industry experience, and final waste products. A review is provided of final

Management of hospital radioactive wastes

International Nuclear Information System (INIS)

Mantrana, D.

1986-01-01

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.) [pt

Conditioning of radioactive waste from the waste collection centers of the German states as illustrated by radioactive waste from industrial production processes

International Nuclear Information System (INIS)

Stellmacher, J.; Sickert, T.

2011-01-01

The amount of negligible heat generating waste in Germany is increasing due to deconstruction of decommissioned nuclear facilities. Until 2040 277.000 m 3 are expected. By conditioning processes the wastes are transferred into a chemical stabile and water insoluble state and packaged in appropriate containers for final repository disposal. The radioactive waste in the collection containers are coated with wax for immobilization of the surface contamination, in the next step the containers are filled with pressurized geopolymer, a thixotropic fluid (under pressure the viscosity is decreased, so that cavities are filled). The conditioned material, the so called interim product is stored in trays for the final packaging in appropriate containers.

Decision for counting condition of radioactive waste activities measuring by Ludlum detector

International Nuclear Information System (INIS)

Bambang-Purwanto

2000-01-01

Radioactive waste must measured for activities before be throw out to environment. Measuring will be important in ordered to know activities can be given management direction. For activities radioactive waste on limit threshold value must processed, but for under limit threshold value activities can be throw out to environment. Activities measuring for solid radioactive waste and liquid by (Total, β, γ) Ludlum detector connected Mode-1000 Scaler Counting. Before measuring for solid waste activities was decisioned optimally counting condition, and be obtained are : sample weight 3.5 gram, heating temperature of 125 o C and heating time at 60 minutes. Activities measuring result by total detector ranges from (0.68-0.71) 10 -1 μCi/gram, β detector ranges from (0.24-0.25) 10 -1 μCi/gram and γ detector ranges from (0.35-0.37) μCi/gram

Strategy for research on radioactive waste processing and conditioning in France

International Nuclear Information System (INIS)

Cavedon, J.M.; Tallec, M.

2001-01-01

Research on radioactive medium level waste processing and conditioning aims at offering processing routes for waste forms and materials of potential value that are not yet provided easy handling by existing industrial processes. These studies are mandatory under the Dec 31, 1991 law and are coordinated by CEA. The strategy relies on the completion and rationalization of the existing processing routes, within acceptable technical and economic limits. Waste processing techniques aim at reducing the volume and the chemical diversity of medium activity waste, and are based on incineration-vitrification. Conditioning techniques call for high performance matrices and standardized containers, the latter keeping an ability to contain bulk waste. (author)

Handling of radioactive waste

International Nuclear Information System (INIS)

Sanhueza Mir, Azucena

1998-01-01

Based on characteristics and quantities of different types of radioactive waste produced in the country, achievements in infrastructure and the way to solve problems related with radioactive waste handling and management, are presented in this paper. Objectives of maintaining facilities and capacities for controlling, processing and storing radioactive waste in a conditioned form, are attained, within a great range of legal framework, so defined to contribute with safety to people and environment (au)

Radioactive wastes - inventories and classification

International Nuclear Information System (INIS)

Brennecke, P.; Hollmann, A.

1992-01-01

A survey is given of the origins, types, conditioning, inventories, and expected abundance of radioactive wastes in the future in the Federal Republic of Germany. The Federal Government's radioactive waste disposal scheme provides that radioactive wastes be buried in deep geological formations which are expected to ensure a maintenance-free, unlimited and safe disposal without intentional excavation of the wastes at a later date. (orig./BBR) [de

Long Term Behaviour Evaluation of Cement Conditioning Matrices Used for Management of Radioactive Wastes at IFIN-HH

International Nuclear Information System (INIS)

Dragolici, F.

2013-01-01

The mechanical and structural characterization of the radioactive waste conditioning matrix is very important during the final disposal stage in the radioactive waste management cycle. The conditioning products should be a monolith with acceptable mechanical, chemical and physical properties that are maintained over an appropriate time such that the release of radioactivity from the waste form in the environment is minimized. The aim of this work is the XRD application for the phase identification of matrix that simulates the conditioned radioactive waste and the correlation with mechanical performance. The selected matrices for the study are normal cement with iron precipitates (hydroxide and phosphate), mineral additives (bentonite and volcanic tuff) and complexing agents (tartaric, citric and oxalic acids). The results obtained by this analysis give information about the chemical reactions between the radioactive precipitates and the hydrates, hydrolysis products of the cement. (author)

Leaching behavior of a simulated bituminized radioactive waste form under deep geological conditions

International Nuclear Information System (INIS)

Nakayama, Shinichi; Iida, Yoshihisa; Nagano, Tetsushi; Akimoto, Toshiyuki

2003-01-01

The leaching behavior of a simulated bituminized waste form was studied to acquire data for the performance assessment of the geologic disposal of bituminized radioactive waste. Laboratory-scale leaching tests were performed for radioactive and non-radioactive waste specimens simulating bituminized waste of a French reprocessing company, COGEMA. The simulated waste was contacted with deionized water, an alkaline solution (0.03-mol/l KOH), and a saline solution (0.5-mol/l KCl) under atmospheric and anoxic conditions. The concentrations of Na, Ba, Cs, Sr, Np, Pu, NO 3 , SO 4 and I in the leachates were determined. Swelling of the bituminized waste progressed in deionized water and KOH. The release of the soluble components, Na and Cs, was enhanced by the swelling, and considered to be diffusion-controlled in the swelled layers of the specimens. The release of sparingly soluble components such as Ba and Np was solubility-limited in addition to the progression of leaching. Neptunium, a redox-sensitive element, showed a distinct difference in release between anoxic and atmospheric conditions. The elemental release from the bituminized waste specimens leached in the KCl was very low, which is likely due to the suppression of swelling of the specimens at high ionic strength. (author)

Condition assessment of the Los Alamos National Laboratory radioactive liquid waste collection system

International Nuclear Information System (INIS)

Edgemon, G.L.; Moss, W.D.; Worland, V.P.

2004-01-01

The radioactive liquid waste collection system (RLWCS) at Los Alamos National Laboratory (LANE) is a site-wide double-encased piping system installed in 1982 that allows radioactive liquid waste (RLW) producing facilities to gravity drain their waste to the radioactive liquid waste treatment facility (RLWTF) through a system of underground high-density polyethylene (HDPE) pipes and vaults. The RLWCS stretches approximately four miles and typically receives approximately 10,000 gallons of RLW per day for treatment at the RLWTF. Uncertainty of the current condition of the RLWCS was recently identified as a potential risk to the future continued availability of the RLW treatment function. A condition assessment was performed in April 2004 to evaluate the risks and estimate the remaining useful life of the existing RLWCS. Several representative and 'worst-case' RLWCS primary piping sections and their associated inspection vaults were selected for direct visual assessment, remote borescopic examination, and in-situ durometer testing. This field investigation combined with an RLWCS materials compatibility review showed that the primary piping of the RLWCS is in relatively good condition, with only a few noteworthy areas of degradation.

Hydrothermal conditions around a radioactive waste repository

International Nuclear Information System (INIS)

Thunvik, R.; Braester, C.

1981-12-01

Numerical solutions for the hydrothermal conditions around a hard rock repository for nuclear fuel waste are presented. The objective of the present investigation is to illustrate in principle the effect of heat released from a hypothetical radioactive waste repository with regard to anisotropy in the rock permeability. Permeability and porosity are assumed to be constant or to decrease exponentially with depth. The hypothetical repository is situated below a horizontal ground surface or below the crest of a hill, and it is assumed that the water table follows the topography. Major interest in the analysis is directed towards the influence of anisotropy in the permeability on the flow patterns and travel times for water particles, being traced from the repository to the ground surface. The presented results show that anisotropy in the permeability may have a significant influence on the flow conditions around the repository and subsequently also on the travel times from the repository. (Authors)

Treatment of Radioactive Gaseous Waste

International Nuclear Information System (INIS)

2014-07-01

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

Optimization of Concrete Composition in Radioactive Waste Management

International Nuclear Information System (INIS)

IIija, P.

1999-01-01

Low and Intermediate level radioactive waste re presents 95% of the total wastes that is conditioned into special concrete containers. Since these containers are to protect radioactive waste safely for about 300 years, the selection and precise control of physical and mechanical characteristics of materials is very important. After volume reduction and valuable components recovery, waste materials have to be conditioned for transport, storage and disposal. Conditioning is the waste management step in which radioactive wastes are immobilized and packed . In this paper methods and optimization of concrete container composition, used for storing radioactive waste, is presented

The disposal of radioactive waste

International Nuclear Information System (INIS)

Ormai, P.

2006-01-01

The first part shows different ways of 'producing' radioactive wastes, defines the wastes of small, medium and high activity and gives estimation on the quantity of the necessary capacities of waste disposal facilities. The modern radioactive waste disposal that is the integrated processing of the form of waste, the package, the technical facility and the embedding geological environment that guarantee the isolation together. Another factor is the lifetime of radioactive waste which means that any waste containing long lifetime waste in higher concentration than 400-4000 kBq/kg should be disposed geologically. Today the centre of debate disposal of radioactive waste is more social than technical. For this reason not only geological conditions and technical preparations, but social discussions and accepting communities are needed in selecting place of facilities. Now, the focus is on long term temporary disposal of high activity wastes, like burnt out heating elements. The final part of the paper summarizes the current Hungarian situation of disposal of radioactive wastes. (T-R.A.)

Radioactive liquid waste filtering device

International Nuclear Information System (INIS)

Inami, Ichiro; Tabata, Masayuki; Kubo, Koji.

1988-01-01

Purpose: To prevent clogging in filter materials and improve the filtration performance for radioactive liquid wastes without increasing the amount of radioactive wastes. Constitution: In a radioactive waste filtering device, a liquid waste recycling pipe and a liquid recycling pump are disposed for recycling the radioactive liquid wastes in a liquid wastes vessel. In this case, the recycling pipe and the recycling pump are properly selected so as to satisfy the conditions capable of making the radioactive liquid wastes flowing through the pipe to have the Reynolds number of 10 4 - 10 5 . By repeating the transportation of radioactive liquid wastes in the liquid waste vessel through the liquid waste recycling pipe by the liquid waste recycling pump and then returning them to the liquid waste vessel again, particles of fine grain size in the suspended liquids are coagulated with each other upon collision to increase the grain size of the suspended particles. In this way, clogging of the filter materials caused by the particles of fine grain size can be prevented, thereby enabling to prevent the increase in the rising rate of the filtration differential pressure, reduce the frequency for the occurrence of radioactive wastes such as filter sludges and improve the processing performance. (Kamimura, M.)

What to do with radioactive wastes?

International Nuclear Information System (INIS)

2006-01-01

This power point presentation (82 slides) gives information on what is a radioactive waste, radioactivity and historical review of radioactivity, radioactive period, natural radioactivity (with examples of data), the three main radiation types (α, β, γ), the origin of radioactive wastes (nuclear power, research, defense, other), the proportion of radioactive wastes in the total of industrial wastes in France, the classification of nuclear wastes according to their activity and period, the quantities and their storage means, the 1991 december 30 law (France) related to the radioactive waste management, the situation in other countries (Germany, Belgium, Canada, USA, Finland, Japan, Netherlands, Sweden, Switzerland), volume figures and previsions for the various waste types in 2004, 2010 and 2020, the storage perspectives, the French national debate on radioactive waste management and the objective of perpetuated solutions, the enhancement of the public information, the 15 June 2006 law on a sustainable management of radioactive materials and wastes with three main axis (deep separation and transmutation, deep storage, waste conditioning and long term surface storage), and the development of a nuclear safety and waste culture that could be extended to other types of industry

Development of methods for treatment and conditioning of biological radioactive waste in the Czech Republic

International Nuclear Information System (INIS)

Holub, J.

1997-01-01

Incineration of biological radioactive waste was performed in a facility manufactured in the Czech Republic for combustion of burnable, radioactive and non-radioactive residues. The equipment has shown an adequate capability for combustion of biological waste. Basic technical parameters of the incinerator SP-603 can guarantee combustion of majority of wastes from different radionuclide users in the country. To ensure proper further handling with the resulting ash, three conditioning options were studied, the bituminization process, incorporation into cement, and embedding of ash into a mixture of bituminous and cementitious materials. Mechanical properties of the conditioned ash were in good compliance with those published elsewhere. Bituminized ash exhibits lowest leachibility, followed by the ash conditioned by means of the mixed process. Potential abnormal operation conditions were evaluated and their consequences assessed. The evaluation encompassed sensitivity analysis of the consequences potentially affecting the operating staff, nearby population and the environment. Cost estimate was carried out using a national approach for the calculation. From the results it can be seen that there are no large differences between the conditioning and disposal of wastes resulting from different conditioning processes. (author). 16 refs, 4 figs, 15 tabs

Development of methods for treatment and conditioning of biological radioactive waste in the Czech Republic

Energy Technology Data Exchange (ETDEWEB)

Holub, J [NYCOM, Prague (Czech Republic)

1997-02-01

Incineration of biological radioactive waste was performed in a facility manufactured in the Czech Republic for combustion of burnable, radioactive and non-radioactive residues. The equipment has shown an adequate capability for combustion of biological waste. Basic technical parameters of the incinerator SP-603 can guarantee combustion of majority of wastes from different radionuclide users in the country. To ensure proper further handling with the resulting ash, three conditioning options were studied, the bituminization process, incorporation into cement, and embedding of ash into a mixture of bituminous and cementitious materials. Mechanical properties of the conditioned ash were in good compliance with those published elsewhere. Bituminized ash exhibits lowest leachibility, followed by the ash conditioned by means of the mixed process. Potential abnormal operation conditions were evaluated and their consequences assessed. The evaluation encompassed sensitivity analysis of the consequences potentially affecting the operating staff, nearby population and the environment. Cost estimate was carried out using a national approach for the calculation. From the results it can be seen that there are no large differences between the conditioning and disposal of wastes resulting from different conditioning processes. (author). 16 refs, 4 figs, 15 tabs.

Conditioning characterization of low level radioactive waste

International Nuclear Information System (INIS)

Osman, A. F.

2010-12-01

This study has been carried out in the radioactive waste management laboratory Sudan Atomic Energy Commission. The main purpose of this work is method development for treatment and conditioning of low level liquid waste in order to improve radiation protection level in the country. For that purpose a liquid radioactive material containing Cs-137 was treated using the developed method. In the method different type of materials (cement, sands, concrete..etc) were tested for absorption of radiation emitted from the source as well as suitability of the material for storage for long time. It was found that the best material to be used is Smsmia concrete. Where the surface dose reduced from 150 to 3μ/h. Also design of storage container was proposed (with specification: diameter 6.5 cm, height 6 cm, placed in internal cylinder of diameter 10.3 cm, height 12.3 cm) and all are installed on the concrete and cement in the cylinder. Method was used in the process of double-packaging configuration. For more protection it is proposed that a mixed of cement to fill the void in addition to the sand be added to ensure low amount of radiation exposure while transport or storage. (Author)

A radioactive waste transportation package monitoring system for normal transport and accident emergency response conditions

International Nuclear Information System (INIS)

Brown, G.S.; Cashwell, J.W.; Apple, M.L.

1993-01-01

This paper addresses spent fuel and high level waste transportation history and prospects, discusses accident histories of radioactive material transport, discusses emergency responder needs and provides a general description of the Transportation Intelligent Monitoring System (TRANSIMS) design. The key objectives of the monitoring system are twofold: (1) to facilitate effective emergency response to accidents involving a radioactive waste transportation package, while minimizing risk to the public and emergency first-response personnel, and (2) to allow remote monitoring of transportation vehicle and payload conditions to enable research into radioactive material transportation for normal and accident conditions. (J.P.N.)

Radioactive waste management at Institute for Nuclear Research (ICN) - Pitesti

International Nuclear Information System (INIS)

Bujoreanu, C.

2004-01-01

The amounts of liquid and solid wastes accumulated at the Radioactive Wastes Treatment Plant are given. The technologies used for the treatment and conditioning of radioactive wastes are presented. The final product is metallic drum-concrete-radioactive wastes (type A package) for the final disposal at the National Repository Baita, Bihor. The facilities for radioactive waste management at ICN Pitesti are: Plant for treatment, with uranium recovery of liquid radioactive waste resulting from the fabrication of CANDU type nuclear fuel; Plant for treatment of low-active liquid wastes; Plant for conditioning in concrete of the radioactive concentrate obtained during the evaporation treatment of liquid radioactive waste; Plant for incineration of solid radioactive waste contaminated with natural uranium; Plant for treatment and conditioning of organic liquid radioactive waste with tritium content. This wastes are generated by Cernavoda-NPP operation; Plant for conditioning into bitumen of spent ion exchangers at TRIGA reactor. The existing Facility is Baita repository - with two rock cavities of an uranium mine and the total capacity of 21000 containers (200 l drums)

Interim storage of radioactive waste packages

International Nuclear Information System (INIS)

1998-01-01

This report covers all the principal aspects of production and interim storage of radioactive waste packages. The latest design solutions of waste storage facilities and the operational experiences of developed countries are described and evaluated in order to assist developing Member States in decision making and design and construction of their own storage facilities. This report is applicable to any category of radioactive waste package prepared for interim storage, including conditioned spent fuel, high level waste and sealed radiation sources. This report addresses the following issues: safety principles and requirements for storage of waste packages; treatment and conditioning methods for the main categories of radioactive waste; examples of existing interim storage facilities for LILW, spent fuel and high level waste; operational experience of Member States in waste storage operations including control of storage conditions, surveillance of waste packages and observation of the behaviour of waste packages during storage; retrieval of waste packages from storage facilities; technical and administrative measures that will ensure optimal performance of waste packages subject to various periods of interim storage

Final disposal of radioactive waste

Directory of Open Access Journals (Sweden)

Freiesleben H.

2013-06-01

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.

Identification and characterization of radioactive wastes

International Nuclear Information System (INIS)

RANDRIAMORA, T.H.

2007-01-01

As the goal of the radioactive waste management is to protect human health and the environment, without imposing excessive constraints to the future generations, this work consists with of the identification of the radioactive waste existing in Madagascar, theirs characterizations for their later conditioning and their final storage. In this work, we used a dosimeter GRAETZ X5 C and a portable spectrometer EXPLORANIUM GR 135. These apparatuses have a great advantage at the user level because of their capacity to measure the equivalent dose rate, to identify, search and locate radiocative elements. The establishment of national center for radioactive waste management for the conditioning and the storage of spent sealed sources is the best solution for radioactive waste management in Madagascar. [fr

Argentina's radioactive waste disposal policy

International Nuclear Information System (INIS)

Palacios, E.

1986-01-01

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.) [pt

Experience and projects concerning treatment, conditioning and storage of all radioactive wastes from Tokai reprocessing plant

International Nuclear Information System (INIS)

Fukuda, G.; Matsumoto, K.; Miyahara, K.

1984-01-01

The active operation of Tokai reprocessing plant started in September 1977, and about 170 t U of spent fuel were reprocessed between then and December 1982. During this period, the low-level waste processing plant reduced the amount of radioactivity discharged into the environment. For radioactive liquid waste, the treatment procedures consist mainly of evaporation to keep the discharge into the sea at a low level. For combustible low-level solid waste and the solvent waste, which is of low tributyl phosphate content, incineration has been used successfully (burned: about 150 t of combined LLSW, about 50 m 3 of solvent waste, i.e. diluent waste). Most of the past R and D work was devoted to reducing the activity discharged into the environment. Current R and D work is concerned with the treatment of solvent waste, the conditioning of solid wastes, the bituminization of low-level liquid waste and the vitrification of high-level liquid waste. The paper describes present practices, R and D work and future aspects of the treatment, conditioning and storage of all radioactive wastes from Tokai reprocessing plant. (author)

Researches on the radioactive wastes management: advances in the domain of the conditioning and the storage

International Nuclear Information System (INIS)

2003-12-01

This paper presents in the first part the researches in the domain of the radioactive wastes management at the Cea: separation processes and transmutation, the underground geologic disposal, the conditioning and the storage. The recent progresses in the domain of the conditioning and the storage are then detailed and the legal context presented. A special attention is given to the CECER of Marcoule, the expertise center on the conditioning and the storage of radioactive wastes. (A.L.B.)

Development of integrated radioactive waste packaging and conditioning solutions in the UK

Energy Technology Data Exchange (ETDEWEB)

Sibley, Peter; Butter, Kevin; Zimmerman, Ian [EnergySolutions EU Ltd., Swindon, Wiltshire (United Kingdom); Viermann, Joerg [GNS Gesellschaft fur Nuklear-Service mbH, Essen (Germany); Messer, Matthias [GNS Gesellschaft fur Nuklear-Service mbH, Bristol (United Kingdom)

2013-07-01

In order to offer a more cost effective, safer and efficient Intermediate Level Waste (ILW) management service, EnergySolutions EU Ltd. and Gesellschaft fur Nuklear-Service mbH (GNS) have been engaged in the development of integrated radioactive waste retrieval, packaging and conditioning solutions in the UK. Recognising the challenges surrounding regulatory endorsement and on-site implementation in particular, this has resulted in an alternative approach to meeting customer, safety regulator and disposability requirements. By working closely with waste producers and the organisation(s) responsible for endorsing radioactive waste management operations in the UK, our proposed solutions are now being implemented. By combining GNS' off-the-shelf, proven Ductile Cast Iron Containers (DCICs) and water removal technologies, with EnergySolutions EU Ltd.'s experience and expertise in waste retrieval, safety case development and disposability submissions, a fully integrated service offering has been developed. This has involved significant effort to overcome technical challenges such as onsite equipment deployment, active commissioning, conditioning success criteria and disposability acceptance. Our experience in developing such integrated solutions has highlighted the importance of working in collaboration with all parties to achieve a successful and viable outcome. Ultimately, the goal is to ensure reliable, safe and effective delivery of waste management solutions. (authors)

Disposal of radioactive wastes

International Nuclear Information System (INIS)

Dlouhy, Z.

1982-01-01

This book provides information on the origin, characteristics and methods of processing of radioactive wastes, as well as the philosophy and practice of their storage and disposal. Chapters are devoted to the following topics: radioactive wastes, characteristics of radioactive wastes, processing liquid and solid radioactive wastes, processing wastes from spent fuel reprocessing, processing gaseous radioactive wastes, fixation of radioactive concentrates, solidification of high-level radioactive wastes, use of radioactive wastes as raw material, radioactive waste disposal, transport of radioactive wastes and economic problems of radioactive wastes disposal. (C.F.)

Transport of radioactive waste in Germany - a survey

International Nuclear Information System (INIS)

Alter, U.

1995-01-01

The transport of radioactive waste is centralised and coordinated by the German Railway Company (Deutsche Bahn AG, DB) in Germany. The conditioning of radioactive waste is now centralised and carried out by the Gesellschaft fuer Nucklear Service (GNS). The Germany Railway Company, DB, is totally and exclusively responsible for the transport, the GNS is totally and exclusively responsible for the conditioning of radioactive waste. The German Railway Company transports all radioactive waste from nuclear power plants, conditioning facilities and the existing intermediate storage facilities in Germany. In 1992 nearly 177 shipments of radioactive waste were carried out, in 1991 the total amount was 179 shipments. A brief description of the transport procedures, the use of different waste packages for radioactive waste with negligible heat generation and the transport routes within Germany will be given. For this purpose the inspection authorities in Germany have used a new documentation system, a special computer program for waste flow tracking and quality assurance and compliance assurance, developed by the electrical power companies in Germany. (Author)

Chapter 7. Radioactive wastes

International Nuclear Information System (INIS)

2000-01-01

The inspection and assessment activities of Nuclear Regulatory Authority of the Slovak Republic (UJD) focused on minimization of activity and the quantity of produced radioactive waste (RAW), and on increasing safety of waste management. The general scheme of rad-waste management in the Slovak Republic is presented. The radioactive wastes produced during the operation of NPP V-1, NPP V-2 and NPP Mochovce in 1999 are listed.Liquid RAW was treated and conditioned into a solid form at the nuclear facility Technology for treatment and conditioning of RAW. In 1999 combustible solid waste was treated at the nuclear facility Incinerator of VUJE Trnava. Produced liquid and solid RAW are stored at designed equipment at individual nuclear installations (in case of NPP V-1, NPP V-2 Bohunice and NPP Mochovce in compliance with the Regulation No. 67/1987 Coll. law).The status of free capacity of these storages as of 31.121999 is presented. Storage solidified product built the SE-VYZ was fully filled at the end of 1999. In 1999 there was a significant improvement in the process of radioactive waste management by: (A) issuing approval for commissioning the National Repository for RAW, (B) issuing approval for commissioning the Treatment and Conditioning Center for RAW, (C) having the application for approval to transport conditioned RAW to the National repository Mochovce in the final stage of evaluation. At the beginning of 2000 it is realistic to expect that RAW conditioned in the Conditioning center of RAW will start to be disposed at the National repository of RAW in Mochovce

Sponsored research on radioactive waste management

International Nuclear Information System (INIS)

1983-01-01

The report is in chapters entitled: introduction (background, responsibilities, options, structure of the programme); strategy development; disposal of accumulations; disposal of radioactive waste arisings; quality assurance for waste conditioning quality assurance related to radioactive waste disposal (effectiveness of different rock types as natural barriers to the movement of radioactivity, and non-site specific factors in the design of repositories; radiological assessment; environmental studies; research and development to meet requirements specific to UKAEA wastes; long term research (processes for the solidification of highly active liquid wastes); plutonium contamination waste minimisation. (U.K.)

Geological aspects of radioactive waste disposal

International Nuclear Information System (INIS)

Kobera, P.

1985-01-01

Geological formations suitable for burying various types of radioactive wastes are characterized applying criteria for the evaluation and selection of geological formations for building disposal sites for radioactive wastes issued in IAEA technical recommendations. They are surface disposal sites, disposal sites in medium depths and deep disposal sites. Attention is focused on geological formations usable for injecting self-hardening mixtures into cracks prepared by hydraulic decomposition and for injecting liquid radioactive wastes into permeable rocks. Briefly outlined are current trends of the disposal of radioactive wastes in Czechoslovakia and the possibilities are assessed from the geological point of view of building disposal sites for radioactive wastes on the sites of Czechoslovak nuclear power plants at Jaslovske Bohunice, Mochovce, Dukovany, Temelin, Holice (eastern Bohemia), Blahoutovice (northern Moravia) and Zehna (eastern Slovakia). It is stated that in order to design an optimal method of the burial of radioactive waste it will be necessary to improve knowledge of geological conditions in the potential disposal sites at the said nuclear plants. There is usually no detailed knowledge of geological and hydrological conditions at greater depths than 100 m. (Z.M.)

The conditioning of radioactive waste by bitumen; Conditionnement des dechets radioactifs par le bitume

Energy Technology Data Exchange (ETDEWEB)

Rodier, J; Scheidhauer, J; Malabre, M [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

1961-07-01

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) [French] L'isolement de boues radioactives et de dechets par le bitume est etudie. Les resultats de divers essais portant sur la lixiviation par l'eau du produit fini en fonction du pH, du temps et de la composition sont exposes. Les conditions de realisation de l'enrobage sont controlees au point de vue du risque radioactif. (auteur)

Method of decomposing radioactive organic solvent wastes

International Nuclear Information System (INIS)

Uki, Kazuo; Ichihashi, Toshio; Hasegawa, Akira; Sato, Tatsuaki

1986-01-01

Purpose: To decompose radioactive organic solvent wastes or radioactive hydrocarbon solvents separated therefrom into organic materials under moderate conditions, as well as greatly decrease the amount of secondary wastes generated. Method: Radioactive organic solvent wastes comprising an organic phosphoric acid ester ingredient and a hydrocarbon ingredient as a diluent therefor, or radioactive hydrocarbon solvents separated therefrom are oxidatively decomposed by hydrogen peroxide in an aqueous phosphoric acid solution of phosphoric acid metal salts finally into organic materials to perform decomposing treatment for the radioactive organic solvent wastes. The decomposing reaction is carried out under relatively moderate conditions and cause less burden to facilities or the likes. Further, since the decomposed liquid after the treatment can be reused for the decomposing reaction as a catalyst solution secondary wastes can significantly be decreased. (Yoshihara, H.)

Collecting and identifying the radioactive waste

International Nuclear Information System (INIS)

Dogaru, C. GH.

2001-01-01

The procedure 'Collecting and identifying the radioactive waste' applied by the Radioactive Waste Management Department, STDR, complies with the requirements of the competent authority concerning the radioactive source management. One of the most important tasks, requiring the application of this procedure, is collecting and identification of 'historical wastes' for which a complete book keeping does not exist from different reasons. The chapter 1 presents the procedure's goal and the chapter 2 defines the applicability field. Chapter 3 enlists the reference documents while the chapter 4 gives the definitions and abbreviations used in the procedure. Chapter 5 defines responsibilities of the operators implied in collecting, identification and characterization of the radioactive wastes, the producers of the radioactive wastes being implied. Chapter 6 gives the preliminary conditions for applying the procedure. Among these, the transport, collecting, processing, storing and characterization costs are implied, as well as the compliance with technical and different other condition. The procedure structure is presented in the chapter 7. In collecting radioactive wastes, two situations are possible: 1- the producer is able to prepare the wastes for transport and to deliver them to STDR; 2 - the wastes are received from the producer by a delegate STDR operator, properly and technically prepared. The producer must demonstrate by documents the origin and possession, analysis bulletins specifying, the radionuclides activity and measurement date, physical state and, in addition, for spent radiation sources, the series/number of the container and producer. In case the producer is not able to display all this information, the wastes are taken into custody by the STDR labs in view of their analysis. A record in writing is completed specifying the transfer of radioactive wastes from the producer to the STDR, a record which is sent to the national authority in charge with the

Progress on Radioactive Waste Treatment Facilities Construction

Institute of Scientific and Technical Information of China (English)

无

2011-01-01

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

An industry perspective on commercial radioactive waste disposal conditions and trends.

Science.gov (United States)

Romano, Stephen A

2006-11-01

The United States is presently served by Class-A, -B and -C low-level radioactive waste and naturally-occurring and accelerator-produced radioactive material disposal sites in Washington and South Carolina; a Class-A and mixed waste disposal site in Utah that also accepts naturally-occurring radioactive material; and hazardous and solid waste facilities and uranium mill tailings sites that accept certain radioactive materials on a site-specific basis. The Washington site only accepts low-level radioactive waste from 11 western states due to interstate Compact restrictions on waste importation. The South Carolina site will be subject to geographic service area restrictions beginning 1 July 2008, after which only three states will have continued access. The Utah site dominates the commercial Class-A and mixed waste disposal market due to generally lower state fees than apply in South Carolina. To expand existing commercial services, an existing hazardous waste site in western Texas is seeking a Class-A, -B and -C and mixed waste disposal license. With that exception, no new Compact facilities are proposed. This fluid, uncertain situation has inspired national level rulemaking initiatives and policy studies, as well as alternative disposal practices for certain low-activity materials.

Radioactive waste in Federal Germany

International Nuclear Information System (INIS)

Brennecke, P.; Schumacher, J.; Warnecke, E.

1988-01-01

The Physikalisch-Technische Bundesanstalt (PTB) is responsible for the long-term storage and disposal of radioactive waste according to the Federal Atomic Energy Act. On behalf of the Federal Minister of the Environment, Nature Conservation and Nuclear Safety, since 1985, the PTB has been carrying out annual inquiries into the amounts of radioactive waste produced in the Federal Republic of Germany. Within the scope of this inquiry performed for the preceding year, the amounts of unconditioned and conditioned waste are compiled on a producer- and plant-specific basis. On the basis of the inquiry for 1986 and of data presented to the PTB by the waste producers, future amounts of radioactive waste have been estimated up to the year 2000. The result of this forecast is presented. In the Federal Republic of Germany two sites are under consideration for disposal of radioactive waste. In the abandoned Konrad iron mine in Salzgitter-Bleckenstedt it is intended to dispose of such radioactive waste which has a negligible thermal influence upon the host rock. The Gorleben salt dome is being investigated for its suitability for the disposal of all kinds of solid and solidified radioactive wastes, especially of heat-generating waste. Comparing the estimated amount of radioactive wastes with the capacity of both repositories it may be concluded that the Konrad and Gorleben repositories will provide sufficient capacity to ensure the disposal of all kinds of radioactive waste on a long-term basis in the Federal Republic of Germany. 1 fig., 2 tabs

Krsko NPP radioactive waste characteristics

International Nuclear Information System (INIS)

Skanata, D.; Kroselj, V.; Jankovic, M.

2007-01-01

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

Studies on cement matrix materials used at the Radioactive Waste Treatment Plant for radwaste conditioning

International Nuclear Information System (INIS)

Dragolici, Felicia; Lungu, Laura; Nicu, Mihaela; Rotarescu, Gheorghe; Turcanu, Corneliu

2003-01-01

The research activities performed by Department of Radioactive Waste Management is focused on the treatment of LLAW products obtained by chemical precipitation and on the conditioning of these products by cementation. The individual mechanisms implied in the chemical precipitation processes are directly dependent on the precipitate properties and structure, which in turn are connected with the initial system composition and the precipitation procedure, i.e. reagent concentration, rate and orders of chemical addition, mixing rate and time and ageing conditions. In case of conditioning by cementation, the chemical nature and proportion of the sludges or concentrates affect both the hydrolysis of the initial cement components and the reactions of metastable hydration constituents, as well as the mechanical strength and chemical resistance of the hardened cemented matrix.Generally, the study of the precipitation products and their behaviour during cementation and the long-term disposal is extremely difficult because of the system complexity (phase composition and structure) and the lack of the non-destructive analytical methods. The experience accumulated by the countries who advanced nuclear programmes in military and socio-economic fields and which produced important volumes of radioactive wastes, leads us to study some of mineral additives to be used in the conditioning and disposal technology. Is well known that some mineral additives can diminish the leaching rate of the radionuclides in the disposal environment.The studies have the purpose to obtain the most propitious mixture of cement-bentonite and cement-volcanic tuff, which have the mechanical properties similar to the cement paste used for the conditioning of radioactive waste.Taking into account the characteristics of these mineral binders, namely a very good plasticity and capacity of adsorption, which lead at the decrease of porosity, the mixture is planned to be used in the future, at the Radioactive

Conditioning and storage of low level radioactive waste in FR Yugoslavia

International Nuclear Information System (INIS)

Plecas, I.; Pavlovic, R.; Pavlovic, S.

2000-01-01

FR Yugoslavia is a country without any nuclear power plant on its territory. In the last forty years in the country, as a result of the two research reactors operation and also from radionuclides applications in medicine, industry and agriculture, radioactive waste materials of different levels of specific activity are generated. As a temporary solution, these radioactive waste materials are stored in the two interim storage facility. Since one of the storage facilities is completely full with radioactive wastes, packed in metal drums and plastic barrels, and the second one has an effective space for the next few years, attempts are made in the 'Vinca' Institute of Nuclear Sciences in developing the the immobilization process, for low and intermediate level radioactive wastes and their safe disposal. As an immobilization process, cementation process is investigated. Developed immobilization process has, as a final goal, production of solidified waste-matrix mixture form, that is easy for handling and satisfies requirements for interim storage and final disposal. Radioactive wastes immobilized in inactive matrices are to be placed into concrete containers for further manipulation and disposal

Low-level radioactive waste treatment technology. Low-level radioactive waste management handbook series

International Nuclear Information System (INIS)

1984-07-01

Each generator of low-level radioactive waste must consider three sequential questions: (1) can the waste in its as-generated form be packaged and shipped to a disposal facility; (2) will the packaged waste be acceptable for disposal; and (3) if so, is it cost effective to dispose of the waste in its as-generated form. These questions are aimed at determining if the waste form, physical and chemical characteristics, and radionuclide content collectively are suitable for shipment and disposal in a cost-effective manner. If not, the waste management procedures will involve processing operations in addition to collection, segregation, packaging, shipment, and disposal. This handbook addresses methods of treating and conditioning low-level radioactive waste for shipment and disposal. A framework is provided for selection of cost-effective waste-processing options for generic categories of low-level radioactive waste. The handbook is intended as a decision-making guide that identifies types of information required to evaluate options, methods of evaluation, and limitations associated with selection of any of the processing options

Collection and Segregation of Radioactive Waste. Principals for Characterization and Classification of Radioactive Waste

International Nuclear Information System (INIS)

Dziewinska, K.M.

1998-01-01

Radioactive wastes are generated by all activities which utilize radioactive materials as part of their processes. Generally such activities include all steps in the nuclear fuel cycle (for power generation) and non-fuel cycle activities. The increasing production of radioisotopes in a Member State without nuclear power must be accompanied by a corresponding development of a waste management system. An overall waste management scheme consists of the following steps: segregation, minimization, treatment, conditioning, storage, transport, and disposal. To achieve a satisfactory overall management strategy, all steps have to be complementary and compatible. Waste segregation and minimization are of great importance mainly because they lead to cost reduction and reduction of dose commitments to the personnel that handle the waste. Waste characterization plays a significant part in the waste segregation and waste classification processes, it implicates required waste treatment process including the need for the safety assessment of treatment conditioning and storage facilities

Management of radioactive waste at INR-technical support for processing of radioactive waste from nuclear facilities

International Nuclear Information System (INIS)

Bujoreanu, D.; Popescu, I.V.; Bujoreanu, L.

2009-01-01

The Institute for nuclear research (INR) subsidiary of the Romanian authority for nuclear activities has its own radwaste treatment plant (STDR). STDR is supposed to treat and condition radioactive waste from the nuclear fuel facility, the TRIGA reactor, post irradiation examination laboratories and other research laboratories of NRI. The main steps of waste processing are: pretreatment (collection, characterization, segregation, decontamination)., treatment (waste volume reduction, radionuclide removal, compositional change), conditioning (immobilization and containerization), interim storage of the packages in compliance with safety requirements for the protection of human health and environmental protection, transport of the packages containing radioactive waste, disposal.

Low-level radioactive waste, mixed low-level radioactive waste, and biomedical mixed waste

International Nuclear Information System (INIS)

Anon.

1994-01-01

This document describes the proceedings of a workshop entitled: Low-Level Radioactive Waste, Mixed Low-Level Radioactive Waste, and Biomedical Mixed Waste presented by the National Low-Level Waste Management Program at the University of Florida, October 17-19, 1994. The topics covered during the workshop include technical data and practical information regarding the generation, handling, storage and disposal of low-level radioactive and mixed wastes. A description of low-level radioactive waste activities in the United States and the regional compacts is presented

Radioactive waste treatment

International Nuclear Information System (INIS)

Alter, U.

1988-01-01

For the Federal Government the safe disposal of waste from nuclear power plants constitutes the precondition for their further operation. The events in the year 1987 about the conditioning and transport of low activity waste and medium activity waste made it clear that it was necessary to intensify state control and to examine the structures in the field of waste disposal. A concept for the control of radioactive waste with negligible heat development (LAW) from nuclear installations is presented. (DG) [de

Radioactive wastes

International Nuclear Information System (INIS)

Teillac, J.

1988-01-01

This study of general interest is an evaluation of the safety of radioactive waste management and consequently the preservation of the environment for the protection of man against ionizing radiations. The following topics were developed: radiation effects on man; radioactive waste inventory; radioactive waste processing, disposal and storage; the present state and future prospects [fr

Management of radioactive wastes with negligible heat generation

International Nuclear Information System (INIS)

Alter, U.

1990-01-01

In the Federal Republic of Germany only one company is responsible for the management of radioactive wastes with negligible heat generations. This is the Company for Nuclear Service (GNS mbH). It was the intention of the competent authorities of the FRG to intensify state control during conditioning, intermediate storage and transport of low- and medium level radioactive waste. A guideline provides that the responsibility of the waste producers and of those concerned with conditioning, storage and transport of radioactive waste is assigned in the individual case and that the qualitative and quantitative registration of all waste streams will be ensured. An overview of the radioactive waste management within the last two years in the FRG is presented. (orig./DG)

Leaching of radioactive waste forms under saturated and unsaturated flow conditions

International Nuclear Information System (INIS)

Petelka, M.F.

1987-01-01

To predict the environmental impact of shallow land burial sites for radioactive waste, the mobilization and migration of waste nuclides must be estimated. The theoretical understanding that in potential leaching mechanisms leach-rate variations may arise from changes in both moisture content and volumetric flow rate was tested in column flow leach experiments using labeled vermiculite particles as a simulated waste form. As far as possible, conditions of flow rate and solution ion concentration were chosen to roughly approximate expected field conditions. A modified pressure-plate apparatus was developed, tested, and found suitable for the production of steady-state unsaturated conditions with leachate flow. Water content was determined using the gamma-ray attenuation method. The effects of several parameters on leaching were studied, including moisture content and pore velocity. Pore velocity effects were found to be negligible. It was found that the leach rate depends on the fraction of the exposed waste surface that is wetted and varies with the mobile water content in a non-linear fashion. The experimental results indicate that the release rate of radionuclides placed within a properly sited low-level waste disposal site may be two to three times smaller than that predicted assuming saturated conditions. This study was performed using a homogeneous fine-grained synthetic waste form, at room temperature, with a near neutral pH leachant and oxidizing conditions

Management of small quantities of radioactive waste

International Nuclear Information System (INIS)

1998-09-01

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

Evaluation of national cements for the conditioning of radioactive wastes

International Nuclear Information System (INIS)

Mallaupoma, M.; Soriano, A.; Rodriguez, G.; Cruz, W.

1996-01-01

The preliminary research studies carried out to implement the liquid radioactive waste conditioning by cementation are described. First of all, different kind of commercial cements in Peru are analyzed. In the first step, the analysis were made without using the radioactive material. The analyzed parameters were density, porosity, setting time and mechanical strength of a cement type called 'Atlas'. Samples of two geometries were used. One of them was a cylindrical sample (48mm diameter and 48mm height) and the another one was a prismatic sample (40x40x160mm). The results of the different kind of analysis are presented in this paper. (authors). 2 refs., 3 tabs

Radioactive waste treatment technology at Czech nuclear power plants

International Nuclear Information System (INIS)

Kulovany, J.

2001-01-01

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)

Radioactive waste management

International Nuclear Information System (INIS)

Syed Abdul Malik Syed Zain

2005-01-01

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

Classification of solid wastes as non-radioactive wastes

International Nuclear Information System (INIS)

Suzuki, Masahiro; Tomioka, Hideo; Kamike, Kozo; Komatu, Junji

1995-01-01

The radioactive wastes generally include nuclear fuels, materials contaminated with radioactive contaminants or neutron activation to be discarded. The solid wastes arising from the radiation control area in nuclear facilities are used to treat and stored as radioactive solid wastes at the operation of nuclear facilities in Japan. However, these wastes include many non-radioactive wastes. Especially, a large amount of wastes is expected to generate at the decommissioning of nuclear facilities in the near future. It is important to classify these wastes into non-radioactive and radioactive wastes. The exemption or recycling criteria of radioactive solid wastes is under discussion and not decided yet in Japan. Under these circumstances, the Nuclear Safety Committee recently decided the concept on the category of non-radioactive waste for the wastes arising from decommissioning of nuclear facilities. The concept is based on the separation and removal of the radioactively contaminated parts from radioactive solid wastes. The residual parts of these solid wastes will be treated as non-radioactive waste if no significant difference in radioactivity between the similar natural materials and materials removed the radioactive contaminants. The paper describes the procedures of classification of solid wastes as non-radioactive wastes. (author)

Radioactive wastes. The groundwork of current solutions

International Nuclear Information System (INIS)

Grevoz, A.; Boullis, B.; Devezeaux de Lavergne, J.G.; Butez, M.; Bordier, G.; Vitart, X.; Hablot, I.; Chastagnet, F.

2005-01-01

Today the groundwork laid down by research has made processes available for the durable treatment and conditioning of all types of radioactive waste. This document illustrates the today situations in five presentations. Now standing as a national reference, the french inventory of radioactive waste, drawn up by ANDRA, has not only expanded to cover recoverable material but also features predictions of waste arisings for 2010 and 2020, including waste from the decommissioning of current installations. The current process used for spent fuel reprocessing allows extraction for recycling purpose, of uranium and plutonium, with very high recovery and purification rates. Advances in characterization and decontamination allow improvements in sorting and retrieval and conditioning to be considered for older wastes. The french National radioactive waste management agency (ANDRA) is already providing optimum industrial solutions for all short-lived, low and very low level waste on its Soulaines and Morvillers sites. For several decades, Areva has been reprocessing spent fuel and conditioning ultimate waste in its La Hague plants. (A.L.B.)

The radioactive waste management conference

International Nuclear Information System (INIS)

Fareeduddin, S.; Hirling, J.

1983-01-01

The international conference on radioactive waste management was held in Seattle, Washington, from 16 to 20 May 1983. The response was gratifying, reflecting world-wide interest: it was attended by 528 participants from 29 Member States of the IAEA and eight international organizations. The conference programme was structured to permit reviews and presentation of up-to-date information on five major topics: - waste management policy and its implementation: national and international approaches; legal, economic, environmental, and social aspects (four sessions with 27 papers from 16 countries and four international organizations); - handling, treatment, and conditioning of wastes from nuclear facilities, nuclear power plants and reprocessing plants, including the handling and treatment of gaseous wastes and wastes of specific types (five sessions with 35 papers); - storage and underground disposal of radioactive wastes: general, national concepts, underground laboratories, and designs of repositories for high-level, and low- and intermediate-level waste disposal (five sessions with 35 papers); - environmental and safety assessment of waste management systems: goals methodologies, assessments for geological repositories, low- and intermediate-level wastes, and mill tailings (four sessions with 26 papers); - radioactive releases to the environment from nuclear operations: status and perspectives, environmental transport processes, and control of radioactive waste disposal into the environment (three sessions with 23 papers)

Method of solidifying radioactive solid wastes

International Nuclear Information System (INIS)

Fukazawa, Tetsuo; Kawamura, Fumio; Kikuchi, Makoto.

1984-01-01

Purpose: To obtain solidification products of radioactive wastes satisfactorily and safely with no destruction even under a high pressure atmosphere by preventing the stress concentration by considering the relationships of the elastic module between the solidifying material and radioactive solid wastes. Method: Solidification products of radioactive wastes with safety and securing an aimed safety ratio are produced by conditioning the modules of elasticity of the solidifying material equal to or less than that of the radioactive wastes in a case where the elastic module of radioactive solid wastes to be solidified is smaller than that of the solidifying material (the elastic module of wastes having the minimum elastic module among various wastes). The method of decreasing the elastic module of the solidifying material usable herein includes the use of such a resin having a long distance between cross-linking points of a polymer in the case of plastic solidifying materials, and addition of rubber-like binders in the case of cement or like other inorganic solidifying materials. (Yoshihara, H.)

Radioactive waste management

International Nuclear Information System (INIS)

Blomek, D.

1980-01-01

The prospects of nuclear power development in the USA up to 2000 and the problems of the fuel cycle high-level radioactive waste processing and storage are considered. The problems of liquid and solidified radioactive waste transportation and their disposal in salt deposits and other geologic formations are discussed. It is pointed out that the main part of the high-level radioactive wastes are produced at spent fuel reprocessing plants in the form of complex aqueous mixtures. These mixtures contain the decay products of about 35 isotopes which are the nuclear fuel fission products, about 18 actinides and their daughter products as well as corrosion products of fuel cans and structural materials and chemical reagents added in the process of fuel reprocessing. The high-level radioactive waste management includes the liquid waste cooling which is necessary for the short and middle living isotope decay, separation of some most dangerous components from the waste mixture, waste solidification, their storage and disposal. The conclusion is drawn that the seccessful solution of the high-level radioactive waste management problem will permit to solve the problem of the fuel cycle radioactive waste management as a whole. The salt deposits, shales and clays are the most suitable for radioactive waste disposal [ru

Radioactive waste management in Belgium

International Nuclear Information System (INIS)

Detilleux, E.

1984-01-01

The first part of this paper briefly describes the nuclear industry in Belgium and the problem of radioactive wastes with regard to their quality and quantity. The second part emphasizes the recent guidelines regarding the management of the nuclear industry in general and the radioactive wastes in particular. In this respect, important tasks are the reinforcement of administrative structures with regard to the supervision and the control of nuclear activities, the establishment of a mixed company entrusted with the covering of the needs of nuclear plants in the field of nuclear fuels and particularly the setting up of a public autonomous and specialized organization, the 'Public Organization for the Management of Radioactive Waste and Fissile Materials', in short 'O.N.D.R.A.F.'. This organization is in charge of the management of the transport, the conditioning, the storage and the disposal of radioactive wastes. (Auth.)

Research on near-surface disposal of very low level radioactive waste

International Nuclear Information System (INIS)

Wang Shaowei; Yue Huiguo; Hou Jie; Chen Haiying; Zuo Rui; Wang Jinsheng

2012-01-01

Radioactive waste disposal is one of the most sensitive environmental problems to control and solve. As the arriving of decommissioning of early period nuclear facilities in China, large amounts of very low level radioactive waste will be produced inevitably. The domestic and abroad definitions about very low level radioactive waste and its disposal were introduced, and then siting principles of near-surface disposal of very low level radioactive waste were discussed. The near- surface disposal siting methods of very low level radioactive waste were analyzed from natural and geographical conditions assessment, geological conditions analysis, hydrogeological conditions analysis, geological hazard assessment and radioactive background investigation; the near-surface disposal sites'natural barriers of very low level radioactive waste were analyzed from the crustal structure and physico-chemical characteristics, the dynamics characteristics of groundwater, the radionuclide adsorption characteristics of natural barriers and so on; the near-surface disposal sites' engineered barriers of very low level radioactive waste were analyzed from the repository design, the repository barrier materials selection and so on. Finally, the improving direction of very low level radioactive waste disposal was proposed. (authors)

The influence of mineral additives on the mechanical performances of the conditioning matrix of radioactive waste by cementation

International Nuclear Information System (INIS)

Dragolici, F.; Rotarescu, G.; Turcanu, C.N.

1997-01-01

To improve the quality of the conditioning matrix of radioactive waste by the cementation technology, mineral additives which are diminishing the leaching rate of the radionuclides in the disposal environment are used. The studies performed until now have as an objective the obtaining of the most propitious mixture of cement and bentonite or cement and volcanic tuff, which have the mechanical properties similar to the cement paste used for the conditioning of the radioactive waste. This mixture, cement - mineral binder, in the future is required to be used at the Radioactive Waste Treatment Plant - IPNE - HH Bucharest- Magurele for the conditioning of the radioactive wastes, taking in consideration the properties of these mineral binders: very good plasticity and capacity of adsorption, which lead at the decrease of porosity. Bentonite is a clay already used in the technology of disposal as a filling material to diminish the radioactive spreading because of degradation in time of the metallic package or the intrusion of casual water. The composition of the cement - bentonite - water system is checked by the cement to water and cement to bentonite ratio, by strength and by the separated water volume. The studies show that the best mechanical performance was obtained for a cement to water ratio 10. Taking in consideration the property of bentonite to fill compactly the free spaces in the presence of water, what entails the occurrence of internal tensions in the matrix structure, which leads, in turn, to appearance of microfissures, the mixtures examined by mechanical tests had in their composition less than 10 % bentonite. For volcanic tuff, similar results were obtained using almost the same ratios. In these conditions, the results obtained allow to draw the conclusion that the adequate usage of the mineral additives do not change the resistance of the cement paste used in the conditioning of the radioactive waste. (authors)

Sanitation of conditioned radioactive waste after a contamination accident

International Nuclear Information System (INIS)

Aeppli, J.

1980-01-01

In June 1978, there occurred in the port of Ijmuiden, Netherlands, a contamination incident involving drums originating from Switzerkand and containing radioactive wastes intended to be dumped into the sea. The batch of 207 drums excluded from the sea-dumping action had to be sanitated for the next year dumping in such a manner, that these wastes met the international requirements and could be disposed of by sinking them into the Atlantic. As a consequence of extensive sanitation work, requiring part of the wastes to be newly conditioned and several drums to be packaged again, the total weight of the wastes ready for dumping was doubled. The total radiation exposure for the personnel that took part in the individual phases of sanitation amounted to about 10 man-rem. The main causes for this contamination incident were unusual chemical composition of the concentrate to be solidified, unsufficient quality control and a position not suitabble for transport. The measures taken after this incident intend to avoid similar occurrences in the future. (orig.) [de

Amount of radioactive wastes in the Federal Republic of Germany - waste survey for the year 1988

International Nuclear Information System (INIS)

Brennecke, P.; Schumacher, J.

1989-06-01

On December 31, 1988, about 69 800 waste packages - about 40 700 m 3 - were stored in interim storage facilities. The unconditioned radioactive wastes amounted to about 11 700 m 3 . The volume of the conditioned radioactive wastes amounted to about 40 700 m 3 . Of this, the waste from nuclear research centres made up about 16 300 m 3 , the waste from the operation of nuclear power plants about 12 900 m 3 and that from the reprocessing of spent fuel elements about 8 300 m 3 . A prognosis was also made of the future amount of conditioned radioactive wastes. According to this forecast, the cumulated waste package volume of radioactive wastes with negligible heat generation will be approximately in the order of 173 400 m 3 up to the year 2000, whereas for heat-generating radioactive wastes a volume of about 5 800 m 3 is estimated. These figures already express the waste volume reduction according to modern conditioning techniques. In 1988 a capacity of about 123 800 m 3 for the interim storage of radioactive wastes was available in the Federal Republic of Germany. On December 31, 1988, an average of about 37% of this capacity was utilized by unconditioned and conditioned radioactive wastes. From the data on the expected amount of radioactive wastes and on the utilization factor of the interim storage facilities, it may be concluded that, taking an overall view, no bottlenecks in the interim storage of radioactive wastes with negligible heat generation are to be anticipated up to the planned operation of the Konrad repository in 1994. (orig./HP) [de

Radioactive waste management solutions

International Nuclear Information System (INIS)

Siemann, Michael

2015-01-01

One of the more frequent questions that arise when discussing nuclear energy's potential contribution to mitigating climate change concerns that of how to manage radioactive waste. Radioactive waste is produced through nuclear power generation, but also - although to a significantly lesser extent - in a variety of other sectors including medicine, agriculture, research, industry and education. The amount, type and physical form of radioactive waste varies considerably. Some forms of radioactive waste, for example, need only be stored for a relatively short period while their radioactivity naturally decays to safe levels. Others remain radioactive for hundreds or even hundreds of thousands of years. Public concerns surrounding radioactive waste are largely related to long-lived high-level radioactive waste. Countries around the world with existing nuclear programmes are developing longer-term plans for final disposal of such waste, with an international consensus developing that the geological disposal of high-level waste (HLW) is the most technically feasible and safe solution. This article provides a brief overview of the different forms of radioactive waste, examines storage and disposal solutions, and briefly explores fuel recycling and stakeholder involvement in radioactive waste management decision making

Radioactive wastes handling facility

International Nuclear Information System (INIS)

Hirose, Emiko; Inaguma, Masahiko; Ozaki, Shigeru; Matsumoto, Kaname.

1997-01-01

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.)

Disposal of radioactive wastes

International Nuclear Information System (INIS)

Blomeke, J.O.

1979-01-01

Radioactive waste management and disposal requirements options available are discussed. The possibility of beneficial utilization of radioactive wastes is covered. Methods of interim storage of transuranium wastes are listed. Methods of shipment of low-level and high-level radioactive wastes are presented. Various methods of radioactive waste disposal are discussed

Radioactive wastes

International Nuclear Information System (INIS)

Grass, F.

1982-01-01

Following a definition of the term 'radioactive waste', including a discussion of possible criteria allowing a delimitation of low-level radioactive against inactive wastes, present techniques of handling high-level, intermediate-level and low-level wastes are described. The factors relevant for the establishment of definitive disposals for high-level wastes are discussed in some detail. Finally, the waste management organization currently operative in Austria is described. (G.G.)

Radioactive waste management

International Nuclear Information System (INIS)

Balek, V.

1994-01-01

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

Understanding radioactive waste

International Nuclear Information System (INIS)

Murray, R.L.

1981-12-01

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)

Understanding radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Murray, R.L.

1981-12-01

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)

ECOLOGICAL AND TECHNICAL REQUIREMENTS OF RADIOACTIVE WASTE UTILISATION

Directory of Open Access Journals (Sweden)

Gabriel Borowski

2013-01-01

Full Text Available The paper presents a survey of radioactive waste disposal technologies used worldwide in terms of their influence upon natural environment. Typical sources of radioactive waste from medicine and industry were presented. In addition, various types of radioactive waste, both liquid and solid, were described. Requirements and conditions of the waste’s storage were characterised. Selected liquid and solid waste processing technologies were shown. It was stipulated that contemporary methods of radioactive waste utilisation enable their successful neutralisation. The implementation of these methods ought to be mandated by ecological factors first and only then economical ones.

Amount of radioactive wastes in the Federal Republic of Germany. Waste inventory for the year 1984

International Nuclear Information System (INIS)

Brennecke, P.; Schuhmacher, J.

1986-03-01

On December 31, 1984, about 53 200 waste packages were stored in intermediate storage facilities. The unconditioned radioactive wastes amounted to about 7 000 m 3 . The volume of the conditioned radioactive wastes amounted to about 25 100 m 3 . Thereof the waste from nuclear research establishments made up about 10 000 m 3 , the waste from the operation of nuclear power plants about 7 400 m 3 and the waste from spent fuel reprocessing about 5 100 m 3 . In addition the future amount of conditioned radioactive wastes with negligible heat generation was prognosticated. Due to this forecast an amount of about 238 000 m 3 of these wastes is expected in the year 2000. In 1984 a capacity of about 87 800 m 3 for the intermediate storage of radioactive wastes was available. On December 31, 1984, this capacity was utilized by unconditioned and conditioned radioactive wastes to about 37%. It may be concluded from the data on the expected amount of radioactive wastes with negligible heat generation and on the utilization factor of the intermediate storage facilities that no bottlenecks are to be assumed up to the planned operation of the Konrad repository. (orig./HP) [de

Guidebook of radioactive wastes removal. From collection to storage

International Nuclear Information System (INIS)

2014-06-01

This document, more particularly devoted to radioactive waste producers (except electronuclear industry), defines the technical specifications relative to the taking over of their wastes by the ANDRA, the French national agency of radioactive wastes. Content: general conditions (producers liability and obligations), instructions manual of the taking over demand, non-electronuclear wastes collecting, wastes conditioning specifications, specifications for each category of waste, the lightning arresters case, specifications for particular removals with prior consent

Final disposal of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Kroebel, R [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Wiederaufarbeitung und Abfallbehandlung; Krause, H [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Abt. zur Behandlung Radioaktiver Abfaelle

1978-08-01

This paper discusses the final disposal possibilities for radioactive wastes in the Federal Republic of Germany and the related questions of waste conditioning, storage methods and safety. The programs in progress in neighbouring CEC countries and in the USA are also mentioned briefly. The autors conclude that the existing final disposal possibilities are sufficiently well known and safe, but that they could be improved still further by future development work. The residual hazard potential of radioactive wastes from fuel reprocessing after about 1000 years of storage is lower that of known inorganic core deposits.

Radioactive waste management: International peer reviews

International Nuclear Information System (INIS)

Warnecke, E.; Bonne, A.

1995-01-01

The Agency's peer review service for radioactive waste management - known as the Waste Management Assessment and Technical Review Programme (WATRP) - started in 1989, building upon earlier types of advisory programmes. WATRP's international experts today provide advice and guidance on proposed or ongoing radioactive waste management programmes; planning, operation, or decommissioning of waste facilities; or on legislative, organizational, and regulatory matters. Specific topics often cover waste conditioning, storage, and disposal concepts or facilities; or technical and other aspects of ongoing or planned research and development programmes. The missions can thus contributed to improving waste management systems and plans, and in raising levels of public confidence in them, as part of IAEA efforts to assist countries in the safe management of radioactive wastes. This article presents a brief overview of recent WATRP missions in Norway, Slovak Republic, Czech Republic and Finland

Problems of control of radioactive waste

International Nuclear Information System (INIS)

Doi, Kazumi

2000-01-01

The isolation period of high level radioactive waste from human biotope is some ten thousand years or more. Especially, many crustal movement zones are located in our country, so that very careful measures should be taken. Isolation of high level radioactive waste in lithosphere needs to confirm good isolation site. Boring is a chief method to determine the location conditions for radioactive waste. In order to study crack of rock and behavior of groundwater, high density of drilling must be necessary. However, high density drilling should be avoided. In place of it, a geophysical exploration is an ideal method, one of non-destructive inspection. It is important for many countries to establish the technologies to determine the conditions of crack and groundwater by this method. A large amount of data about the contact condition of radionuclide and minerals, pH, oxidative-reduction potential and temperature are needed. (S.Y.)

Radioactive waste management at nuclear power plant Cernavoda

International Nuclear Information System (INIS)

Raducea, D.

2002-01-01

Many human activities generate waste, but people are worried about wastes produced in nuclear power plants (NPPs). Their concern is an unjustified fear toward the hazards from radioactive waste, probably because in any country generating electric power by NPPs a lot of attention is paid to relevant parties involved in radioactive waste management. Significant attention is also given to the management of radioactive waste at the Cemavoda NPP. The general approach required for the collection, handling, conditioning and storage of radioactive wastes, while maintaining acceptable levels of safety for workers, members of the public and the environment, is conceptually established. The overall programme provides the necessary facilities to adequately manage solid radioactive waste from Cemavoda NPP Unit 1 and will be capable of expansion when other units are brought into service. (author)

Radioactive waste containment

International Nuclear Information System (INIS)

Beranger, J.-C.

1978-01-01

The problem of confining the radioactive wastes produced from the nuclear industry, after the ore concentration stage, is envisaged. These residues being not released into the environment are to be stored. The management policy consists in classifying them in view of adapting to each type of treatment, the suitable conditioning and storage. This classification is made with taking account of the following data: radioactivity (weak, medium or high) nature and lifetime of this radioactivity (transuranians) physical nature and volume. The principles retained are those of volume reduction and shaping into insoluble solids (vitrification) [fr

Selection of appropriate conditioning matrices for the safe disposal of radioactive waste

International Nuclear Information System (INIS)

Vance, E.R.

2002-01-01

The selection of appropriate solid conditioning matrices or wasteforms for the safe disposal of radioactive waste is dictated by many factors. The overriding issue is that the matrix incorporating the radionuclides, together with a set of engineered barriers in a near-surface or deep geological repository, should prevent significant groundwater transport of radionuclides to the biosphere. For high-level waste (HLW) from nuclear fuel reprocessing, the favored matrices are glasses, ceramics and glass-ceramics. Borosilicate glasses are presently being used in some countries, but there are strong scientific arguments why ceramics based on assemblages of natural minerals are advantageous for HLW. Much research has been carried out in the last 40 years around the world, and different matrices are more suitable than others for a given waste composition. However a major stumbling block for HLW immobilisation is the mall number of approved geological repositories for such matrices. The most appropriate matrices for Intermediate and low-level wastes are contentious and the selection criteria are not very well defined. The candidate matrices for these latter wastes are cements, bitumen, geopolymers, glasses, glass-ceramics and ceramics. After discussing the pros and cons of various candidate matrices for given kinds of radioactive wastes, the SYNROC research program at ANSTO will be briefly surveyed. Some of the potential applications of this work using a variety of SYNROC derivatives will be given. Finally the basic research program at ANSTO on radioactive waste immobilisation will be summarised. This comprises mainly work on solid state chemistry to understand ionic valences and co-ordinations for the chemical design of wasteforms, aqueous durability to study the pH and temperature dependence of solid-water reactions, radiation damage effects on structure and solid-water reactions. (Author)

Non-fuel cycle radioactive waste policy in Turkey

International Nuclear Information System (INIS)

Demirel, H.

2003-01-01

Radioactive wastes generated in Turkey are mostly low level radioactive waste generated from the operation of one research reactor, research centers and universities, hospitals, and from radiological application of various industries. Disused sealed sources which potentially represent medium and high radiological risks in Turkey are mainly Am-241, Ra-226, Kr-85, Co-60, Ir-192 and Cs-137. All radioactive waste produced in Turkey is collected, segregated, conditioned and stored at CWPSF. Main components of the facility are listed below: Liquid waste is treated in chemical processing unit where precipitation is applied. Compactable solids are compressed in a compaction cell. Spent sources are embedded into cement mortar with their original shielding. If the source activities are in several millicuries, sometimes dismantling is applied and segregated sources are conditioned in shielded drums. Due to increasing number of radiation and nuclear related activities, the waste facility of CNAEM is now becoming insufficient to meet the storage demand of the country. TAEA is now in a position to establish a new radioactive waste management facility and studies are now being carried out on the selection of best place for the final storage of processed radioactive wastes. Research and development studies in TAEA should continue in radioactive waste management with the aim of improving data, models, and concepts related to long-term safety of disposal of long-lived waste

Radioactive waste disposal

International Nuclear Information System (INIS)

Cluchet, J.; Roger, B.

1975-10-01

After mentioning the importance of the problem of the disposal of wastes produced in the electro-nuclear industry, a short reminder on a few laws of radioactivity (nature and energy of radiations, half-life) and on some basic dosimetry is given. The conditioning and storage procedures are then indicated for solid wastes. The more active fractions of liquid wastes are incorporated into blocks of glass, whereas the less active are first concentrated by chemical treatments or by evaporation. The concentrates are then embedded into concrete, asphalt or resins. Storage is done according to the nature of each type of wastes: on a hard-surfaced area or inside concrete-lined trenches for the lowest radioactivity, in pits for the others. Transuranium elements with very long half-lives are buried in very deep natural cavities which can shelter them for centuries. From the investigations conducted so far and from the experience already gained, it can be concluded that safe solutions are within our reach [fr

Low-level Radioactive waste Management

International Nuclear Information System (INIS)

1991-01-01

This meeting describes low-level radioactive waste management problems and contains 8 papers: 1 Low-level radioactive waste management: exemption concept and criteria used by international organizations. 2 Low-level radioactive waste management: french and foreign regulations 3 Low-level radioactive waste management in EDF nuclear power plants (FRANCE) 4 Low-level radioactive waste management in COGEMA (FRANCE) 5 Importance of low-level radioactive wastes in dismantling strategy in CEA (FRANCE) 6 Low-level radioactive waste management in hospitals 7 Low-level radioactive waste disposal: radiation protection laws 8 Methods of low-level radioactive materials measurements during reactor dismantling or nuclear facilities demolition (FRANCE)

Radioactive waste management at AECL

International Nuclear Information System (INIS)

Gadsby, R.D.; Allan, C.J.

2003-01-01

AECL has maintained an active program in radioactive waste management since 1945, when the Canadian nuclear program commenced activities at the Chalk River Laboratories (CRL). Waste management activities have included operation of waste management storage and processing facilities at AECL's CRL and Whiteshell Laboratories (WL); operation of the Low Level Radioactive Waste Management Office on behalf of Natural Resources Canada to resolve historic radioactive waste problems (largely associated with radioactive ore recovery, transport and processing operations) that are the responsibility of the Federal Government; development of the concept and related technology for geological disposal of Canada's nuclear fuel waste; development of the Intrusion-Resistant Underground Structure (IRUS) disposal concept for low-level nuclear waste; development of dry storage technology for the interim storage of used fuel; and development and assessment of waste processing technology for application in CANDU nuclear power plants and at CRL and WL. Today these activities are continuing. In addition, AECL is: preparing to decommission the nuclear facilities at WL; carrying out a number of smaller decommissioning projects at CRL; putting in place projects to upgrade the low-level liquid waste processing capabilities of the CRL Waste Treatment Centre, recover and process highly active liquid wastes currently in storage, and recover, condition and improve the storage of selected fuel wastes currently stored in below-ground standpipes in the CRL waste management areas; and assessing options for additional remediation projects to improve the management of other wastes currently in storage and to address environmental contamination from past practices. (author)

Radioactive waste processing

International Nuclear Information System (INIS)

Dejonghe, P.

1978-01-01

This article gives an outline of the present situation, from a Belgian standpoint, in the field of the radioactive wastes processing. It estimates the annual quantity of various radioactive waste produced per 1000 MW(e) PWR installed from the ore mining till reprocessing of irradiated fuels. The methods of treatment concentration, fixation, final storable forms for liquid and solid waste of low activity and for high level activity waste. The storage of radioactive waste and the plutonium-bearing waste treatement are also considered. The estimated quantity of wastes produced for 5450 MW(e) in Belgium and their destination are presented. (A.F.)

Optimalization studies concerning volume reduction and conditioning of radioactive waste in view of storage and disposal (geological disposal into clay)

International Nuclear Information System (INIS)

Dejonghe, P.; Van De Voorde, N.; Bonne, A.

1984-01-01

Volume reduction of low-level and medium-level wastes, and simultaneous optimization of the quality of the conditioned end-product is a major challenge in the management of radioactive wastes. Comments will be given on recent achievements in treatment of non-high-level liquid and solid wastes from power reactors and low-level plutonium contaminated wastes. The latter results can contribute to an overall optimization of a radioactive waste management scheme, including the final disposal of the conditioned materials. Some detailed results will be given concerning volume reduction, decontamination factors, degree of immobilization of the contained radioelements, and cost considerations

Safety disposal studies of radioactive and hazardous wastes using cement

International Nuclear Information System (INIS)

Aly, M.M.E.

2000-01-01

radioactive waste is generated from the production of nuclear energy and from the use of radioactive materials applications, agriculture and medicine. the important of safe management of radioactive waste for the protection of human health and the environment has long been recognized. conditioning of radioactive waste is the transform of radioactive waste into a suitable form for storage and disposal. common immobilization methods include solidification of low radioactive waste in cement or bitumen.in order to improve cement properties to decrease the release of liquid radioactive waste into the environment and its dispersion to a level where the risks to individuals, population and the environment

Radioactive wastes of Nuclear Industry

International Nuclear Information System (INIS)

1995-01-01

This conference studies the radioactive waste of nuclear industry. Nine articles and presentations are exposed here; the action of the direction of nuclear installations safety, the improvement of industrial proceedings to reduce the waste volume, the packaging of radioactive waste, the safety of radioactive waste disposal and environmental impact studies, a presentation of waste coming from nuclear power plants, the new waste management policy, the international panorama of radioactive waste management, the international transport of radioactive waste, finally an economic analysis of the treatment and ultimate storage of radioactive waste. (N.C.)

Amount of radioactive wastes in the Federal Republic of Germany - waste inquiry for the year 1985

International Nuclear Information System (INIS)

Brennecke, P.; Schumacher, J.

1986-09-01

On December 31, 1985, about 61 400 waste packages were stored in intermediate storage facilities. The unconditioned radioactive wastes amounted to about 6 300 m 3 . The volume of the conditioned radioactive wastes amounted to about 29 600 m 3 . Thereof the waste from nuclear research establishments made up about 11 200 m 3 , the waste from the operation of nuclear power plants about 9 900 m 3 and the waste from reprocessing of spent fuel elements about 5 800 m 3 . In addition the future amount of conditioned radioactive wastes with negligible heat generation was prognosticated. Due to this forecast an amount of about 227 600 m 3 of these wastes is expected in the year 2000. In 1985 a capacity of about 88 700 m 3 for the intermediate storage of radioactive wastes was available in the Federal Republic of Germany. On December 31, 1985, this capacity was utilized by unconditioned and conditioned radioactive wastes at an average of about 40%. It may be concluded from the data on the expected amount of radioactive wastes with negligible heat generation and on the utilization factor of the intermediate storage facilities that no bottlenecks are to be assumed up to the planned operation of the Konrad repository. (orig./HP) [de

Yield of radioactive wastes in the Federal Republic of Germany - waste survey for the year 1986

International Nuclear Information System (INIS)

Brennecke, P.; Schumacher, J.

1987-05-01

On December 31, about 67600 waste packages were stored in interim storage facilities. The unconditioned radioactive wastes amounted to about 6600 m 3 . The volume of the conditioned radioactive wastes amounted to about 33900 m 3 . Thereof the waste from nuclear research establishments made up about 13300 m 3 , the waste from the operation of nuclear power plants about 10700 m 3 and the waste from reprocessing of spent fuel elements about 6700 m 3 . In addition the future amount of conditioned radioactive wastes with negligible heat generation was prognosticated. According to this forecast, the waste package volume will be approximately in the order of 218200 m 3 up to the year 2000. In 1986 a capacity of about 97500 m 3 for the interim storage of radioactive wastes was available in the Federal Republic of Germany. On December 31, 1986, this capacity was utilized by unconditioned and conditioned radioactive wastes at an average of about 38%. It may be concluded from the data on the expected amount of radioactive wastes with negligible heat generation and on the utilization factor of the interim storage facilities that no bottlenecks are to be assumed up to the planned operation of the Konrad repository. (orig./RB) [de

Radioactive Waste in Perspective

International Nuclear Information System (INIS)

2011-01-01

Large volumes of hazardous wastes are produced each year, however only a small proportion of them are radioactive. While disposal options for hazardous wastes are generally well established, some types of hazardous waste face issues similar to those for radioactive waste and also require long-term disposal arrangements. The objective of this NEA study is to put the management of radioactive waste into perspective, firstly by contrasting features of radioactive and hazardous wastes, together with their management policies and strategies, and secondly by examining the specific case of the wastes resulting from carbon capture and storage of fossil fuels. The study seeks to give policy makers and interested stakeholders a broad overview of the similarities and differences between radioactive and hazardous wastes and their management strategies. Contents: - Foreword; - Key Points for Policy Makers; - Executive Summary; - Introduction; - Theme 1 - Radioactive and Hazardous Wastes in Perspective; - Theme 2 - The Outlook for Wastes Arising from Coal and from Nuclear Power Generation; - Risk, Perceived Risk and Public Attitudes; - Concluding Discussion and Lessons Learnt; - Strategic Issues for Radioactive Waste; - Strategic Issues for Hazardous Waste; - Case Studies - The Management of Coal Ash, CO 2 and Mercury as Wastes; - Risk and Perceived Risk; - List of Participants; - List of Abbreviations. (authors)

The conceptual design of waste repository for radioactive waste from medical, industrial and research facilities containing comparatively high radioactivity

International Nuclear Information System (INIS)

Yamamoto, Masayuki; Hashimoto, Naro

2002-02-01

Advisory Committee on Nuclear Fuel Cycle Backend Policy reported the basic approach to the RI and Institute etc. wastes on March 2002. According to it, radioactive waste form medical, industrial and research facilities should be classified by their radioactivity properties and physical and chemical properties, and should be disposed in the appropriate types of repository with that classification. For the radioactive waste containing comparatively high radioactivity generated from reactors, NSC has established the Concentration limit for disposal. NSC is now discussing about the limit for the radioactive waste from medical, industrial and research facilities containing comparatively high radioactivity. Japan Nuclear Cycle Development Institute (JNC) preliminary studied about the repository for radioactive waste from medical, industrial and research facilities and discussed about the problems for design on H12. This study was started to consider those problems, and to develop the conceptual design of the repository for radioactive waste from medical, industrial and research facilities. Safety assessment for that repository is also performed. The result of this study showed that radioactive waste from medical, industrial and research facilities of high activity should be disposed in the repository that has higher performance of barrier system comparing with the vault type near surface facility. If the conditions of the natural barrier and the engineering barrier are clearer, optimization of the design will be possible. (author)

Radioactive waste management and disposal in Australia

International Nuclear Information System (INIS)

Harries, J.R.

1997-01-01

A national near-surface repository at a remote and arid location is proposed for the disposal of solid low-level and short-lived intermediate-level radioactive wastes in Australia. The repository will be designed to isolate the radioactive waste from the human environment under controlled conditions and for a period long enough for the radioactivity to decay to low levels. Compared to countries that have nuclear power programs, the amount of waste in Australia is relatively small. Nevertheless, the need for a national disposal facility for solid low-level radioactive and short-lived intermediate-level radioactive wastes is widely recognised and the Federal Government is in the process of selecting a site for a national near-surface disposal facility for low and short-lived intermediate level wastes. Some near surface disposal facilities already exist in Australia, including tailings dams at uranium mines and the Mt Walton East Intractable Waste Disposal Facility in Western Australia which includes a near surface repository for low level wastes originating in Western Australia. 7 refs, 1 fig., 2 tabs

Radioactive waste management: Spanish experiences

International Nuclear Information System (INIS)

Beceiro, A. R.

1996-01-01

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)

Issues in radioactive waste disposal. Second report of the working group on principles and criteria for radioactive waste disposal

International Nuclear Information System (INIS)

1996-10-01

This report discusses issues related to long time-scale underground disposal of radioactive wastes. The chapters are devoted to the following issues: (1) Post closure issues of underground repositories, e.g., record keeping and markers, public reassurance and prevention of misuse; (2) Optimization of radiation protection by optimizing radioactive waste management, siting analysis, repository design etc.; (3) An interface between nuclear safeguards and radioactive waste management by safeguarding conditioning of spent fuel, during operational phase of repository and post-closure phase of the repository. 31 refs

Treatment and conditioning of low-level radioactive waste in Belgium: initial operating results of the Cilva facility

International Nuclear Information System (INIS)

Monsch, O.; Renard, C.; Deckers, J.; Luycx, P.

1995-01-01

The Belgian National Radioactive Waste and Enriched Fissile Material Agency (ONDRAF), which is responsible for the management of all radioactive waste in Belgium, recently decided to commission the CILVA facility. Operation of this facility, which comprises a number of units for the treatment of low-level radwaste, has been contracted to ONDRAF's Belgoprocess subsidiary based at the Dessel site. A consortium comprising SGN and Fabricom was in charge of building the CILVA facility's waste preparation and conditioning (concrete solidification) units. The concrete solidification processes, which were devised and developed by SGN, have been qualified to secure ONDRAF certification of the process and the facility. This enabled active commissioning of the waste conditioning unit in mid-August 1994. Active commissioning of the waste preparation unit was carried out in several stages up to the beginning of 1995 in accordance with operating requirements. Initial operating results of the two units are presented. (author)

Radioactive waste handling at the Mochovce NPP, 1998-2008

International Nuclear Information System (INIS)

Vasickova, Gabriela

2009-01-01

The radioactive waste management system at the Mochovce NPP is described. The system addresses technical aspects as well as administrative provisions related to radioactive waste generated within the controlled area, from the waste generation phase to waste sorting, packaging, storage, recording, measurement, and transportation to the Bohunice waste processing facility or transfer to the Mochovce liquid radioactive waste treatment facility. The article also addresses conditions for release from the controlled area to the environment for radioactive waste which can be exempt from the institutional administrative control system or released to the environment on the basis of a valid permission issued by the relevant regulatory authority

Radioactive wastes transport. A safety logic

International Nuclear Information System (INIS)

2005-01-01

The safety principle which applies to transport operations of radioactive wastes obeys to a very strict regulation. For the conditioning of wastes in package, the organisation of shipments and the qualification of carriers, the ANDRA, the French national agency of radioactive wastes, has implemented a rigorous policy based on the respect of a quality procedure and on the mastery of delivery fluxes. This brochure presents in a simple, illustrated and detailed manner the different steps of these transports. (J.S.)

Immersed radioactive wastes

International Nuclear Information System (INIS)

2017-03-01

This document presents a brief overview of immersed radioactive wastes worldwide: historical aspects, geographical localization, type of wastes (liquid, solid), radiological activity of immersed radioactive wastes in the NE Atlantic Ocean, immersion sites and monitoring

Acceptance criteria for disposal of radioactive waste in Romania

International Nuclear Information System (INIS)

Dogaru, D.

2001-01-01

In Romania the institutional radioactive waste are managed by National Institute of R and D for Physics and Nuclear Engineering. The institutional radioactive waste are collected, treated and conditioned at the Radioactive Waste Treatment Plant then transferred and disposed to the National Repository of Radioactive Waste at Baita Bihor. National Repository for Radioactive Waste is a long term storage facility. The repository is placed in a former worked out uranium ore mine, being excavated in the Bihor peak. The repository has been sited taking into account the known geological, hydrogeoloical, seismic and meteorological and mining properties of a uranium mining site. In the absence of an updated Safety Analysis Report, the maximum radioactive content permitted by the regulatory authority in the operation license is below the values reported for other engineered repositories in mine galleries. The paper presents the acceptance criteria for disposal of radioactive waste in National Repository for Radioactive Waste at Baita Bihor. (author)

The management of radioactive wastes from small producers

International Nuclear Information System (INIS)

1996-01-01

Medicine, research and industry generate various type of radioactive wastes which have to be managed by the ANDRA, the French agency for the management of radioactive wastes. This educative booklet explains the missions of the ANDRA with respect to these small producers: collection, selection, conditioning, control and storage of wastes. (J.S.)

China's status and strategy of radioactive waste management

International Nuclear Information System (INIS)

Bi Decai

2001-01-01

China has a forty-year history of nuclear industry and nuclear technology application. Safety management of radioactive wastes has been the great concern of related regulatory authorities. After the national policy on regional disposal for low and intermediate level radioactive waste was enacted in 1992, the management of radioactive wastes gradually focused on disposal. Currently, the strategies for radioactive waste management in China are: (a) storing high level radioactive wastes temporarily and launching the study of vitrification and deep geological disposal of high level liquid waste, treating spent fuels from PWR by reprocessing; (b) implementing regional disposal policy for low and intermediate level wastes, implementing cement solidification for low and intermediate level liquid waste before disposal, carrying out bulk casting shallow land disposal technology and hydraulic-fractured cement solidification for deep geological disposal in some special regions under specific conditions, treating low and intermediate level solid radioactive wastes by cement solidification after incineration or by compressing before final disposal; (c) stabilizing the tailing repository by reinforcing embankment, constructing flood dam and overlaying plantation; and (d) developing and formulating laws, regulations, and standards to ensure safe management of radioactive wastes. When establishing standards, other than to follow the generic principles and requirements, emphasis should be placed on the following principles: safety the first, economy, disposal of radioactive wastes as focus, and introduction of international advanced standards as possible. (author)

Behavior of radioactive metal surrogates under various waste combustion conditions

International Nuclear Information System (INIS)

Yang, Hee Chul; Lee, Jae Hee; Kim, Jung Guk; Yoo, Jae Hyung; Kim, Joon Hyung

2002-01-01

A laboratory investigation of the behavior of radioactive metals under the various waste combustion atmospheres was conducted to predict the parameters that influence their partitioning behavior during waste incineration. Neodymium, samarium, cerium, gadolinium, cesium and cobalt were used as non-radioactive surrogate metals that are representative of uranium, plutonium, americium, curium, radioactive cesium, and radioactive cobalt, respectively. Except for cesium, all of the investigated surrogate metal compounds converted into each of their stable oxides at medium temperatures from 400 to 900 .deg. C, under oxygen-deficient and oxygen-sufficient atmospheres (0.001-atm and 0.21-atm O 2 ). At high temperatures above 1,400 .deg. C, cerium, neodymium and samarium in the form of their oxides started to vaporize but the vaporization rates were very slow up to 1500 .deg. C. Inorganic chlorine (NaCl) as well as organic chlorine (PVC) did not impact the volatility of investigated Nd 2 O 3 , CoO and Cs 2 O. The results of laboratory investigations suggested that the combustion chamber operating parameters affecting the entrainment of particulate and filtration equipment operating parameters affecting particle collection efficiency be the governing parameters of alpha radionuclides partitioning during waste incineration

Outline of the radioactive waste management strategy at the national radioactive waste disposal facility 'Ekores'

International Nuclear Information System (INIS)

Rozdyalovskaya, L.F.; Tukhto, A.A.; Ivanov, V.B.

2000-01-01

The national Belarus radioactive waste disposal facility 'Ekores' was started in 1964 and was designed for radioactive waste coming from nuclear applications in industry, medicine and research. It is located in the neighbourhood of Minsk (2 Mil. people) and it is the only one in this country. In 1997 the Government initiated the project for the facility reconstruction. The main reconstruction goal is to upgrade radiological safety of the site by creating adequate safety conditions for managing radioactive waste at the Ekores disposal facility. This covers modernising technologies for new coming wastes and also that the wastes currently disposed in the pits are retrieved, sorted and treated in the same way as new coming wastes. The reconstruction project developed by Belarus specialists was reviewed by the IAEA experts. The main provisions of the revised project strategy are given in this paper. The paper's intention is to outline the technical measures which may be taken at standard 'old type Soviet Radon' disposal facility so as to ensure the radiological safety of the site. (author)

Management of Radioactive Wastes

International Nuclear Information System (INIS)

Tchokosa, P.

2010-01-01

Management of Radioactive Wastes is to protect workers and the public from the radiological risk associated with radioactive waste for the present and future. It application of the principles to the management of waste generated in a radioisotope uses in the industry. Any material that contains or is contaminated with radionuclides at concentrations or radioactivity levels greater than ‘exempt quantities’ established by the competent regulatory authorities and for which no further use is foreseen or intended. Origin of the Radioactive Waste includes Uranium and Thorium mining and milling, nuclear fuel cycle operations, Operation of Nuclear power station, Decontamination and decommissioning of nuclear facilities and Institutional uses of isotopes. There are types of radioactive waste: Low-level Waste (LLW) and High-level Waste. The Management Options for Radioactive Waste Depends on Form, Activity, Concentration and half-lives of the radioactive waste, Storage and disposal methods will vary according to the following; the radionuclides present, and their concentration, and radio toxicity. The contamination results basically from: Contact between radioactive materials and any surface especially during handling. And it may occur in the solid, liquid or gas state. Decontamination is any process that will either reduce or completely remove the amount of radionuclides from a contaminated surface

Radioactive waste management

International Nuclear Information System (INIS)

1992-01-01

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

Proposal of threshold levels for the definition of non-radioactive wastes

International Nuclear Information System (INIS)

Yoshida, Yoshikazu

1979-01-01

With increasing amounts of radioactive wastes along with the advances of nuclear power generation and radioactive material utilizations, the needs for management cost reduction and resource saving have arisen. Under the situation, the threshold levels for the definition of non-radioactive solid wastes are required. The problem has been studied by an ad hoc committee in Nuclear Safety Research Association, by the request of the Science and Technology Agency. The matters described are the procedures of deriving the threshold levels, the feasibility studies of the management of waste threshold-level with several enterprises, and future subjects of study. The threshold levels are grouped in two, i.e. the unconditional level and the conditional level. According to the unconditional threshold level, solid wastes are separated definitely into radioactive and non-radioactive ones. According to the conditional threshold level, under certain conditions, some radioactive solid wastes according to the unconditional level are regarded as non-radioactive ones. (J.P.N.)

Dynamics of radioactive waste generation

International Nuclear Information System (INIS)

Dogaru, Daniela; Virtopeanu, Cornelia; Ivan, Alexandrina

2008-01-01

In Romania there are in operation three facilities licensed for collection, treatment and storage of radioactive waste resulted from industry, research, medicine, and agriculture, named institutional radioactive waste. The repository, which is of near surface type, is designed for disposing institutional radioactive waste. The institutional radioactive wastes generated are allowed to be disposed into repository according to the waste acceptance criteria, defined for the disposal facility. The radioactive wastes which are not allowed for disposal are stored on the site of each facility which is special authorised for this. The paper describes the dynamics of generation of institutional waste in Romania, both for radioactive waste which are allowed to be disposed into repository and for radioactive waste which are not allowed to be disposed of. (authors)

Controlling radioactive waste

International Nuclear Information System (INIS)

Wurtinger, W.

1992-01-01

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.) [de

2009 National inventory of radioactive material and wastes. Descriptive catalogue of waste types

International Nuclear Information System (INIS)

2009-01-01

The various types of radioactive wastes (produced or to be produced in France) are presented. Each radioactive waste family (i.e. having analogous characteristics) is described, with a thorough information on their general characteristics, their localization in France, the waste management process, and details on their origin and owner, state of production, volume and conditioning, etc. Data are given concerning produced quantities and radioactivity levels at the end of 2007 (with forecasts for 2020 and 2030), mean package radioactivity, presence of possibly toxic chemicals, etc

Geological storage of radioactive waste

International Nuclear Information System (INIS)

Barthoux, A.

1983-01-01

Certain radioactive waste contains substances which present, although they disappear naturally in a progressive manner, a potential risk which can last for very long periods, of over thousands of years. To ensure a safe long-term handling, provision has been made to bury it deep in stable geological structures which will secure its confinement. Radioactive waste is treated and conditioned to make it insoluble and is then encased in matrices which are to immobilize them. The most radioactive waste is thus incorporated in a matrix of glass which will ensure the insulation of the radioactive substances during the first thousands of years. Beyond that time, the safety will be ensured by the properties of the storage site which must be selected from now on. Various hydrogeological configurations have been identified. They must undergo detailed investigations, including even the creation of an underground laboratory. This document also presents examples of underground storage installations which are due to be built [fr

Aspects of radioactive waste management

International Nuclear Information System (INIS)

Cutoiu, Dan

2003-01-01

The origin and types of radioactive waste, the objective and the fundamental principles of radioactive waste management and the classification of radioactive waste are presented. Problems of the radioactive waste management are analyzed. (authors)

Low-level radioactive waste disposal: radiation protection laws

International Nuclear Information System (INIS)

Chapuis, A.M.; Guetat, P.; Garbay, H.

1991-01-01

The politics of radioactive waste management is a part of waste management and activity levels are one of the components of potential waste pollutions in order to assume man and environment safety. French regulations about personnel and public' radiation protection defines clearly the conditions of radioactive waste processing, storage, transport and disposal. But below some activity levels definite by radiation protection laws, any administrative procedures or processes can be applied for lack of legal regulations. So regulations context is not actually ready to allow a rational low-level radioactive waste management. 15 refs.; 4 tabs.; 3 figs

Transport of radioactive wastes

International Nuclear Information System (INIS)

Stuller, C.

2003-01-01

In this article author describes the system of transport and processing of radioactive wastes from nuclear power of Slovenske elektrarne, plc. It is realized the assurance of transport of liquid and solid radioactive wastes to processing links from places of their formation, or of preliminary storage and consistent transports of treated radioactive wastes fixed in cement matrix of fibre-concrete container into Rebublic storage of radioactive wastes in Mochovce

Optimization of concrete composition in radioactive waste management

International Nuclear Information System (INIS)

Plecas, I.; Peric, A.

1995-01-01

Low and intermediate level waste represents 95% of the total wastes that is conditioned into special concrete containers. Since these containers are to protect radioactive waste safely for about 300 years, the selection and precise control of physical and mechanical characteristics of materials is very important. After volume reduction and valuable components recovery, waste materials have to be conditioned for transport, storage and disposal. Conditioning is the waste management step in which radioactive wastes are immobilized and packed. The immobilization processes involve conversation of the wastes to solid forms that reduce the potential for migration or dispersion of radionuclides from the wastes by natural processes during storage, transport and disposal. The immobilization processes involve the use of various matrices of nonradioactive materials, such as concrete, to fix the wastes as monoliths, usually directly in the waste containers used for subsequent handling. In this paper an optimization of concrete container composition, used for storing radioactive waste from nuclear power plants, is presented. Optimization was performed on the composition of the concrete that is used in the container production. In experiments, the authors tried to obtain the best mechanical characteristics of the concrete, varying the weight percentage of the granulate due to its diameter, water-to-cement ratios and type of the cements that were used in preparing the concrete container formulation. Concrete containers, that were optimized in the manner described in this paper, will be in used for the radioactive waste materials final disposal, using the concept of the engineer trench system facilities

Infrared thermography applied to monitoring of radioactive waste drums

International Nuclear Information System (INIS)

Kelmer, P.; Camarano, D.M.; Calado, F.; Phillip, B.; Viana, C.; Andrade, R.M.

2013-01-01

The use of thermography in the inspection of drums containing radioactive waste is being stimulated by the absence of physical contact. In Brazil the majority of radioactive wastes are compacted solids packed in metal drums stored temporarily for decades and requires special attention. These drums have only one qualitative indication of the radionuclides present. However, its structural condition is not followed systematically. The aim of this work is presents a methodology by applying thermography for monitoring the structural condition of drums containing radioactive waste in order to detect degraded regions of the drums. (author)

Treatment and conditioning of radioactive organic liquids

International Nuclear Information System (INIS)

1992-07-01

Liquid organic radioactive wastes are generated from the use of radioisotopes in nuclear research centres and in medical and industrial applications. The volume of these wastes is small by comparison with aqueous radioactive wastes, for example; nevertheless, a strategy for the effective management of these wastes is necessary in order to ensure their safe handling, processing, storage and disposal. A aqueous radioactive wastes may be discharged to the environment after the radioactivity has decayed or been removed. By contrast, organic radioactive wastes require management steps that not only take account of their radioactivity, but also of their chemical content. This is because both the radioactivity and the organic chemical nature can have detrimental effects on health and the environment. Liquid radioactive wastes from these applications typically include vacuum pump oil, lubricating oil and hydraulic fluids, scintillation cocktails from analytical laboratories, solvents from solvent extraction research and uranium refining, and miscellaneous organic solvents. The report describes the factors which should be considered in the development of appropriate strategies for managing this class of wastes from generation to final disposal. Waste sources and characterization, treatment and conditioning processes, packaging, interim storage and the required quality assurance are all discussed. The report is intended to provide guidance to developing Member States which do not have nuclear power generation. A range of processes and procedures is presented, though emphasis is given to simple, easy-to-operate processes requiring less sophisticated and relatively inexpensive equipment. 31 refs, 16 figs, 3 tabs

Evaluation of an external exposure of a worker during manipulation with waste packages stored in Bohunice radioactive waste treatment centre

International Nuclear Information System (INIS)

Slimak, A.; Hrncir, T.; Necas, V.

2012-01-01

The paper briefly describes current state of radioactive waste management as well as radioactive waste treatment and conditioning technologies used in Bohunice Radioactive Waste Treatment Centre. Radioactive Waste management includes pretreatment, treatment, conditioning, storage, transport and disposal of radioactive waste. Presented paper deals with the evaluation of an external exposure of a worker during manipulation with fibre-reinforced concrete container stored under shelter object. The external exposure of a worker was evaluated using VISIPLAN 3D ALARA code. (Authors)

Radioactive waste management and regulation

International Nuclear Information System (INIS)

Willrich, M.; Lester, R.K.; Greenberg, S.C.; Mitchell, H.C.; Walker, D.A.

1977-01-01

Purpose of this book is to assist in developing public policy and institutions for the safe management of radioactive waste, currently and long term. Both high-level waste and low-level waste containing transuranium elements are covered. The following conclusions are drawn: the safe management of post-fission radioactive waste is already a present necessity and an irreversible long-term commitment; the basic goals of U.S. radioactive waste policy are unclear; the existing organization for radioactive waste management is likely to be unworkable if left unchanged; and the existing framework for radioactive waste regulation is likely to be ineffective if left unchanged. The following recommendations are made: a national Radioactive Waste Authority should be established as a federally chartered public corporation; with NRC as the primary agency, a comprehensive regulatory framework should be established to assure the safety of all radioactive waste management operations under U.S. jurisdiction or control; ERDA should continue to have primary government responsibility for R and D and demonstration of radioactive waste technology; and the U.S. government should propose that an international Radioactive Waste Commission be established under the IAEA

ANSTO's radioactive waste management policy. Preliminary environmental review

International Nuclear Information System (INIS)

Levins, D.M.; Airey, P.; Breadner, B.; Bull, P.; Camilleri, A.; Dimitrovski, L.; Gorman, T.; Harries, J.; Innes, R.; Jarquin, E.; Jay, G.; Ridal, A.; Smith, A.

1996-05-01

For over forty years, radioactive wastes have been generated by ANSTO (and its predecessor, the AAEC) from the operation of nuclear facilities, the production of radioisotopes for medical and industrial use, and from various research activities. the quantities and activities of radioactive waste currently at Lucas Heights are very small compared to many other nuclear facilities overseas, especially those in countries with nuclear power program. Nevertheless, in the absence of a repository for nuclear wastes in Australia and guidelines for waste conditioning, the waste inventory has been growing steadily. This report reviews the status of radioactive waste management at ANSTO, including spent fuel management, treatment of effluents and environmental monitoring. It gives details of: relevant legislative, regulatory and related requirements; sources and types of radioactive waste generated at ANSTO; waste quantities and activities (both cumulative and annual arisings); existing practices and procedures for waste management and environmental monitoring; recommended broad strategies for dealing with radioactive waste management issues. Detailed proposals on how the recommendations should be implemented is the subject of a companion internal document, the Radioactive Waste Management Action Plan 1996-2000 which provides details of the tasks to be undertaken, milestones and resource requirements. 44 refs., 2 tabs., 18 figs

Radioactive Waste Management Basis

International Nuclear Information System (INIS)

Perkins, B.K.

2009-01-01

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.

Management of radioactive wastes from non-power applications. The Cuban experience

International Nuclear Information System (INIS)

Benitez, J.C.; Salgado, M.; Jova, L.

2001-01-01

Full text: Origin of Radioactive Wastes. The wastes arisen from the applications of radioisotopes in medicine are mainly liquids and solid materials contaminated with short lived radionuclides and sealed sources used in radiotherapy and for sterilization of medical materials. Radioactive wastes from industrial applications are generally disused sealed sources used in level detection, quality control, smoke detection and non-destructive testing. The principal forms of wastes generated by research institutes are miscellaneous liquids, trash, biological wastes, and scintillation vials, sealed sources and targets. Solid radioactive wastes are mainly produced during research works, cleaning and decontamination activities and they consist of rags, paper, cellulose, plastics, gloves, clothing, overshoes, etc. Laboratory materials such as cans, polyethylene bags and glass bottles also contribute to the solid waste inventory. Small quantities of non-compactable wastes are also collected and received for treatment. They include wood pieces, metal scrap, defective components and tools. Radioactive Waste Management Policy and Infrastructure. Since 1994 the Cuban integral policy of nuclear development is entrusted to the Nuclear Energy Agency of the Ministry of Science, Technology and Environment (CITMA). The National Center for Nuclear Safety (CNSN) is responsible for the licensing and supervision of radioactive and nuclear installations. The CPHR is in charge of waste management policy and therefore is responsible for centralized collection, transportation, treatment, conditioning, long term storage, and disposal of radioactive waste, as well as for developing new waste conditioning and containment methods. Radioactive Waste Management Facilities. Waste Treatment and Conditioning Plant (WTCP). The present facility is a building that includes a technological area of 100 m 2 and a laboratory area with a surface of around 30 m 2 . Other areas to be distinguished inside the

Treatment of radioactive waste - Routine or challenge? Proceedings

International Nuclear Information System (INIS)

2003-01-01

The seminar had the following topics: Proposal for new legislation covering radioactive waste management in the EU, new requirements preparations for the later repository, efficient and cost effective treatment of radioactive waste water, intermediate level waste cementation, incineration of spent ion exchange resins in a triphasic mixture, application of THOR-technology on resins, new development for transportation and storage of reactor vessel parts, and conditioning of nuclear fuel containing wastes. (uke)

Management of radioactive waste in FR Yugoslavia

International Nuclear Information System (INIS)

Plecas, I.

1998-01-01

In the last forty years, in FR Yugoslavia, as a result of the two research reactors operation and as a result of the radionuclides application in the medicine, industry and agriculture, radioactive waste materials of different levels of specific activity was generated. As a temporary solution, these radioactive waste materials are stored in the two interim storage facilities. Since the one of the storages is completely filled with the radioactive waste materials that are packed in the metal drums and plastic barrels, and the second one has a effective space for radioactive waste materials storing for the approximately next few years, attempts are made in the 'Vinca' institute of nuclear sciences in developing the immobilization process for the low and intermediate level radioactive waste materials and their safe disposal into the appropriate disposal system, that was adopted for such materials. Research work on optimization of the chosen techniques in treatment, conditioning, immobilization and storing the radioactive waste materials is in progress. Investigations are carrying out on materials that are adopted as components of the engineer trench system, in aim to improve their physical-chemical properties, mainly retention the radionuclides release from the disposal facility to environment, as well as their mechanical characteristics. Parallel with the optimization of the composition of the materials that will create the engineer trench system, optimization of the processes and matrix-radioactive waste mixture forms is in progress, and we hope that this work will influence the design of the future Yugoslav storage center, shallow land burial type, for low and intermediate level radioactive waste materials

International co-operation for safe radioactive waste management

International Nuclear Information System (INIS)

1983-01-01

As a specialised inter-governmental body, NEA pursues three main objectives for its radioactive waste management programme: - The promotion of studies to improve the data base available in support of national programmes. - The support of Research and Development through co-ordination of national activities and promotion of international projects. - An improvement in the general level of understanding of waste management issues and options, particularly in the field of waste disposal. The management of radioactive waste from nuclear activities covers several sequences of complex technical operations. However, as the ultimate objective of radioactive waste management is the disposal of the waste, the largest part of the work programme is directed towards the analysis of disposal options. In addition, NEA is active in various other areas of waste management, such as the treatment and conditioning of waste, the decommissioning of nuclear facilities and the institutional aspects of the long term management of radioactive waste

Radioactive wastes and discharges

International Nuclear Information System (INIS)

1993-01-01

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.)

Chemistry and technology of radioactive waste management - the IAEA perspective

International Nuclear Information System (INIS)

Efremenkov, V.M.; )

2003-01-01

The paper refers the consideration of chemical composition of radioactive waste in selection of particular method and technology for waste treatment and conditioning, importance of physico-chemical parameters of waste processing techniques for optimisation of waste processing to produce waste form of appropriate quality. Consideration of waste chemistry is illustrated by several IAEA activities on radioactive waste management and by outlining the scope of some selected technical reports on different waste management subjects. Different components of the IAEA activities on radioactive waste management and on technology transfer are presented and discussed. (author)

Survey of product quality control of radioactive waste

International Nuclear Information System (INIS)

Warnecke, E.

1989-01-01

The PTB has developed basic procedures with regard to deriving final storage conditions and product quality control. After this, requirements for radioactive waste are derived via safety analysers, in which information about the radioactive waste, the geological overall situation of the site and the layout of the final storage mine, in particular, are included as basic data. The final storage conditions are only determined with the awarding of the planning decision. Compliance with them can be proved by random sample tests on waste containers or via a qualification and inspection of the conditioning process. (DG) [de

Shallow ground disposal of radioactive wastes

International Nuclear Information System (INIS)

1981-01-01

This guidebook outlines the factors to be considered in site selection, design, operation, shut-down and surveillance as well as the regulatory requirements of repositories for safe disposal of radioactive waste in shallow ground. No attempt is made to summarize the existing voluminous literature on the many facets of radioactive waste disposal. In the context of this guidebook, shallow ground disposal refers to the emplacement of radioactive waste, with or without engineered barriers, above or below the ground surface, where the final protective covering is of the order of a few metres thick. Deep geological disposal and other underground disposal methods, management of mill tailings and disposal into the sea have been or will be considered in other IAEA publications. These guidelines have been made sufficiently general to cover a broad variety of climatic, hydrogeological and biological conditions. They may need to be interpreted or modified to reflect local conditions and national regulations

Management of radioactive wastes

International Nuclear Information System (INIS)

Hendee, W.R.

1984-01-01

The disposal of radioactive wastes is perhaps the most controversial and least understood aspect of the use of nuclear materials in generating electrical power, the investigation of biochemical processes through tracer kinetics, and the diagnosis and treatment of disease. In the siting of nuclear power facilities, the disposal of radioactive wastes is invariably posed as the ultimate unanswerable question. In the fall of 1979, biochemical and physiologic research employing radioactive tracers was threatened with a slowdown resulting from temporary closure of sites for disposal of low-level radioactive wastes (LLW). Radioactive pharmaceuticals used extensively for diagnosis and treatment of human disease have increased dramatically in price, partly as a result of the escalating cost of disposing of radioactive wastes created during production of the labeled pharmaceuticals. These problems have resulted in identification of the disposal of LLW as the most pressing issue in the entire scheme of management of hazardous wastes. How this issue as well as the separate issue of disposal of high-level radioactive wastes (HLW) are being addressed at both national and state levels is the subject of this chapter

Radioactive waste disposal

International Nuclear Information System (INIS)

Bohm, H.; Closs, K.D.; Kuhn, K.

1981-01-01

The solutions to the technical problem of the disposal of radioactive waste are limited by a) the state of knowledge of reprocessing possibilites, b) public acceptance of the use of those techniques which are known, c) legislative procedures linking licensing of new nuclear power plants to the solution of waste problems, and d) other political constraints. Wastes are generated in the mining and enriching of radioactive elements, and in the operation of nuclear power plants as well as in all fields where radioactive substances may be used. Waste management will depend on the stability and concentration of radioactive materials which must be stored, and a resolution of the tension between numerous small storage sites and a few large ones, which again face problems of public acceptability

Radioactive wastes and discharges

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

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.

Radioactive wastes and discharges

International Nuclear Information System (INIS)

2000-01-01

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

International trends of radioactive waste management

International Nuclear Information System (INIS)

Luo Shanggeng

1989-01-01

The new trends of radioactive waste management in the world such as focusing on decreasing the amount of radioactive wastes, developing decontamination and decommissioning technology, conscientious solution for radiactive waste disposal, carrying out social services of waste treatment and quality assurance are reviewed. Besides, comments and suggestions are presented. Key words Radioactive waste management, Radioactive waste treatment, Radioactive waste disposal

Objectives for radioactive waste packaging

International Nuclear Information System (INIS)

Flowers, R.H.

1982-04-01

The report falls under the headings: introduction; the nature of radioactive wastes; how to manage radioactive wastes; packaging of radioactive wastes (supervised storage; disposal); waste form evaluation and test requirements (supervised storage; disposal); conclusions. (U.K.)

Low and medium radioactive waste management in Belgium

International Nuclear Information System (INIS)

Dejonghe, P.; Bonne, A.; Van de Voorde, N.; Detilleux, E.

1986-01-01

This paper summarizes some information on the producers and production of radioactive wastes in Belgium, the evolution of the technical thinking in this area, how the management of radioactive wastes has been and is being organized in the country, and some practical achievements. This paper does not contain much information on new methods and processes and is based primarily on actual experience. Successively the following subjects are discussed: the waste producers; the main objectives in treatment/conditioning and disposal; organization; treatment and conditioning technology; and storage and disposal

Radioactive Wastes. Revised.

Science.gov (United States)

Fox, Charles H.

This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. This booklet deals with the handling, processing and disposal of radioactive wastes. Among the topics discussed are: The Nature of Radioactive Wastes; Waste Management; and Research and Development. There are…

Radioactive Waste Management Strategy

International Nuclear Information System (INIS)

2002-01-01

This strategy defines methods and means how collect, transport and bury radioactive waste safely. It includes low level radiation waste and high level radiation waste. In the strategy are foreseen main principles and ways of storage radioactive waste

Regulatory inspection practices for radioactive and non-radioactive waste management facilities

International Nuclear Information System (INIS)

Roy, Amitava

2017-01-01

Management of nuclear waste plays an important role in the nuclear energy programme of the country. India has adopted the Closed Fuel Cycle option, where the spent nuclear fuel is treated as a material of resource and the nuclear waste is wealth. Closed fuel cycle aims at recovery and recycle of valuable nuclear materials in to reactors as fuel and also separation of useful radio isotopes for the use in health care, agriculture and industry. India has taken a lead role in the waste management activities and has reached a level of maturity over a period of more than forty decades. The nuclear waste management primarily comprises of waste characterization, segregation, conditioning, treatment, immobilization of radionuclides in stable and solid matrices and interim retrievable storage of conditioned solid waste under surveillance. The waste generated in a nuclear facility is in the form of liquid and solid, and it's classification depends on the content of radioactivity. The liquid waste is characterized as Low level (LLW), Intermediate level (ILW) and High Level (HLW). The LLW is relatively large in volume and much lesser radioactive. The LLW is subjected to chemical precipitation using various chemicals based on the radionuclides present, followed by filtration, settling, ion exchange and cement fixation. The conditioning and treatment processes of ILW uses ion exchange, alkali hydrolysis for spent solvent, phase separation and immobilization in cement matrix. The High Level Waste (HLW), generated during spent fuel reprocessing and containing more than 99 percent of the total radioactivity is first subjected to volume reduction/concentration by evaporation and then vitrified in a meIter using borosilicate glass. Presently, Joule Heated Ceramic Meter is used in India for Vitrification process. Vitrified waste products (VWP) are stored for interim period in a multibarrier, air cooled facility under surveillance

Low-level radioactive waste disposal facility closure

International Nuclear Information System (INIS)

White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J.

1990-11-01

Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs

Low-level radioactive waste disposal facility closure

Energy Technology Data Exchange (ETDEWEB)

White, G.J.; Ferns, T.W.; Otis, M.D.; Marts, S.T.; DeHaan, M.S.; Schwaller, R.G.; White, G.J. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

1990-11-01

Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act on long-term predictions are evaluated including biological, chemical, and physical phenomena of both natural and anthropogenic origin. These factors are then applied to six existing, yet very different, low-level radioactive waste sites. A summary and recommendations for future site characterization and monitoring activities is given for application to potential and existing sites. Part II of this report contains guidance on the design and implementation of a performance monitoring program for low-level radioactive waste disposal facilities. A monitoring programs is described that will assess whether engineered barriers surrounding the waste are effectively isolating the waste and will continue to isolate the waste by remaining structurally stable. Monitoring techniques and instruments are discussed relative to their ability to measure (a) parameters directly related to water movement though engineered barriers, (b) parameters directly related to the structural stability of engineered barriers, and (c) parameters that characterize external or internal conditions that may cause physical changes leading to enhanced water movement or compromises in stability. Data interpretation leading to decisions concerning facility closure is discussed. 120 refs., 12 figs., 17 tabs.

Radioactive Waste Repositories Administration - SURAO

International Nuclear Information System (INIS)

Kucerka, M.

1998-01-01

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.)

Glasses used for the high level radioactive wastes storage

International Nuclear Information System (INIS)

Sombret, C.

1983-06-01

High level radioactive wastes generated by the reprocessing of spent fuels is an important concern in the conditioning of radioactive wastes. This paper deals with the status of the knowledge about glasses used for the treatment of these liquids [fr

Guide book of radioactive wastes collecting. Producers, from collection to storage

International Nuclear Information System (INIS)

2003-01-01

This document, more particularly devoted to radioactive waste producers (except electronuclear industry), defines the technical specifications and the financial conditions relative to the taking over of their wastes by the ANDRA, the French national agency of radioactive wastes. Content: general principles, instructions manual of the taking over demand, practical conditions of wastes collecting, packaging and containers, specifications for each category of waste, particular cases, price table, disputes. (J.S.)

Perspectives concerning radioactive waste management

International Nuclear Information System (INIS)

Noynaert, L.

2013-01-01

The article presents a general overview of the principles of radioactive waste management as established by the International Atomic Energy Agency. Subsequently, research and development related to radioactive waste management at the Belgian Nuclear Research Center SCK·CEN is discussed. Different topical areas are treated including radioactive waste characterisation, decontamination and the long-term management of radioactive waste. The decommissioning of the BR3 reactor and the construction and the exploitation of the underground research laboratory HADES are cited as examples of the pioneering role that SCK·CEN has played in radioactive waste management.

Conditioning of low level radioactive wastes, spent radiation sources and their transport at the interim storage building of the Institute of Nuclear Physics in Albania

International Nuclear Information System (INIS)

Qafmolla, L.

2000-01-01

Aspects of treatment and management of radioactive wastes resulting from the use of radiation sources and radioisotopes in research, medicine and industry, are described. The methods applied for the conditioning of low-level radioactive wastes and spent radiation sources are simple. Solid radioactive wastes with low-level activity, after accumulation, minimization, segregation and measurement, are burned or compressed in a simple compactor of the PGS type. Spent radiation sources are placed into 200 l drums, are cemented and conditioned. Conditioned drums from the Radiation Protection Division of the Institute of Nuclear Physics (INP), which is the responsible Institution for the treatment and management of radioactive wastes in Albania, are transported to the interim storage building of the Institute of Nuclear Physics in Tirana. Work to construct a new building for treatment and management of radioactive wastes and spent radiation sources within the territory of INP is underway. Funds have been allocated accordingly: based on the Law No. 8025 of 25.11.1995, it is the Albanian Government's responsibility to finance activities concerned with the treatment and management of radioactive wastes generating from the use of ionizing radiation in science, medicine and industry in the country. (author)

An interim report of the Subcommittee on Radioactive Waste Countermeasures: measures for radioactive waste treatment and disposal

International Nuclear Information System (INIS)

1984-01-01

The Subcommittee on Radioactive Waste Countermeasures has studied on the measures for land disposal of low-level radioactive wastes and ultra-low-level radioactive wastes and the measures for treatment and disposal of high-level radioactive wastes and transuranium wastes. The results of studies so far are presented as an interim report. In disposal of low-level radioactive wastes, the land disposal is being required increasingly. The measures according to the levels of radioactivity are necessary. For the ultra-low-level radioactive wastes, their occurrence in large quantities is expected along with reactor decommissioning. In disposal of the high-level radioactive wastes, the present status is a transition toward the practical stages. Transuranium wastes should increase in their arising in the future. (Mori, K.)

Waste minimization for commercial radioactive materials users generating low-level radioactive waste

International Nuclear Information System (INIS)

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S.; Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L.

1991-07-01

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature

Radioactive mixed waste disposal

International Nuclear Information System (INIS)

Jasen, W.G.; Erpenbeck, E.G.

1993-02-01

Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste

Radioactive waste management

International Nuclear Information System (INIS)

1984-07-01

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.)

Steel corrosion in radioactive waste storage tanks

International Nuclear Information System (INIS)

Carranza, Ricardo M.; Giordano, Celia M.; Saenz, E.; Weier, Dennis R.

2004-01-01

A collaborative study is being conducted by CNEA and USDOE (Department of Energy of the United States of America) to investigate the effects of tank waste chemistry on radioactive waste storage tank corrosion. Radioactive waste is stored in underground storage tanks that contain a combination of salts, consisting primarily of sodium nitrate, sodium nitrite and sodium hydroxide. The USDOE, Office of River Protection at the Hanford Site, has identified a need to conduct a laboratory study to better understand the effects of radioactive waste chemistry on the corrosion of waste storage tanks at the Hanford Site. The USDOE science need (RL-WT079-S Double-Shell Tanks Corrosion Chemistry) called for a multi year effort to identify waste chemistries and temperatures within the double-shell tank (DST) operating limits for corrosion control and operating temperature range that may not provide the expected corrosion protection and to evaluate future operations for the conditions outside the existing corrosion database. Assessment of corrosion damage using simulated (non-radioactive) waste is being made of the double-shell tank wall carbon steel alloy. Evaluation of the influence of exposure time, and electrolyte composition and/or concentration is being also conducted. (author) [es

Radioactive waste (disposal)

International Nuclear Information System (INIS)

Jenkin, P.

1985-01-01

The disposal of low- and intermediate-level radioactive wastes was discussed. The following aspects were covered: public consultation on the principles for assessing disposal facilities; procedures for dealing with the possible sites which the Nuclear Industry Radioactive Waste Executive (NIREX) had originally identified; geological investigations to be carried out by NIREX to search for alternative sites; announcement that proposal for a site at Billingham is not to proceed further; NIREX membership; storage of radioactive wastes; public inquiries; social and environmental aspects; safety aspects; interest groups; public relations; government policies. (U.K.)

Significance of chemotoxic admixtures in radioactive wastes

International Nuclear Information System (INIS)

Merz, E.R.

1989-01-01

The double hazard potential of mixed wastes is characterized by several criteria: radioactivity on the one hand, and chemical toxicity, in flammability, corrosiveness as well as chemical reactivity on the other. The author argues that mixed wastes assigned for ultimate disposal should therefore be thoroughly detoxified, inertized, or mineralized, prior to conditioning and packaging. Strategies and techniques are presented which ensure the elimination of hazardous organic chemicals and minimizing waste volumes to be disposed of. Advantage can be taken of mixing mineralized filter dusts, arising in the combustion of hazardous chemical wastes with low-activity inertized radioactive wastes as a solidifying reagent. Simultaneous geological disposal of such mixed waste is feasible without any drawbacks

Treatment of solid radioactive waste: The incineration of low level radioactive waste

International Nuclear Information System (INIS)

Dirks, F.; Hempelmann, W.

1982-01-01

Nuclear facilities produce large quantities of burnable solid radioactive waste which incineration can reduce in volume and change into a form capable of ultimate storage. Experiments over many years were carried out at the Karlsruhe Nuclear Research Center to determine the boundary conditions for the design and construction of incineration plants for radioactive waste. On the basis of those experiments a test facility was started up in 1971. This operating facility consists of a shaft furnace lined with ceramics with a downstream series of ceramic flue gas filters. In 1976 the plant was exchanged by the installation of a pilot facility for burning organic solvents and of a flue gas scrubber. The plant has so far been in operation for more than 28000 hours and has processed in excess of 1500 to of solid and some 300 m 3 of liquid low level radioactive wastes. Various repairs and interventions were carried out without greatly impairing availability, which was 81 % on the average. The plant design is being used by various licensees in Japan and Europe; three plants are either in operation or completed, three more are under construction or in the planning stage. On the basis of the available process an incineration plant for alpha contaminated waste will be built at the Karlsruhe Nuclear Research Center in the next few years. (orig.)

System for disposing of radioactive waste

International Nuclear Information System (INIS)

Gablin, K.A.; Hansen, L.J.

1979-01-01

A system is described for disposing of radioactive waste material from nuclear reactors by solidifying the liquid components to produce an encapsulated mass adapted for disposal by burial. The method contemplates mixing of radioactive waste materials, with or without contained solids, with a setting agent capable of solidifying the waste liquids into a free standing hardened mass, placing the resulting liquid mixture in a container with a proportionate amount of a curing agent to effect solidification under controlled conditions, and thereafter burying the container and contained solidified mixture. The setting agent is a water-extendable polymer consisting of a suspension of partially polymerized particles of urea formaldehyde in water, and the curing agent is sodium bisulfate. Methods are disclosed for dewatering slurry-like mixtures of liquid and particulate radioactive waste materials, such as spent ion exchange resin beads, and for effecting desired distribution of non-liquid radioactive materials in the central area of the container prior to solidification, so that the surrounding mass of lower specific radioactivity acts as a partial shield against higher radioactivity of the non-liquid radioactive materials. The methods also provide for addition of non-radioactive filler materials to dilute the mixture and lower the overall radioactivity of the hardened mixture to desired Lowest Specific Activity counts. An inhibiting agent is added to the liquid mixture to adjust the solidification time, and provision is made for adding additional amounts of setting agent and curing agent to take up any free water and further encapsulate the hardened material within the container. 30 claims

System for disposing of radioactive waste

International Nuclear Information System (INIS)

Gablin, K.A.; Hansen, L.J.

1977-01-01

A system is described for disposing of radioactive waste material from nuclear reactors by solidifying the liquid components to produce an encapsulated mass adapted for disposal by burial. The method contemplates mixing of radioactive waste materials, with or without contained solids, with a setting agent capable of solidifying the waste liquids into a free standing hardened mass, placing the resulting liquid mixture in a container with a proportionate amount of a curing agent to effect solidification under controlled conditions, and thereafter burying the container and contained solidified mixture. The setting agent is a water-extendable polymer consisting of a suspension of partially polymerized particles of urea formaldehyde in water, and the curing agent is sodium bisulfate. Methods are disclosed for dewatering slurry-like mixtures of liquid and particulate radioactive waste materials, such as spent ion exchange resin beads, and for effecting desired distribution of non-liquid radioactive materials in the central area of the container prior to solidification, so that the surrounding mass of lower specific radioactivity acts as a partial shield against higher radioactivity of the non-liquid radioactive materials. The methods also provide for addition of non-radioactive filler materials to dilute the mixture and lower the overall radioactivity of the hardened mixture to desired Lowest Specific Activity counts. An inhibiting agent is added to the liquid mixture to adjust the solidification time, and provision is made for adding additional amounts of setting agent and curing agent to take up any free water and further encapsulate the hardened material within the container

National facilities for the management of institutional radioactive waste in Romania

International Nuclear Information System (INIS)

Rotarescu, Gh.; Turcanu, C.N.; Dragolici, F.; Nicu, M.; Lungu, L.; Cazan, L.; Matei, G.; Guran, V.

2000-01-01

The management of the non-fuel cycle radioactive wastes from all over Romania is centralized at IFIN-HH in the Radioactive Waste Treatment Plant (STDR). Final disposal is carried out at the National Repository of Radioactive Wastes (DNDR) at Baita Bihor. Radioactive waste treated at STDR arise from three main sources: 1. Wastes arising from the WWR-S research reactor during operation and the future decommissioning works; 2. Local waste from other facilities operating on IFIN-HH site. These sources include wastes generated during the normal activities of the STDR; 3. Wastes from IFIN-HH off site facilities and activities including medical, biological, and industrial applications all over the country. The Radiochemical Production Center, operating within IFIN-HH is the most important source of low and intermediate level radioactive wastes (liquid and solid), as the operational wastes arising from processing at STDR are. The STDR basically consists of liquid and solid waste treatment and conditioning facilities, a radioactive decontamination centre, a laundry and an intermediate storage area. The processing system of the STDR are located at six principal areas performing the following activities: 1. Liquid effluent treatment; 2. Burning of combustible solid stuff; 3. Compaction of solid non-combustible stuff; 4. Cement conditioning; 5. Radioactive decontamination; 6. Laundry. The annual designed treatment capacity of the plant is 1500 m 3 Low Level Aqueous Waste, 100 m 3 Low Level Solid Waste and shielded drums for Intermediate Level Waste. The temporary storage within and final disposal of waste in the frame of DNDR are explained as well as the up-dating of institutional radioactive waste infrastructure

Radioactive wastes

International Nuclear Information System (INIS)

Dupuis, M.C.

2007-01-01

Managing radioactive wastes used to be a peripheral activity for the French atomic energy commission (Cea). Over the past 40 years, it has become a full-fledged phase in the fuel cycle of producing electricity from the atom. In 2005, the national radioactive waste management agency (ANDRA) presented to the government a comprehensive overview of the results drawn from 15 years of research. This landmark report has received recognition beyond France's borders. By broadening this agency's powers, an act of 28 June 2006 acknowledges the progress made and the quality of the results. It also sets an objective for the coming years: work out solutions for managing all forms of radioactive wastes. The possibility of recovering wastes packages from the disposal site must be assured as it was asked by the government in 1998. The next step will be the official demand for the creation of a geological disposal site in 2016

ANSTO`s radioactive waste management policy. Preliminary environmental review

Energy Technology Data Exchange (ETDEWEB)

Levins, D.M.; Airey, P.; Breadner, B.; Bull, P.; Camilleri, A.; Dimitrovski, L.; Gorman, T.; Harries, J.; Innes, R.; Jarquin, E.; Jay, G.; Ridal, A.; Smith, A.

1996-05-01

For over forty years, radioactive wastes have been generated by ANSTO (and its predecessor, the AAEC) from the operation of nuclear facilities, the production of radioisotopes for medical and industrial use, and from various research activities. the quantities and activities of radioactive waste currently at Lucas Heights are very small compared to many other nuclear facilities overseas, especially those in countries with nuclear power program. Nevertheless, in the absence of a repository for nuclear wastes in Australia and guidelines for waste conditioning, the waste inventory has been growing steadily. This report reviews the status of radioactive waste management at ANSTO, including spent fuel management, treatment of effluents and environmental monitoring. It gives details of: relevant legislative, regulatory and related requirements; sources and types of radioactive waste generated at ANSTO; waste quantities and activities (both cumulative and annual arisings); existing practices and procedures for waste management and environmental monitoring; recommended broad strategies for dealing with radioactive waste management issues. Detailed proposals on how the recommendations should be implemented is the subject of a companion internal document, the Radioactive Waste Management Action Plan 1996-2000 which provides details of the tasks to be undertaken, milestones and resource requirements. 44 refs., 2 tabs., 18 figs.

Classification of radioactive waste and determination of waste specifications as well as conditions of acceptance for ultimate storage

International Nuclear Information System (INIS)

Merz, E.

1983-04-01

The determination of waste specification and conditions of acceptance must follow a certain scheme, the basics of which will be presented. First the types of waste and the ultimate storage facilities will be characterized. The various categories of waste will be listed in a universally valid system, and the preliminary conditioning options will be determined. Based on the results of safety analysis taking into account the whole system - geological circumstances, ultimate store mines, types and forms of waste - specifications for the various ultimate store products are to be derived following iterative methods. Suggestions though not of a binding nature and probably subject to eventual revisions in part will be presented. To ensure the safety goals, i.e. the exclusion of radioactivity from the human biosphere, appropriate quality control is required concerning the production and the acceptance at the ultimate store. The guiding principles to be heeded will be discussed in brief. (orig./HP) [de

[Investigation of actual condition of management and disposal of medical radioactive waste in Korea].

Science.gov (United States)

Watanabe, Hiroshi; Nagaoka, Hiroaki; Yamaguchi, Ichiro; Horiuchi, Shoji; Imoto, Atsushi

2009-07-20

In order to realize the rational management and disposal of radioactive waste like DIS or its clearance as performed in Europe, North America, and Japan, we investigated the situation of medical radioactive waste in Korea and its enforcement. We visited three major Korean facilities in May 2008 and confirmed details of the procedure being used by administering a questionnaire after our visit. From the results, we were able to verify that the governmental agency had established regulations for the clearance of radioactive waste as self-disposal based on the clearance level of IAEA in Korea and that the medical facilities performed suitable management and disposal of radioactive waste based on the regulations and superintendence of a radiation safety officer. The type of nuclear medicine was almost the same as that in Japan, and the half-life of all radiopharmaceuticals was 60 days or less. While performing regulatory adjustment concerning the rational management and disposal of radioactive waste in Korea for reference also in this country, it is important to provide an enforcement procedure with quality assurance in the regulations.

Radioactive waste processing

International Nuclear Information System (INIS)

Curtiss, D.H.; Heacock, H.W.

1976-01-01

The description is given of a process for treating radioactive waste whereby a mud of radioactive waste and cementing material is formed in a mixer. This mud is then transferred from the mixer to a storage and transport container where it is allowed to harden. To improve transport efficiency an alkali silicate or an alkaline-earth metal silicate is added to the mud. For one hundred parts by weight of radioactive waste in the mud, twenty to one hundred parts by weight of cementing material are added and five to fifty parts by weight of silicate, the amount of waste in the mud exceeding the combined amount of cementing and silicate material [fr

Method of controlling radioactive waste processing systems

International Nuclear Information System (INIS)

Mikawa, Hiroji; Sato, Takao.

1981-01-01

Purpose: To minimize the pellet production amount, maximize the working life of a solidifying device and maintaining the mechanical strength of pellets to a predetermined value irrespective of the type and the cycle of occurrence of the secondary waste in the secondary waste solidifying device for radioactive waste processing systems in nuclear power plants. Method: Forecasting periods for the type, production amount and radioactivity level of the secondary wastes are determined in input/output devices connected to a control system and resulted signals are sent to computing elements. The computing elements forecast the production amount of regenerated liquid wastes after predetermined days based on the running conditions of a condensate desalter and the production amounts of filter sludges and liquid resin wastes after predetermined days based on the liquid waste processing amount or the like in a processing device respectively. Then, the mass balance between the type and the amount of the secondary wastes presently stored in a tank are calculated and the composition and concentration for the processing liquid are set so as to obtain predetermined values for the strength of pellets that can be dried to solidify, the working life of the solidifying device itself and the radioactivity level of the pellets. Thereafter, the running conditions for the solidifying device are determined so as to maximize the working life of the solidifying device. (Horiuchi, T.)

Radioactive Waste Management BasisApril 2006

Energy Technology Data Exchange (ETDEWEB)

Perkins, B K

2011-08-31

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.

Radioactive waste management and regulation

International Nuclear Information System (INIS)

Willrich, M.

1976-12-01

The following conclusions are reached: (1) safe management of post-fission radioactive waste is already a present necessity and an irreversible long-term commitment; (2) basic goals of U.S. radioactive waste policy are unclear; (3) the existing organization for radioactive waste management is likely to be unworkable if left unchanged; and (4) the existing framework for radioactive waste regulation is likely to be ineffective if left unchanged

KONTEC 2009. Report about the 9th International Symposium on ''Conditioning of radioactive operational and decommissioning wastes''

International Nuclear Information System (INIS)

Anon.

2009-01-01

''Kontec 2009'' was organized in Dresden on April 15-17, 2009. For the 8 th time, this established international meeting covered the subjects of ''Conditioning of Radioactive Operational and Decommissioning Wastes'' and ''Decommissioning and Dismantling of Nuclear Facilities'' and the R and D Status Report delivered by the German Federal Ministry for Education and Research on this key topic. Some 790 participants from 13 countries heard and discussed the contributions to the three-day meeting. The program of the symposium comprised plenary sessions dealing with these 4 key subjects: Disposal of Radioactive Residues from Nuclear Facilities' Operation and Decommissioning, Decommissioning and Dismantling of Nuclear Facilities, Facilities and Systems for the Conditioning of Operational and Decommissioning Wastes, Transport, Interim and Final Storage of Non-heat Generating Wastes (i.e. Konrad). The sessions were supplemented by poster sessions and selected short presentations under the heading of ''Kontec Direct.'' (orig.)

Radioactive waste management

International Nuclear Information System (INIS)

Morley, F.

1980-01-01

A summary is given of the report of an Expert Group appointed in 1976 to consider the 1959 White Paper 'The Control of Radioactive Wastes' in the light of the changes that have taken place since it was written and with the extended remit of examining 'waste management' rather than the original 'waste disposal'. The Group undertook to; review the categories and quantities present and future of radioactive wastes, recommend the principles for the proper management of these wastes, advise whether any changes in practice or statutory controls are necessary and make recommendations. (UK)

Assessment of Malaysia Institutional radioactive waste management

International Nuclear Information System (INIS)

Syed Hakimi Sakuma; Nik Marzukee; Ibrahim Martibi

1996-01-01

A complete inventory of radioactive wastes from different source bas been set up in Malaysia. Wastes from external agencies were sent to the National Radioactive Waste Management Center at MINT for final disposal. MINT has been collecting information on the accumulated wastes received since 1982. Assessment of radioactive waste management in Malaysia has been conducted based on the inventory record. The information in the inventory include description of users, type volume, characteristics of the wastes; and the current and accumulated activities of the radioisotopes in the wastes forms while storing. The records indicate that there is a significant increase in the volume of wastes from medical and industrial applications. The category of users varies; there are about 270 industrial users, about 60 in medical fields and 13 in research institutes and universities. Major users generating sealed source wastes for the industrial sector are services, manufacturing and consumer companies; including government department and universities. It is estimated that by the year 2005, approximately a total accumulated processed waste package volume for disposal will be between 210-215 m sup 3. This estimate includes low level and intermediate level wastes. From this study, future waste management activities in Malaysia can be planned with proper policy decision, treatment conditioning, storage and disposal facilities. This will enable radioactive wastes to be kept under control and their potential impact on man and the environment to be minimal

Predisposal Radioactive Waste Management

International Nuclear Information System (INIS)

2014-01-01

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

Radioactive waste with 14C in Argentina

International Nuclear Information System (INIS)

Di Lello, D.S.

2009-01-01

14 C is a long half-life radioisotope, which is present in radioactive waste generated during the operation and decommissioning of nuclear power plants. 14 C can also be found in waste generated by medical diagnostic laboratories or any one generated by fields that deal with research and development (mainly connected with the biochemists area). According to international precedents the disposal of 14 C based on the final amount found in radioactive waste and its chemical form have conditioned the design and operation of the facilities (either because of the amount of it or the chemical form in which 14 C was present). We have to take into account that the design of facilities for radioactive waste disposal is included among the obligations of the National Radioactive Waste Management Program (PNGRR). It is absolutely necessary to count with enough information about the characteristics of any waste containing 14 C that is generated in Argentina, in order to be able to fulfil the requirements previously mentioned. The main characteristics of interest in the frame of the present project are: a) the principal reactions that take place for the formation of 14 C; b) The specific concentration of activity in materials where this radio nuclei is formed or is accumulated; c) To know which is the current step in the process of managing these wastes (in Argentina and all over the world). Either if it refers to bulk or conditioned storage, inside the generating facility; d) Transportation possibilities of 14 C under these conditions; e) The accumulated volume and the generation rate of this kind of waste in Argentina. This paper presents an initial collection and evaluation of the information related to the characteristics already mentioned, having gathered published material from the literature and information in the PNGRR up to this moment. The description of the characteristics of the radioactive waste containing 14 C from nuclear power plants, hospitals and research and

Management of radioactive waste: A review

OpenAIRE

Luis Paulo Sant'ana; Taynara Cristina Cordeiro

2016-01-01

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...

Leachability of bituminized radioactive waste. Literature survey

International Nuclear Information System (INIS)

Akimoto, Toshiyuki; Nakayama, Shinichi; Iida, Yoshihisa; Nagano, Tetsushi

1999-02-01

Bituminized radioactive waste that will be returned from COGEMA, France is planned to be disposed of in deep geologic repository in Japan. Data on leachability of radionuclides from bituminized waste are required for the performance assessment of the disposal. We made a literature survey on bitumen and bituminized radioactive waste, placing emphasis on leach tests and leach data in terms of geologic disposal. This survey revealed that reliable leach data on transuranium elements and data obtained under reducing conditions that is characteristic to deep underground are lacking. (author). 64 refs

Radioactive waste management in Switzerland

International Nuclear Information System (INIS)

Hugi, M.

2011-01-01

deep geological repositories are commissioned, the radioactive waste will be temporarily stored in the nuclear power plants and in the central interim storage facility (Würenlingen). The expected amount of waste is based on a safety-related service life of probably 50 years for the existing five nuclear power plants and a MIF collection period until 2050 and comprises approx. 90,000 m3 SMA (conditioned including packaging) and 9,500 m3 HAA / LMA. The site selection procedure is defined as binding in the Sectoral Plan for Deep Geological Repositories. It is a federal planning instrument for regulating and carrying out site selection in accordance with the Swiss Spatial Planning Act. The Sectoral Plan defines the procedural steps and criteria for a transparent and fair selection process and leads to the site selection and the initiation of the general approval procedure in three stages. The Federal Council's decision on the proposals of waste producers regarding geological siting areas according to stage 1 is expected by the end of 2011. Safety is the first priority for site selection, socio-economic and spatial planning aspects have an important but subordinate significance. The commissioning of the deep geological repository SMA is scheduled for 2030 at the earliest, and that for the deep repository HAA at the earliest in 2040. (roessner)

Method of storing radioactive wastes

International Nuclear Information System (INIS)

Adachi, Toshio; Hiratake, Susumu.

1980-01-01

Purpose: To reduce the radiation doses externally irradiated from treated radioactive waste and also reduce the separation of radioactive nuclide due to external environmental factors such as air, water or the like. Method: Radioactive waste adhered with radioactive nuclide to solid material is molten to mix and submerge the radioactive nuclide adhered to the surface of the solid material into molten material. Then, the radioactive nuclide thus mixed is solidified to store the waste in solidified state. (Aizawa, K.)

Conditioning of Radioactive Wastes Prior to disposal; Segregation and Repackaging

Energy Technology Data Exchange (ETDEWEB)

Kang, Il Sik; Kim, Ki Hong; Hong, Dae Seok; Lee, Bum Chul [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-05-15

We stored several types of radioactive wastes at interim storage facility of KAERI ; the combustible wastes (cloths, decontamination paper and vinyls) from Hanaro multipurpose research reactor, nuclear fuel cycle facility, RI production facility and laboratories, and the non-combustible wastes (metals and glass) dismantled and discarded from the apparatus of laboratories which deteriorated, and also the miscellaneous wastes (spent air-filters). After a segregation of these wastes as the same type, they were treated by using a proper method in order to meet both the national regulation and the waste acceptance criteria of Kyung-ju disposal site. For a safe disposal of waste drums, the waste characterization system including a scaling factor which is hard to measure special radionuclides is established completely. All data of those repackaged drums were input into an ANSIM system so that we could manage them clearly and effectively such like an easy transparent traceability. Through a decontamination of empty drums generated in a repackaging process of the stored drums, these drums can be reused or compressed to reduce their volume reduction for disposal. As a result, the space to store radioactive waste drums are secured more than before, and also the interim storage facility are maintained in a good state. The combustible wastes, which stored at the interim storage facility of KAERI, are managed safely in compliance with the specifications of the national regulations and disposal site. Through the classification and repackage of them, the storage space of drums at RWTF was secured more than before, and the storage facility was kept in a good state, and also the disposal cost of all stored waste drums of KAERI will be reduced due to the reduction of waste volume. Base on the experiences, the non-combustible wastes will be treated soon.

Issues and trends in radioactive waste management in Turkey

International Nuclear Information System (INIS)

Osmanlioglu, A.E.

2002-01-01

This paper focuses on issues associated with the waste management aspects of Turkey. Predisposal management of radioactive wastes covers a broad range of activities. This also includes waste identification, characterization and conditioning. Experience gained over years shows that current predisposal waste management practices are well advanced. The paper concludes these activities based on experience gained by CWPSF (CNAEM Waste Processing and Storage Facility) and includes issues and trends in radioactive waste management. In addition general information is presented on ongoing national projects and IAEA research projects on various issues of waste management. (author)

Radioactive waste equivalence

International Nuclear Information System (INIS)

Orlowski, S.; Schaller, K.H.

1990-01-01

The report reviews, for the Member States of the European Community, possible situations in which an equivalence concept for radioactive waste may be used, analyses the various factors involved, and suggests guidelines for the implementation of such a concept. Only safety and technical aspects are covered. Other aspects such as commercial ones are excluded. Situations where the need for an equivalence concept has been identified are processes where impurities are added as a consequence of the treatment and conditioning process, the substitution of wastes from similar waste streams due to the treatment process, and exchange of waste belonging to different waste categories. The analysis of factors involved and possible ways for equivalence evaluation, taking into account in particular the chemical, physical and radiological characteristics of the waste package, and the potential risks of the waste form, shows that no simple all-encompassing equivalence formula may be derived. Consequently, a step-by-step approach is suggested, which avoids complex evaluations in the case of simple exchanges

Conditioning the radioactive oils released from the Cernavoda NPP operation

International Nuclear Information System (INIS)

Popescu, I.; Deneanu, N.; Dulama, M.; Baboiescu, E.

2001-01-01

The radioactive oils released during the Cernavoda NPP operation are lubricating oils used in the primary circuit pumps, hydraulic oils used in the reactor charging machine, as well as, waste turbine oils. The primary cooling circuit is the main way of contamination. This waste contain variable amounts of tritium of activities up to 10 8 Bq/l and relatively small amounts of β/γ emitting radionuclides. The radioactive oils resulting of the heat transport system may contain as much as 1.8 TBq/l of tritium. At INR Pitesti, Department of Radioactive Waste Processing, studies were done concerning the radioactive oils conditioning in concrete. It was found that the minimal compression level required for disposal, of 50 MPa, was exceeded. As consequence, the conditioned waste fulfils the conditions of acceptance provided by the Radioactive Waste National Repository at Baita-Bihor. The main stages of the process are: - dosing the radioactive oil, water and NOFOX9 and NOFOX4 emulsion additives for the 220 l or 80 l barrel; - mixing these ingredients up to reaching the emulsion state; - dosing the cement and lime; - adding the enhancing silicate and shaking the mixture to get a homogeneous matrix; - closing the barrel; - conditioning the 80 l barrel within the 220 l container. The production capacity is of 5 to 8 barrels/shift

Discussion on the methods for calculation release limits for low-level radioactive waste

International Nuclear Information System (INIS)

Cao Fengbo; Liu Xiaochao

2012-01-01

The release request for low-level radioactive waste are briefly described in this paper. Associating with the conditions of low-level radioactive waste of some radioactive waste processing station, the methods and gist for calculating release limits for low-level radioactive waste with national release limits and annual effective dose limit for the public or the occupation are discussed. Then release limits for the low-level radioactive waste are also proposed. (authors)

CONDITIONING OF INTERMEDIATE-LEVEL WASTE AT FORSCHUNGSZENTRUM JUELICH GMBH

International Nuclear Information System (INIS)

Krumbach, H.

2003-01-01

This contribution to the group of low-level, intermediate, mixed and hazardous waste describes the conditioning of intermediate-level mixed waste (dose rate above 10 mSv/h at the surface) from Research Centre Juelich (FZJ). Conditioning of the waste by supercompaction is performed at Research Centre Karlsruhe (FZK). The waste described is radioactive waste arising from research at Juelich. This waste includes specimens and objects from irradiation experiments in the research reactors Merlin (FRJ-1) and Dido (FRJ-2) at FZJ. In principle, radioactive waste at Forschungszentrum Juelich GmbH is differentiated by the surface dose rate at the waste package. Up to a surface dose rate of 10 mSv/h, the waste is regarded as low-level. The radioactive waste described here has a surface dose rate above 10 mSv/h. Waste up to 10 mSv/h is conditioned at the Juelich site according to different conditioning methods. The intermediate-level waste can only be conditioned by supercompaction in the processing facility for intermediate-level waste from plant operation at Research Centre Karlsruhe. Research Centre Juelich also uses this waste cell to condition its intermediate-level waste from plant operation

Disposal of low and intermediate level solid radioactive waste

International Nuclear Information System (INIS)

Kanwar Raj

1998-01-01

Radioactive waste disposal facility is a very important link in the nuclear fuel cycle chain. Being at the end of the back-end of the fuel cycle, it forms an interface between nuclear industry and the environment. Therefore, the effectiveness of the disposal facility for safe isolation of radioactive waste is vital. This is achieved by following a systematic approach to the disposal system as a whole. Conditioned waste, engineered barriers, back-fill and surrounding geosphere are main components of the disposal system. All of them play complementary role in isolating the radioactivity contained in the waste for extended period of time

Incineration technology for alpha-bearing radioactive waste in Germany

International Nuclear Information System (INIS)

Dirks, Friedlich; Pfeiffer, Reinhard

1997-01-01

Since 1971 the Karlsruhe Research Center has developed and operated plants for the incineration of radioactive waste. Three incineration plants for pure β/γ solid, α-bearing solid and radioactive liquid waste have been successfully utilized during last two decades. Recently more than 20 year-old β/γ plant was shut down with the economic point of view, mainly due to the recently reduced volume of burnable β/γ waste. Burnable β/γ solid waste is now being treated with α-bearing waste in a α solid incineration plant. The status of incineration technology for α-bearing waste and other radioactive waste treatment technologies, which are now utilized in Karlsruhe Research Center, such as conditioning of incineration ash, supercompaction, scrapping, and decontamination of solid radioactive waste, etc. are introduced in this presentation. Additionally, operational results of the recently installed new dioxin adsorber and fluidized-bed drier for scrubber liquid in α incineration plant are also described in this presentation. (author) 1 tab., 13 figs

Principles for disposal of radioactive and chemical hazardous wastes

International Nuclear Information System (INIS)

Merz, E. R.

1991-01-01

The double hazard of mixed wastes is characterized by several criteria: radioactivity on the one hand, and chemical toxicity, flammability, corrosiveness as well as chemical reactivity on the other hand. Chemotoxic waste normally has a much more complex composition than radioactive waste and appears in much larger quantities. However, the two types of waste have some properties in common when it comes to their long-term impact on health and the environment. In order to minimize the risk associated with mixed waste management, the material assigned for ultimate disposal should be thoroughly detoxified, inertized, or mineralized prior to conditioning and packaging. Good control over the environmental consequence of waste disposal requires that detailed criteria for tolerable contamination should be established, and that compliance with these criteria can be demonstrated. For radioactive waste, there has been an extensive international development of criteria to protect human health. For non-radioactive waste, derived criteria exist only for a limited number of substances

Inventory and management of radioactive waste in Thailand

International Nuclear Information System (INIS)

Vonglertmongkol, S.

1994-01-01

The objectives of the study are to conceive the data based on the utilization of radiation and radioisotopes in Thailand and the inventory of radioactive waste arising from such utilization. The suggestions of the future radioactive waste management are also given as well. Data collection was done by mean of questionnaire and interviewing 245 radioisotope users in Thailand. The outcome can be summarized as follows:. Increase in the quantity of radioisotope in all sectors of the utilization was found, especially on the applications in nuclear medicine and industry. The amount of radioactive waste is increasing accordingly. The waste from unsealed radioisotopes increase 10.68 percent per year for liquid wastes and about 6.39 percent per year for solid waste. Most of these wastes are subjected to transfer for treatment by the Office of Atomic Energy for Peace (OAEP). The wastes from sealed radiation sources were packed in shielded containers. Most of these wastes would be shipped to the country of supply, but, some will be handled by OAEP. The accumulated wastes volume after treatment and conditioning, in the next 30 year will be around 220 cubic meter, excluding the wastes from the operation of nuclear research reactor, nuclear power plant, decommissioning, used sealed sources and the wastes from mining and milling of radioactive ores

Radioactive waste management and disposal

International Nuclear Information System (INIS)

Simon, R.; Orlowski, S.

1980-01-01

The first European Community conference on Radioactive Waste Management and Disposal was held in Luxembourg, where twenty-five papers were presented by scientists involved in European Community contract studies and by members of the Commission's scientific staff. The following topics were covered: treatment and conditioning technology of solid intermediate level wastes, alpha-contaminated combustible wastes, gaseous wastes, hulls and dissolver residues and plutonium recovery; waste product evaluation which involves testing of solidified high level wastes and other waste products; engineering storage of vitrified high level wastes and gas storage; and geological disposal in salt, granite and clay formations which includes site characterization, conceptual repository design, waste/formation interactions, migration of radionuclides, safety analysis, mathematical modelling and risk assessment

Chemical decontamination of radioactive waste

International Nuclear Information System (INIS)

Mohamed, H.I.

2006-01-01

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)

Method for calcining radioactive wastes

International Nuclear Information System (INIS)

Bjorklund, W.J.; McElroy, J.L.; Mendel, J.E.

1979-01-01

A method for the preparation of radioactive wastes in a low leachability form involves calcining the radioactive waste on a fluidized bed of glass frit, removing the calcined waste to melter to form a homogeneous melt of the glass and the calcined waste, and then solidifying the melt to encapsulate the radioactive calcine in a glass matrix

Central processing and interim storage of radioactive wastes

International Nuclear Information System (INIS)

Wenger, J.P.

1996-01-01

Within the ZWILAG project, the buildings for the temporary storage of all categories of radioactive wastes including the spent fuel elements are being readied at a central location. The intermediate storage installations are enhanced by a conditioning and burning plant for weak radioactive operating waste from the nuclear power plants and from the area of responsibility of the state. (author) 2 figs

Evolution in radioactive waste countermeasures

International Nuclear Information System (INIS)

Moriguchi, Yasutaka

1984-01-01

The establishment of radioactive waste management measures is important to proceed further with nuclear power development. While the storage facility projects by utilities are in progress, large quantity of low level wastes are expected to arise in the future due to the decommissioning of nuclear reactors, etc. An interim report made by the committee on radioactive waste countermeasures to the Atomic Energy Commission is described as follows: the land disposal measures of ultra-low level and low level radioactive wastes, that is, the concept of level partitioning, waste management, the possible practice of handling wastes, etc.; the treatment and disposal measures of high level radioactive wastes and transuranium wastes, including task sharing among respective research institutions, the solidification/storage and the geological formation disposal of high level wastes, etc. (Mori, K.)

BN-350 decommissioning problems of radioactive waste management

International Nuclear Information System (INIS)

Galkin, A.; Tkachenko, V.

2002-01-01

Pursuant of modern concept on radioactive waste management applied in IAEA Member States all radioactive wastes produced during the BN-350 operation and decommissioning are subject to processing in order to be transformed to a form suitable for long-term storage and final disposal. The first two priority objectives for BN-350 reactor are as follows: cesium cleaning from sodium followed by sodium drain, and processing; processing of liquid and solid radioactive waste accumulated during BN-350 operation. Cesium cleaning from sodium and sodium processing to NaOH will be implemented under USA engineering and financial support. However the outputted product might be only subject to temporary storage under special conditions. Currently the problem is being solved on selection of technology for sodium hydroxide conversion to final product incorporated into cement-like matrix ready for disposal pursuant to existing regulatory requirements. Industrial installation is being designed for liquid radioactive waste processing followed by incorporation to cement matrix subject to further disposal. The next general objective is management of radioactive waste expected from BN-350 decommissioning procedure. Complex of engineering-radiation investigation that is being conducted at BN-350 site will provide estimation of solid and liquid radioactive waste that will be produced during the course of the BN-350 decommission. Radioactive wastes that will be produced may be shared for primary (metal structures of both reactor and reactor plant main and auxiliary systems equipment as well as construction wastes of dismantled biological protection, buildings and structures) and secondary (deactivation solutions, tools, materials, cloth, special accessory, etc.). Processing of produced radioactive wastes (including high activity waste) requires the use of special industrial facilities and construction of special buildings and structures for arrangement of facilities mentioned as well as for

ORNL radioactive waste operations

International Nuclear Information System (INIS)

Sease, J.D.; King, E.M.; Coobs, J.H.; Row, T.H.

1982-01-01

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

Microbial transformation of low-level radioactive waste

International Nuclear Information System (INIS)

Francis, A.J.

1980-06-01

Microorganisms play a significant role in the transformation of the radioactive waste and waste forms disposed of at shallow-land burial sites. Microbial degradation products of organic wastes may influence the transport of buried radionuclides by leaching, solubilization, and formation of organoradionuclide complexes. The ability of indigenous microflora of the radioactive waste to degrade the organic compounds under aerobic and anaerobic conditions was examined. Leachate samples were extracted with methylene chloried and analyzed for organic compounds by gas chromatography and mass spectrometry. In general, several of the organic compounds in the leachates were degraded under aerobic conditions. Under anaerobic conditions, the degradation of the organics was very slow, and changes in concentrations of several acidic compounds were observed. Several low-molecular-weight organic acids are formed by breakdown of complex organic materials and are further metabolized by microorganisms; hence these compounds are in a dynamic state, being both synthesized and destroyed. Tributyl phosphate, a compound used in the extraction of metal ions from solutions of reactor products, was not degraded under anaerobic conditions

Radioactive waste computerized management

International Nuclear Information System (INIS)

Communaux, M.; Lantes, B.

1993-01-01

Since December 31, 1990, the management of the nuclear wastes for all the power stations has been computerized, using the DRA module of the Power Generation and Transmission Group's data processing master plan. So now EDF has a software package which centralizes all the data, enabling it to declare the characteristics of the nuclear wastes which are to be stored on the sites operated by the National Radioactive Waste Management Agency (ANDRA). Among other uses, this application makes it possible for EDF, by real time data exchange with ANDRA, to constitute an inventory of validated, shippable packs. It also constitutes a data base for all the wastes produced on the various sites. This application was developed to meet the following requirements: give the producers of radioactive waste a means to fully manage all the characteristics and materials that are necessary to condition their waste correctly; guarantee the traceability and safety of data and automatically assure the transmission of this data in real time between the producers and the ANDRA; give the Central Services of EDF an operation and statistical tool permitting an experienced feed-back based on the complete national production (single, centralized data base); and integrate the application within the products of the processing master plan in order to assure its maintenance and evolution

Systematic handling of requirements and conditions (in compliance with waste acceptance requirements for a radioactive waste disposal facility)

International Nuclear Information System (INIS)

Keyser, Peter; Helander, Anita

2012-01-01

This Abstract and presentation will demonstrate the need for a structured requirement management and draw upon experiences and development from SKB requirements data base and methodology, in addition to international guidelines and software tools. The presentation will include a discussion on how requirement management can be applied for the decommissioning area. The key issue in the decommissioning of nuclear facilities is the progressive removal of hazards, by stepwise decontamination and dismantling activities that have to be carried out safely and within the boundaries of an approved safety case. For decommissioning there exists at least two safety cases, one for the pre-disposal activities and one for the disposal facility, and a need for a systematic handling of requirements and conditions to safely manage the radioactive waste in the long term. The decommissioning safety case is a collection of arguments and evidence to demonstrate the safety of a decommissioning project. It also includes analyzing and updating the decommissioning safety case in accordance with the waste acceptance criteria's and the expected output, i.e. waste packages. It is a continuous process to confirm that all requirements have been met. On the other hand there is the safety case for a radioactive waste disposal facility, which may include the following processes and requirements: i) Integrating relevant scientific (and other) information in a structured, traceable and transparent way and, thereby, developing and demonstrating an understanding of the potential behavior and performance of the disposal system; ii) Identifying uncertainties in the behavior and performance of the disposal system, describing the possible significance of the uncertainties, and identifying approaches for the management of significant uncertainties; iii) Demonstrating long-term safety and providing reasonable assurance that the disposal facility will perform in a manner that protects human health and the

Radioactive Waste.

Science.gov (United States)

Blaylock, B. G.

1978-01-01

Presents a literature review of radioactive waste disposal, covering publications of 1976-77. Some of the studies included are: (1) high-level and long-lived wastes, and (2) release and burial of low-level wastes. A list of 42 references is also presented. (HM)

SE-VYZ - Decommissioning of Nuclear Installations, Radioactive Waste and Spent Fuel Management

International Nuclear Information System (INIS)

Anon

2004-01-01

In this presentations processes of radioactive waste treatment in the Bohunice Radioactive Waste Processing Center (SE-VYZ), Jaslovske Bohunice are presented. Decommissioning of the A-1 NPP is also presented. Disposal of conditioned radioactive waste in fibre concrete containers (FCC) are transported to Mochovce from Jaslovske Bohunice by the transport truck where are reposited in the National radioactive waste repository Mochovce. The Interim spent fuel storage facility (ISFSF) is included into this presentation

Overview of the solid radioactive waste management programme for Cernavoda NPP

International Nuclear Information System (INIS)

Raducea, D.

2001-01-01

The wastes generated from nuclear power plants have a very large diversity, and can be grouped into non-radioactive and radioactive wastes. These two types are manipulated completely different ways from each other. Among radioactive wastes, solid radioactive wastes are important, because of their diversity, their method of treatment and of their volume compared to the others types. The strategy for their treatment and characterisation has a dynamic character and allows modification after the identification of new solutions at the international level, or after the production of new waste types. The Radioactive Waste Management concept for Cernavoda NPP established the general approach required for the collection, handling, conditioning and storage of radioactive wastes, while maintaining acceptable levels of safety for workers, members of the public and the environment. The radioactive waste management programme has the following major characteristics: plant operation at all times ensures that radioactive wastes are minimised; procedures are established to ensure that radiation doses to operating staff and members of the public are in accordance with ALARA and contamination from collection, transportation and storage of wastes are eliminated; all staff is trained and qualified to carry out their responsibilities. This presentation does not address the management of spent fuel, contaminated heavy water and the disposal of the solid radioactive wastes.(author)

Fusion reactor radioactive waste management

International Nuclear Information System (INIS)

Kaser, J.D.; Postma, A.K.; Bradley, D.J.

1976-01-01

Quantities and compositions of non-tritium radioactive waste are estimated for some current conceptual fusion reactor designs, and disposal of large amounts of radioactive waste appears necessary. Although the initial radioactivity of fusion reactor and fission reactor wastes are comparable, the radionuclides in fusion reactor wastes are less hazardous and have shorter half-lives. Areas requiring further research are discussed

radioactive waste disposal standards abroad

International Nuclear Information System (INIS)

Lu Yan; Xin Pingping; Wu Jian; Zhang Xue

2012-01-01

With the world focus on human health and environmental protection, the problem of radioactive waste disposal has gradually become a global issue, and the focus of attention of public. The safety of radioactive waste disposal, is not only related to human health and environmental safety, but also an important factor of affecting the sustainable development of nuclear energy. In recent years the formulation of the radioactive waste disposal standards has been generally paid attention to at home and abroad, and it has made great progress. In China, radioactive waste management standards are being improved, and there are many new standards need to be developed. The revised task of implement standards is very arduous, and there are many areas for improvement about methods and procedures of the preparation of standards. This paper studies the current situation of radioactive waste disposal standards of the International Atomic Energy Agency, USA, France, Britain, Russia, Japan, and give some corresponding recommendations of our radioactive waste disposal standards. (authors)

Disposal facility for radioactive wastes

International Nuclear Information System (INIS)

Utsunomiya, Toru.

1985-01-01

Purpose: To remove heat generated from radioactive wastes thereby prevent the working circumstances from being worsened in a disposal-facility for radioactive wastes. Constitution: The disposal-facility comprises a plurality of holes dug out into the ground inside a tunnel excavated for the storage of radioactive wastes. After placing radioactive wastes into the shafts, re-filling materials are directly filled with a purpose of reducing the dosage. Further, a plurality of heat pipes are inserted into the holes and embedded within the re-filling materials so as to gather heat from the radioactive wastes. The heat pipes are connected to a heat exchanger disposed within the tunnel. As a result, heating of the solidified radioactive wastes itself or the containing vessel to high temperature can be avoided, as well as thermal degradation of the re-filling materials and the worsening in the working circumstance within the tunnel can be overcome. (Moriyama, K.)

USING STATISTICAL PROCESS CONTROL TO MONITOR RADIOACTIVE WASTE CHARACTERIZATION AT A RADIOACTIVE FACILITY

International Nuclear Information System (INIS)

WESTCOTT, J.L.

2006-01-01

Two facilities for storing spent nuclear fuel underwater at the Hanford site in southeastern Washington State being removed from service, decommissioned, and prepared for eventual demolition. The fuel-storage facilities consist of two separate basins called K East (KE) and K West (KW) that are large subsurface concrete pools filled with water, with a containment structure over each. The basins presently contain sludge, debris, and equipment that have accumulated over the years. The spent fuel has been removed from the basins. The process for removing the remaining sludge, equipment, and structure has been initiated for the basins. Ongoing removal operations generate solid waste that is being treated as required, and then disposed. The waste, equipment and building structures must be characterized to properly manage, ship, treat (if necessary), and dispose as radioactive waste. As the work progresses, it is expected that radiological conditions in each basin may change as radioactive materials are being moved within and between the basins. It is imperative that these changing conditions be monitored so that radioactive characterization of waste is adjusted as necessary

USING STATISTICAL PROCESS CONTROL TO MONITOR RADIOACTIVE WASTE CHARACTERIZATION AT A RADIOACTIVE FACILITY

International Nuclear Information System (INIS)

WESTCOTT, J.L.; JOCHEN; PREVETTE

2007-01-01

Two facilities for storing spent nuclear fuel underwater at the Hanford site in southeastern Washington State are being removed from service, decommissioned, and prepared for eventual demolition. The fuel-storage facilities consist of two separate basins called K East (KE) and K West (KW) that are large subsurface concrete pools filled with water, with a containment structure over each. The basins presently contain sludge, debris, and equipment that have accumulated over the years. The spent fuel has been removed from the basins. The process for removing the remaining sludge, equipment, and structure has been initiated for the basins. Ongoing removal operations generate solid waste that is being treated as required, and then disposed. The waste, equipment and building structures must be characterized to properly manage, ship, treat (if necessary), and dispose as radioactive waste. As the work progresses, it is expected that radiological conditions in each basin may change as radioactive materials are being moved within and between the basins. It is imperative that these changing conditions be monitored so that radioactive characterization of waste is adjusted as necessary

Contribution to Radioactive Waste Management in Croatia

International Nuclear Information System (INIS)

Hudec, M.; Frgic, L.; Sunjerga, S.

2002-01-01

The problem of dangerous waste disposal in Croatia is not more only technical problem; it grew over to political one of the first degree. Nobody likes to have the repository in own courtyard. Some five hundred institutions and factories produce in Croatia low, intermediate or high level radioactive waste. Till now all the dangerous waste is keeping in basements of the institute Rudjer Boskovic in Zagreb, just one kilometre form the city centre. This temporary solution is working fore some fifty years, but cannot be conserved forever. In the paper are presented some of the solutions for radioactive waste deposition, known from the references. The deep, impermeable layers in Panonian area have conserved petroleum and gas under pressure of more hundred bars for few dozens millions of years. Therefore, we propose the underground deposition of radioactive waste in deep boreholes. The liquid waste can be injected in deep isolated layers. In USA and Russia, for many years such solutions are realised. In USA exist special regulations for this kind of waste management. In the paper is described the procedure of designing, execution and verification of deposition in Russia. In northern part of Croatia exist thousand boreholes with known geological data. The boreholes were executed for investigation and exploitation of oil and gas fields. This data can make good use to define safe deep layers capable to be used for repositories of liquid waste. For the high level radioactive waste we propose the deep boreholes of greater diameter, filled with containers. One borehole with 50 cm diameter and 1000 m deep can be safe deposition for c/a 50 m3 of solid high level radioactive waste. Croatia has not big quantity of waste and some boreholes can satisfy all the quantities of waste in Croatia. This is not the cheapest solution, but it can satisfy the strongest conditions of safety. (author)

Radioactive Waste Management BasisSept 2001

International Nuclear Information System (INIS)

Goodwin, S.S.

2011-01-01

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 RWMB 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 meeeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Methodology development for radioactive waste treatment of CDTN/BR - liquid low-level radioactive wastes

International Nuclear Information System (INIS)

Morais, Carlos Antonio de

1996-01-01

The radioactive liquid wastes generated in Nuclear Technology Development Centre (CDTN) were initially treated by precipitation/filtration and then the resulting wet solid wastes were incorporated in cement. These wastes were composed of different chemicals and different radioactivities and were generated by different sectors. The objective of the waste treatment method was to obtain minimum wet solid waste volume and decontamination and minimum operational cost. The composition of the solid wastes were taken into consideration for compatible cementation process. Approximately 5,400 litres of liquid radioactive wastes were treated by this process during 1992-1995. The volume reduction was 1/24 th and contained 20% solids. (author)

Radioactive waste: show time? - 16309

International Nuclear Information System (INIS)

Codee, Hans; Verhoef, Ewoud

2009-01-01

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)

Radioactive waste management at Cernavoda NPP after 5 years of experience

International Nuclear Information System (INIS)

Raducea, D.

2002-01-01

Many human activities generate waste but people are worried about those produced in nuclear power plants. Their concern is an unjustified fear toward the hazard from radioactive wastes because any country, which produces electrical power in this way, pays a lot of attention of all relevant parties involved in radioactive waste management. The same policy is applied for Cernavoda NPP. Our concept establishes the general approach required for the collection, handling, conditioning and storage of radioactive waste from Cernavoda NPP Unit 1 and will be ready for expansion when other units are brought into service. Among others, a major objective is to reduce the radioactive waste production and volume. In this regard we are trying to improve as much as possible our procedures and radioactive wastes management. Further, it will be presented the radioactive waste management, including the improvements in our program and the future plans.(author)

Radioactive Waste Conditioning, Immobilisation, And Encapsulation Processes And Technologies: Overview And Advances (Chapter 7)

Energy Technology Data Exchange (ETDEWEB)

Jantzen, Carol M. [Savannah River National Lab., Aiken SC (United States); Lee, William E. [Imperial College, London (United Kingdom). Dept. of Materials; Ojovan, Michael I. [Univ. of Sheffield (United Kingdom). Dept. of Materials Science and Engineering

2012-10-19

The main immobilization technologies that are available commercially and have been demonstrated to be viable are cementation, bituminization, and vitrification. Vitrification is currently the most widely used technology for the treatment of high level radioactive wastes (HLW) throughout the world. Most of the nations that have generated HLW are immobilizing in either alkali borosilicate glass or alkali aluminophosphate glass. The exact compositions of nuclear waste glasses are tailored for easy preparation and melting, avoidance of glass-in-glass phase separation, avoidance of uncontrolled crystallization, and acceptable chemical durability, e.g., leach resistance. Glass has also been used to stabilize a variety of low level wastes (LLW) and mixed (radioactive and hazardous) low level wastes (MLLW) from other sources such as fuel rod cladding/decladding processes, chemical separations, radioactive sources, radioactive mill tailings, contaminated soils, medical research applications, and other commercial processes. The sources of radioactive waste generation are captured in other chapters in this book regarding the individual practices in various countries (legacy wastes, currently generated wastes, and future waste generation). Future waste generation is primarily driven by interest in sources of clean energy and this has led to an increased interest in advanced nuclear power production. The development of advanced wasteforms is a necessary component of the new nuclear power plant (NPP) flowsheets. Therefore, advanced nuclear wasteforms are being designed for robust disposal strategies. A brief summary is given of existing and advanced wasteforms: glass, glass-ceramics, glass composite materials (GCM’s), and crystalline ceramic (mineral) wasteforms that chemically incorporate radionuclides and hazardous species atomically in their structure. Cementitious, geopolymer, bitumen, and other encapsulant wasteforms and composites that atomically bond and encapsulate

Optimisation of treatment, storage and disposal strategies for (unconditioned and conditioned) radioactive waste

International Nuclear Information System (INIS)

Bealby, J.

1989-03-01

This study examines the trade-offs involved between unconditioned and conditioned waste storage, by investigating the effects of different cost and environmental minimisation strategies on radioactive waste treatment and disposal strategies. The costs and environmental impacts from storage (unconditioned and conditioned), conditioning, transport and disposal are examined. A single generic mixed Magnox/AGR site is investigated, assuming a moderate nuclear power growth scenario over the period 1986 to 2030. Assessments have been performed for four weighting sets which cover the range of views perceived to exist about the relative importance of cost and environmental impact reduction. The base case conditioning option considers the availability of a LLW low force compaction plant in 1986 and two ILW conditioning plants (cement encapsulation and dissolution) in 1990. A base case set of disposal options considers the options of disposal to shallow land and burial facility and deep cavity facilities. The study investigates the effect of deferring the opening dates of the conditioning plants. A set of sensitivity studies show that the assessments are robust to the assumptions and impact parameters used. (author)

Public acceptance in radioactive waste management

International Nuclear Information System (INIS)

Diaconu, Stela; Covreag, Ilinca

2008-01-01

Radioactive waste, unavoidable by-products of economically developed societies, arises from the production of energy by nuclear fission reactors as well as from medical, research and industrial applications of radioactive materials. The main objective of radioactive waste management is the safety as well the protection of public health and the environment. The first approach for the disposal of radioactive waste was based on the traditional 'decide, announce and defend' model, focused almost exclusively on technical content. In spite of the significant technical progress that would ensure long-term safety, the rate of progress towards implementing such solutions has been slower than expected, partly attributable to an earlier technical optimism and to an underestimation of the societal and political dimensions. It is now broadly recognized that radioactive waste management involves both technical and societal dimensions which cannot be dissociated. Because of changes in society's decision-making environment and heightened public sensitivity to all matters connected with environmental protection, nuclear power, radioactivity, and especially radioactive waste, any decision regarding whether, when and how to implement waste management solutions will typically require thorough public examination and the involvement of many relevant stakeholders. The building of a long-term relationship with the local communities and the waste management facility is one of the most important contributors to sustainable radioactive waste management solutions. A new approach in now in place at international level, based on 'engage, interact and co-operate', for which both technical and societal issues are to be reconciled. That means that the involvement of all interested parties in the decision-making process is a condition for a successful and publicly acceptable implementation of such a project. A central role in the public acceptance of nuclear technologies play the management and

Technological and organizational aspects of radioactive waste management

International Nuclear Information System (INIS)

2005-01-01

This document comprises collected lecture on radioactive waste management which were given by specialists of the Radioactive Waste Management Section of the IAEA, scientific-industrial enterprise 'Radon' (Moscow, RF) and A.A. Bochvar's GNTs RF VNIINM (Moscow, RF) on various courses, seminars and conferences. These lectures include the following topics: basic principles and national systems of radioactive waste management; radioactive waste sources and their classification; collection, sorting and initial characterization of radioactive wastes; choice of technologies of radioactive waste processing and minimization of wastes; processing and immobilization of organic radioactive wastes; thermal technologies of radioactive waste processing; immobilization of radioactive wastes in cements, asphalts, glass and polymers; management of worked out closed radioactive sources; storage of radioactive wastes; deactivation methods; quality control and assurance in radioactive waste management

Formation of stable uranium(VI) colloidal nanoparticles in conditions relevant to radioactive waste disposal.

Science.gov (United States)

Bots, Pieter; Morris, Katherine; Hibberd, Rosemary; Law, Gareth T W; Mosselmans, J Frederick W; Brown, Andy P; Doutch, James; Smith, Andrew J; Shaw, Samuel

2014-12-09

The favored pathway for disposal of higher activity radioactive wastes is via deep geological disposal. Many geological disposal facility designs include cement in their engineering design. Over the long term, interaction of groundwater with the cement and waste will form a plume of a hyperalkaline leachate (pH 10-13), and the behavior of radionuclides needs to be constrained under these extreme conditions to minimize the environmental hazard from the wastes. For uranium, a key component of many radioactive wastes, thermodynamic modeling predicts that, at high pH, U(VI) solubility will be very low (nM or lower) and controlled by equilibrium with solid phase alkali and alkaline-earth uranates. However, the formation of U(VI) colloids could potentially enhance the mobility of U(VI) under these conditions, and characterizing the potential for formation and medium-term stability of U(VI) colloids is important in underpinning our understanding of U behavior in waste disposal. Reflecting this, we applied conventional geochemical and microscopy techniques combined with synchrotron based in situ and ex situ X-ray techniques (small-angle X-ray scattering and X-ray adsorption spectroscopy (XAS)) to characterize colloidal U(VI) nanoparticles in a synthetic cement leachate (pH > 13) containing 4.2-252 μM U(VI). The results show that in cement leachates with 42 μM U(VI), colloids formed within hours and remained stable for several years. The colloids consisted of 1.5-1.8 nm nanoparticles with a proportion forming 20-60 nm aggregates. Using XAS and electron microscopy, we were able to determine that the colloidal nanoparticles had a clarkeite (sodium-uranate)-type crystallographic structure. The presented results have clear and hitherto unrecognized implications for the mobility of U(VI) in cementitious environments, in particular those associated with the geological disposal of nuclear waste.

Solid and liquid radioactive wastes

International Nuclear Information System (INIS)

Cluchet, J.; Desroches, J.

1977-01-01

The problems raised by the solid and liquid radioactive wastes from the CEA nuclear centres are briefly exposed. The processing methods developed at the Saclay centre are described together with the methods for the wastes from nuclear power plants and reprocessing plants. The different storage techniques used at the La Hague centre are presented. The production of radioactive wastes by laboratories, hospitals and private industry is studied for the sealed sources and the various radioactive substances used in these plants. The cost of the radioactive wastes is analysed: processing, transport, long term storage [fr

Activities of the IAEA in the area of radioactive waste management

International Nuclear Information System (INIS)

Efremenkov, V.M.

1998-01-01

The IAEA activity in the area of radioactive waste management mainly concentrates on three areas, namely: (i) the establishing of international principles and standards for the safe management of radioactive waste; (ii) to promote the development and improvements of waste processing technologies, including handling, treatment, conditioning, packaging, storage and disposal of waste; and (iii) assisting developing Member States in establishing good waste management practice through dissemination of technical information, providing technical support and training. These activities are carried out by the Waste Technology Section, Department of Nuclear Energy, and the Waste Safety Section, Department of Nuclear Safety. The Waste Technology Section's activities are organized into four subprogrammes covering: the handling, processing and storage of radioactive waste; radioactive waste disposal; technology and management aspects of decontamination, decommissioning and environmental restoration; and waste management information and support services

Radioactive wastes in Oklo

International Nuclear Information System (INIS)

Balcazar, M.; Flores R, J.H.; Pena, P.; Lopez, A.

2006-01-01

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

Thermal treatment of organic radioactive waste

International Nuclear Information System (INIS)

Chrubasik, A.; Stich, W.

1993-01-01

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

Management situation and prospect of radioactive waste

International Nuclear Information System (INIS)

Han, Pil Jun

1985-04-01

This book tell US that management situation and prospect of radioactive waste matter, which includes importance of energy, independence, limitation of fossil fuel energy, density of nuclear energy, strategy of supply of energy resource in Korea, nuclear energy development and radioactive waste matter, summary of management of radioactive waste, statistics of radioactive waste, disposal principle of radioactive waste, management on radioactive waste after using, disposal of Trench, La Marche in French, and Asse salt mine in Germany.

Radioactive waste management policy

International Nuclear Information System (INIS)

Morrison, R.W.

1983-06-01

The speaker discusses the development of government policy regarding radioactive waste disposal in Canada, indicates overall policy objectives, and surveys the actual situation with respect to radioactive wastes in Canada. He also looks at the public perceptions of the waste management situation and how they relate to the views of governmental decision makers

Disposal of radioactive wastes. Chapter 11

International Nuclear Information System (INIS)

Skitt, J.

1979-01-01

An account is given of the history and present position of legislation in the United Kingdom on the disposal of radioactive wastes. The sections are headed: introduction and definitions; history; the Radioactive Substances Act 1960; disposal of solid radioactive wastes through Local Authority services; function of Local Authorities; exemptions; national radioactive waste disposal service; incidents involving radioactivity. (U.K.)

Estimation of global inventories of radioactive waste and other radioactive materials

International Nuclear Information System (INIS)

2008-06-01

A variety of nuclear activities have been carried out in the second part of the twentieth century for different purposes. Initially the emphasis was on military applications, but with the passage of time the main focus of nuclear activities has shifted to peaceful uses of nuclear energy and to the use of radioactive material in industry, medicine and research. Regardless of the objectives, the nuclear activities generate radioactive waste. It was considered worthwhile to produce a set of worldwide data that could be assessed to evaluate the legacy of the nuclear activities performed up to the transition between the twentieth and the twenty first century. The assessment tries to cover the inventory of all the human produced radioactive material that can be considered to result from both military and civilian applications. This has caused remarkable difficulties since much of the data, particularly relating to military programmes, are not readily available. Consequently the data on the inventory of radioactive material should be considered as order-of-magnitude approximations. This report as a whole should be considered as a first iteration in a continuing process of updating and upgrading. The accumulations of radioactive materials can be considered a burden for human society, both at present and in the future, since they require continuing monitoring and control. Knowing the amounts and types of such radioactive inventories can help in the assessment of the relative burdens. Knowledge of the national or regional radioactive waste inventory is necessary for planning management operations, including the sizing and design of conditioning, storage and disposal facilities. A global inventory, either of radioactive waste or of other environmental accumulations of radioactive material, could be used to provide a perspective on the requirements and burdens associated with their management, by means of comparisons with the burdens caused by other types of waste or other

Handbook of high-level radioactive waste transportation

International Nuclear Information System (INIS)

Sattler, L.R.

1992-10-01

The High-Level Radioactive Waste Transportation Handbook serves as a reference to which state officials and members of the general public may turn for information on radioactive waste transportation and on the federal government's system for transporting this waste under the Civilian Radioactive Waste Management Program. The Handbook condenses and updates information contained in the Midwestern High-Level Radioactive Waste Transportation Primer. It is intended primarily to assist legislators who, in the future, may be called upon to enact legislation pertaining to the transportation of radioactive waste through their jurisdictions. The Handbook is divided into two sections. The first section places the federal government's program for transporting radioactive waste in context. It provides background information on nuclear waste production in the United States and traces the emergence of federal policy for disposing of radioactive waste. The second section covers the history of radioactive waste transportation; summarizes major pieces of legislation pertaining to the transportation of radioactive waste; and provides an overview of the radioactive waste transportation program developed by the US Department of Energy (DOE). To supplement this information, a summary of pertinent federal and state legislation and a glossary of terms are included as appendices, as is a list of publications produced by the Midwestern Office of The Council of State Governments (CSG-MW) as part of the Midwestern High-Level Radioactive Waste Transportation Project

Conditioning of intermediate-level waste at Forschungszentrum Juelich GmbH

International Nuclear Information System (INIS)

Krumbach, H.

2003-01-01

This contribution to the group of low-level, intermediate, mixed and hazardous waste describes the conditioning of intermediate-level mixed waste (dose rate above 10 mSv/h at the surface) from Research Centre Juelich (FZJ). Conditioning of the waste by supercompaction is performed at Research Centre Karlsruhe (FZK). The waste described is radioactive waste arising from research at Juelich. This waste includes specimens and objects from irradiation experiments in the research reactors Merlin (FRJ-1) and Dido (FRJ-2) at FZJ. In principle, radioactive waste at Forschungszentrum Juelich GmbH is differentiated by the surface dose rate at the waste package. Up to a surface dose rate of 10 mSv/h, the waste is regarded as low-level. The radioactive waste described here has a surface dose rate above 10 mSv/h. Waste up to 10 mSv/h is conditioned at the Juelich site according to different conditioning methods. The intermediate-level waste can only be conditioned by supercompaction in the processing facility for intermediate-level waste from plant operation at Research Centre Karlsruhe. Research Centre Juelich also uses this waste cell to condition its intermediate-level waste from plant operation. (orig.)

Conditions for the test emplacement of intermediate-level radioactive wastes in chamber 8a of the 511 m level of the Asse Salt Mine

International Nuclear Information System (INIS)

1984-01-01

The Gesellschaft fuer Strahlen- und Umweltforschung mbH (GSF) emplaces intermediate-level radioactive wastes which accumulate in an activity involving the use of radioactive materials that is licensed or reported in the Federal Republic of Germany or which are stored on an interim basis by the appropriate licensing or inspection agencies in chamber 8a of the 511 m level of the Asse Salt Mine in Remlingen near Wolfenbuettel in conjunction with an engineering test program. The type and form of the intermediate-level wastes must conform to certain conditions so that there are no hazards to personnel and the repository during transfer and subsequent storage. It is therefore necessary for the radioactive wastes to be treated and packaged before delivery in such a way that they satisfy the conditions presented in this document. The GSF shall inform the companies and organizations delivering wastes about its experiences with emplacement operations. The Conditions for the Test Emplacement of Intermediate-Level Radioactive Wastes in Chamber 8a of the 511 m Level of the Asse Salt Mine must be adapted to conform to the latest state of science and the art. The GSF must therefore reserve the right to modify the conditions, allowing for an appropriate transition period

Radioactive waste management in Mexico

International Nuclear Information System (INIS)

Paredes, L.; Reyes L, J.; Jimenez D, J.

2000-01-01

This paper describes the radioactive waste management in Mexico, particularly the activities that the National Institute of Nuclear Research (NINR) is undertaking in this field. Classification and annual generation of radioactive waste, together with practices and facilities relating to the management of radioactive waste are addressed. The respective national legal framework and policy are outlined. (author)

Radioactive waste problems in Russia

International Nuclear Information System (INIS)

Bridges, O.; Bridges, J.W.

1995-01-01

The collapse of the former Soviet Union, with the consequent shift to a market driven economy and demilitarisation, has had a profound effect on the nuclear and associated industries. The introduction of tighter legislation to control the disposal of radioactive wastes has been delayed and the power and willingness of the various government bodies responsible for its regulation is in doubt. Previously secret information is becoming more accessible and it is apparent that substantial areas of Russian land and surface waters are contaminated with radioactive material. The main sources of radioactive pollution in Russia are similar to those in many western countries. The existing atomic power stations already face problems in the storage and safe disposal of their wastes. These arise because of limited on site capacity for storage and the paucity of waste processing facilities. Many Russian military nuclear facilities also have had a sequence of problems with their radioactive wastes. Attempts to ameliorate the impacts of discharges to important water sources have had variable success. Some of the procedures used have been technically unsound. The Russian navy has traditionally dealt with virtually all of its radioactive wastes by disposal to sea. Many areas of the Barents, Kola and the Sea of Japan are heavily contaminated. To deal with radioactive wastes 34 large and 257 small disposal sites are available. However, the controls at these sites are often inadequate and illegal dumps of radioactive waste abound. Substantial funding will be required to introduce the necessary technologies to achieve acceptable standards for the storage and disposal of radioactive wastes in Russia. (author)

Radioactive waste management from nuclear facilities

International Nuclear Information System (INIS)

2005-06-01

This report has been published as a NSA (Nuclear Systems Association, Japan) commentary series, No. 13, and documents the present status on management of radioactive wastes produced from nuclear facilities in Japan and other countries as well. Risks for radiation accidents coming from radioactive waste disposal and storage together with risks for reactor accidents from nuclear power plants are now causing public anxiety. This commentary concerns among all high-level radioactive waste management from nuclear fuel cycle facilities, with including radioactive wastes from research institutes or hospitals. Also included is wastes produced from reactor decommissioning. For low-level radioactive wastes, the wastes is reduced in volume, solidified, and removed to the sites of storage depending on their radioactivities. For high-level radioactive wastes, some ten thousand years must be necessary before the radioactivity decays to the natural level and protection against seismic or volcanic activities, and terrorist attacks is unavoidable for final disposals. This inevitably results in underground disposal at least 300 m below the ground. Various proposals for the disposal and management for this and their evaluation techniques are described in the present document. (S. Ohno)

Method of processing radioactive metal wastes

International Nuclear Information System (INIS)

Inoue, Yoichi; Kitagawa, Kazuo; Tsuzura, Katsuhiko.

1980-01-01

Purpose: To enable long and safety storage for radioactive metal wastes such as used fuel cans after the procession or used pipe, instruments and the likes polluted with various radioactive substances, by compacting them to solidify. Method: Metal wastes such as used fuel cans, which have been cut shorter and reprocessed, are pressed into generally hexagonal blocks. The block is charged in a capsule of a hexagonal cross section made of non-gas permeable materials such as soft steels, stainless steels and the likes. Then, the capsule is subjected to static hydraulic hot pressing as it is or after deaeration and sealing. While various combinations are possible for temperature, pressure and time as the conditions for the static hydraulic hot pressing, dense block with no residual gas pores can be obtained, for example, under the conditions of 900 0 C, 1000 Kg/cm 2 and one hour where the wastes are composed of zircaloy. (Kawakami, Y.)

Classification of radioactive waste

International Nuclear Information System (INIS)

1994-01-01

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

Handling and treatment of radioactive aqueous wastes

International Nuclear Information System (INIS)

1992-07-01

This report aims to provide essential guidance to developing Member States without a nuclear power programme regarding selection, design and operation of cost effective treatment processes for radioactive aqueous liquids arising as effluents from small research institutions, hospitals and industries. The restricted quantities and low activity associated with the relevant wastes will generally permit contact-handling and avoid the need for shielding requirements. The selection of liquid waste treatment involves: Characterization of arising with the possibility of segregation; Discharge requirements for decontaminated liquors, both radioactive and non-radioactive; Available technologies and costs; Conditioning of the concentrates resulting from the treatment; Storage and disposal of the conditioned concentrates. 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. Therefore, emphasis is limited to the simpler treatment facilities, which will be included with only the robust, well-established waste management processes carefully chosen as appropriate to developing countries. 20 refs, 12 figs, 7 tabs

Safety of radioactive waste management in France

International Nuclear Information System (INIS)

Raimbault, P.

2002-01-01

Radioactive waste produced in France vary considerably by their activity level, their half lives, their volume or even their nature. In order to manage them safely, the treatment and final disposal solution must be adapted to the type of waste considered by setting up specific waste management channels. A strong principle in France is that it is the responsibility of the nuclear operators as waste producers to dispose of their waste or have them disposed of in a suitable manner. The competent authorities regulate and control the radioactive waste management activities. At present, only short-lived low and intermediate level waste have a definitive solution, the surface repository, where adequate waste packages are disposed of in concrete structures. Other types of radioactive waste are in interim storage facilities at the production sites. For very low level waste coming mainly from dismantling of nuclear facilities a dedicated repository is planned to be built in the coming years. Dedicated repositories are also planned for radiferous, tritiated and graphite waste. As for high level waste and long-lived waste coming mainly from reprocessing of spent nuclear fuel the disposal options are being sought along the lines specified by law 91-1381 concerning research on radioactive waste management, passed on December 30, 1991: research of solutions to partition and transmute long-lived radionuclides in the waste; studies of retrievable and non retrievable disposal in deep geological layers with the help of underground laboratories; studies of processes for conditioning and long term surface storage of these waste. In 2006, the French Parliament will assess the results of the research conducted by ANDRA relative to deep geological disposal as well as the work conducted by CEA in the two other areas of research and, if this research is conclusive, pass a law defining the final disposal option. (author)

Predisposal Management of Radioactive Waste from Nuclear Fuel Cycle Facilities. Specific Safety Guide

International Nuclear Information System (INIS)

2016-01-01

This Safety Guide provides guidance on the predisposal management of all types of radioactive waste (including spent nuclear fuel declared as waste and high level waste) generated at nuclear fuel cycle facilities. These waste management facilities may be located within larger facilities or may be separate, dedicated waste management facilities (including centralized waste management facilities). The Safety Guide covers all stages in the lifetime of these facilities, including their siting, design, construction, commissioning, operation, and shutdown and decommissioning. It covers all steps carried out in the management of radioactive waste following its generation up to (but not including) disposal, including its processing (pretreatment, treatment and conditioning). Radioactive waste generated both during normal operation and in accident conditions is considered

Investigation into the behaviour of highly compacted dry low-level radioactive waste under repository conditions. Task 3 characterization of radioactive waste forms a series of final reports (1985-89) no 12

International Nuclear Information System (INIS)

Field, S.N.; Wang, J.

1991-01-01

Supercompaction is a process in which drums containing low-level radioactive waste are compressed at a high axial pressure of up to 70 MPa, resulting in a significant saving in the volume of a repository built to store such waste. Recent practice of supercompaction is to compact waste which has been placed in a sealed primary container, typically a 200-litre steel drum. During the process of compaction the drum is squashed with its contents into a flat pellet; and the compaction ratio can reach as high as 20:1. Although the compaction of radioactive waste has long been a popular means for reducing its storage volume, there is virtually no available information as to the physical or chemical characteristics of such compacted wastes. The primary objective of this project has been to investigate the physical and some of the chemical characteristics of such supercompacted pellets. All the work was carried out on full-scale 200-litre drums of simulated, but non-radioactive, waste. The compaction ratio reached in this study ranged from 5 to 21, depending on the type of waste. Upon completion of compaction, all drums exhibited a tendency to expand. The magnitude of ultimate expansion for dry storage was of the order of 1 mm only, whereas under wet storage conditions values were up to about 10 mm. As the presence of moisture can significantly increase the expansion of compacted waste drums or stress developed due to restraint, it is recommended that the waste repository be made water/vapour-tight

Radioactive waste management in Korea

International Nuclear Information System (INIS)

Lee, Ik Hwan

1997-01-01

In order to meet the increasing energy demand in Korea, continuous promotion of nuclear power program will be inevitable in the future. However, the use of nuclear energy eventually requires effective and reliable radioactive waste management. For the safe and economical management of radioactive waste, first of all, volume reduction is essentially required and hence the development of related technologies continuously be pursued. A site for overall radioactive waste management has to be secured in Korea. KEPCO-NETEC will improve public understanding by reinforcing PA and will maintain transparency of radioactive waste management. (author). 1 fig

Radioactive waste management - a safe solution

International Nuclear Information System (INIS)

1993-01-01

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)

Anaerobic microbial transformations of radioactive wastes in subsurface environments

International Nuclear Information System (INIS)

Francis, A.J.

1984-01-01

Radioactive wastes disposed of in subsurface environments contain a variety of radionuclides and organic compounds. Microorganisms play a major role in the transformation of organic and inorganic constituents of the waste and are partly responsible for the problems encountered at the waste disposal sites. These include microbial degradation of waste forms resulting in trench cover subsidence, migration of radionuclides, and production of radioactive gases such as 14 CO 2 , 14 CH 4 , HT, and CH 3 T. Microbial processes involved in solubilization, mobilization, and immobilization of toxic metals under aerobic and anaerobic conditions are reviewed. Complexing agents and several organic acids produced by microbial action affect mobilization of radionuclides and heavy metals from the wastes. Microorganisms play a significant role in the transformation and cycling of tritium in the environment by (i) oxidation of tritium and tritiated methane under aerobic conditions and (ii) production of tritium and tritiated methane from wastes containing tritiated water and organic compounds under anaerobic conditions. 23 references, 2 figures, 2 tables

Radioactive waste below regulatory concern

International Nuclear Information System (INIS)

Neuder, S.M.

1987-01-01

The U.S. Nuclear Regulatory Commission (NRC) published two notices in the Federal Register concerning radioactive waste below regulatory concern. The first, a Commission Policy Statement and Implementation Plan published August 29, 1986, concerns petition to exempt specific radioactive waste streams from the regulations. The second, an Advanced Notice of Proposed Rulemaking published Decemger 2, 1986, addresses the concept of generic rulemaking by the NRC on radioactive wastes that are below regulatory concern. Radioactive waste determined to be below regulatory concern would not be subject to regulatory control and would not need to go to a licensed low-level radioactive waste disposal site. The Policy Statement and Implementation Plan describe (1) the information a petitioner should file in support of a petition to exempt a specific waste stream, (2) the decision criteria the Commission intends to use for judging the petition, and (3) the internal administrative procedures to use be followed in order to permit the Commission to act upon the petition in an expedited manner

Radioactive waste management - the Indian scenario

International Nuclear Information System (INIS)

Raj, Kanwar

2008-01-01

In India, nuclear power generation programme and application of radioisotopes for health care and various other application is increasing steadily. With resultant increase in generation of radioactive waste, emphasis is on the minimization of generation of radioactive waste by deploying suitable processes and materials, segregation of waste streams at sources, recycle and re-use of useful components of waste and use of volume reduction techniques. The minimization of the radioactive waste is also essential to facilitate judicious use of the scarce land available for disposal, to reduce impact on the environment due to disposal and, finally to optimize the cost of radioactive waste management. This paper presents a bird's eye view of radioactive waste management programme in the country today

Solidification method of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Baba, Tsutomu; Chino, Koichi; Sasahira, Akira; Ikeda, Takashi

1992-07-24

Metal solidification material can completely seal radioactive wastes and it has high sealing effect even if a trace amount of evaporation should be caused. In addition, the solidification operation can be conducted safely by using a metal having a melting point of lower than that of the decomposition temperature of the radioactive wastes. Further, the radioactive wastes having a possibility of evaporation and scattering along with oxidation can be solidified in a stable form by putting the solidification system under an inert gas atmosphere. Then in the present invention, a metal is selected as a solidification material for radioactive wastes, and a metal, for example, lead or tin having a melting point of lower than that of the decomposition temperature of the wastes is used in order to prevent the release of the wastes during the solidification operation. Radioactive wastes which are unstable in air and scatter easily, for example, Ru or the like can be converted into a stable solidification product by conducting the solidification processing under an inert gas atmosphere. (T.M.).

Radiological assessment of the radioactive wastes management

International Nuclear Information System (INIS)

Domenech Nieves, Haydee; Hernandez Saiz, Alejandro

1996-01-01

In the work are obtained the dose values resulting from the evaluation of the conditioning operations of wastes in the scenarios of exposure that are mentioned and are compared with the dose restriction suggested for the moment for such tasks. The radioactive wastes that are evaluated in the work are: liquids -both those from the generating institutions and the ones stored in the Managua- located deposit, Radon-226 not-in-use solids and sources 226: the results demonstrate that it is possible to treat in a year the total volume of the liquid and solid radioactive wastes as well as a large number of sources of Radon-226

Radioactive waste management practices in India

International Nuclear Information System (INIS)

Raj, Kanwar

2012-01-01

Different countries around the globe, especially those involved in nuclear power plant operation, spent fuel reprocessing, nuclear research activities and diverse nuclear applications; generate large inventory of radioactive wastes. These waste streams generated during various stages of nuclear fuel cycle are of different categories, which require special care for handling, treatment and conditioning. Conventional treatment and conditioning methods may not be efficient for various type of waste; therefore special options may be required to manage these waste streams. Presently, Indian waste management fraternity is focused to minimize the volume of the waste to be finally disposed off, by partitioning radionuclides, regenerating separation media and re-using as much of the waste components as possible and economically feasible. This approach, together with the reuse/recycling strategy, seems to represent a robust waste treatment strategy for the future

Regulation on radioactive waste management

International Nuclear Information System (INIS)

1999-01-01

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

The essential conditions for the choice of location for a long-term storage of radioactive wastes

International Nuclear Information System (INIS)

Markovic, V.

1964-10-01

The paper deals with a long-term storage of radioactive wastes with a special reference to the parameters to be considered in choosing the location. It gives a short account of methods for disposal of radioactive liquid and solid wastes used in nuclear centers in the world. The possibilities of radioactive wastes disposal in our country using the methods investigated are also presented (author)

Process for the encapsulation of radioactive wastes

International Nuclear Information System (INIS)

Pordes, O.; Plows, J.P.; Hill, M.L.

1980-01-01

Radioactive waste material, particularly radioactive ion exchange resin in the wet condition, is encapsulated in a polyurethane by dispersing the waste in an aqueous emulsion of an organic polyol, a polyisocyanate and an hydraulic cement and allowing the emulsion to set to form a monolithic block. If desired the emulsion may also contain additional filler e.g. sand or aggregate to increase the density of the final product. Preferred polyurethanes are those made from a polyester polyol and an organic diisocyanate, particularly hexamethylene diisocyanate. (author)

Destructive and non-destructive tests for radioactive waste packages Task 3 Characterization of radioactive waste forms. A series of final reports (1985-89) No 43

International Nuclear Information System (INIS)

Odoj, R.

1991-01-01

On the basis of preliminary waste acceptance requirements quality control of radioactive waste has to be performed prior to interim storage or final disposal. The quality control can either be achieved by random tests on conditioned radioactive waste packages or by process qualification of the conditioning processes. One of the most important criteria is the activity of the radioactive waste product or packages. To get some first information on the waste package γ-spectrometric measurement is performed as non-destructive test. Besides the γ-emitting nuclides the α and β-emitting nuclides can be estimated by calculation if the waste was generated in nuclear power plants and the nuclide relations are known. If the non-destructive determination of nuclides is not sufficient or the non-radioactive content of the waste packages has to be identified sampling from the waste packages has to be performed. This can best be done by core drilling. To avoid the need of water for cooling the drill head, air cooled core drilling is investigated. As mixed wastes is not allowed for final disposal the determination of possible organic toxic materials like PCB, dioxin and furane-compounds in cemented wastes is conducted by GC-MS-investigations. For getting more knowledge in the field of process qualification concerning super compaction, instrumentation of the super compaction process is investigated and tested

Prediction of radionuclide inventory for the low-and intermediated-level radioactive waste disposal facility the radioactive waste classification

International Nuclear Information System (INIS)

Jung, Kang Il; Jeong, Noh Gyeom; Moon, Young Pyo; Jeong, Mi Seon; Park, Jin Beak

2016-01-01

To meet nuclear regulatory requirements, more than 95% individual radionuclides in the low- and intermediate-level radioactive waste inventory have to be identified. In this study, the radionuclide inventory has been estimated by taking the long-term radioactive waste generation, the development plan of disposal facility, and the new radioactive waste classification into account. The state of radioactive waste cumulated from 2014 was analyzed for various radioactive sources and future prospects for predicting the long-term radioactive waste generation. The predicted radionuclide inventory results are expected to contribute to secure the development of waste disposal facility and to deploy the safety case for its long-term safety assessment

Law on the management of radioactive waste

International Nuclear Information System (INIS)

1999-01-01

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

Radioactive waste management in Tanzania

International Nuclear Information System (INIS)

Banzi, F.P.; Bundala, F.M.; Nyanda, A.M.; Msaki, P.

2002-01-01

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)

Progress in radioactive graphite waste management

International Nuclear Information System (INIS)

2010-07-01

Radioactive graphite constitutes a major waste stream which arises during the decommissioning of certain types of nuclear installations. Worldwide, a total of around 250 000 tonnes of radioactive graphite, comprising graphite moderators and reflectors, will require management solutions in the coming years. 14 C is the radionuclide of greatest concern in nuclear graphite; it arises principally through the interaction of reactor neutrons with nitrogen, which is present in graphite as an impurity or in the reactor coolant or cover gas. 3 H is created by the reactions of neutrons with 6 Li impurities in graphite as well as in fission of the fuel. 36 Cl is generated in the neutron activation of chlorine impurities in graphite. Problems in the radioactive waste management of graphite arise mainly because of the large volumes requiring disposal, the long half-lives of the main radionuclides involved and the specific properties of graphite - such as stored Wigner energy, graphite dust explosibility and the potential for radioactive gases to be released. Various options for the management of radioactive graphite have been studied but a generally accepted approach for its conditioning and disposal does not yet exist. Different solutions may be appropriate in different cases. In most of the countries with radioactive graphite to manage, little progress has been made to date in respect of the disposal of this material. Only in France has there been specific thinking about a dedicated graphite waste-disposal facility (within ANDRA): other major producers of graphite waste (UK and the countries of the former Soviet Union) are either thinking in terms of repository disposal or have no developed plans. A conference entitled 'Solutions for Graphite Waste: a Contribution to the Accelerated Decommissioning of Graphite Moderated Nuclear Reactors' was held at the University of Manchester 21-23 March 2007 in order to stimulate progress in radioactive graphite waste management

Security of Radioactive Waste

International Nuclear Information System (INIS)

Goldammer, W.

2003-01-01

Measures to achieve radioactive waste security are discussed. Categorization of waste in order to implement adequate and consistent security measures based on potential consequences is made. The measures include appropriate treatment/storage/disposal of waste to minimize the potential and consequences of malicious acts; management of waste only within an authorised, regulated, legal framework; management of the security of personnel and information; measures to minimize the acquisition of radioactive waste by those with malicious intent. The specific measures are: deter unauthorized access to the waste; detect any such attempt or any loss or theft of waste; delay unauthorized access; provide timely response to counter any attempt to gain unauthorised access; measures to minimize acts of sabotage; efforts to recover any lost or stolen waste; mitigation and emergency plans in case of release of radioactivity. An approach to develop guidance, starting with the categorisation of sources and identification of dangerous sources, is presented. Dosimetric criteria for internal and external irradiation are set. Different exposure scenarios are considered. Waste categories and security categories based on the IAEA INFCIRC/225/Rev.4 are presented

Radioactive Waste Technical and Normative Aspects of its Disposal

CERN Document Server

Streffer, Christian; Kamp, Georg; Kröger, Wolfgang; Rehbinder, Eckard; Renn, Ortwin; Röhlig, Klaus-Jürgen

2012-01-01

Waste caused by the use of radioactive material in research, medicine and technologies, above all high level waste from nuclear power plants, must be disposed of safely. However, the strategies discussed for the disposal of radioactive waste as well as proposals for choosing a proper site for final waste disposal are strongly debated. An appropriate disposal must satisfy complex technical requirements and must meet stringent conditions to appropriately protect man and nature from risks of radioactivity over very long periods. Ethical, legal and social conditions must be considered as well. An interdisciplinary team of experts from relevant fields compiled the current status and developed criteria as well as strategies which meet the requirements of safety and security for present and future generations. The study also provides specific recommendations that will improve and optimize the chances for the selection of a repository site implementing the participation of stakeholders including the general public an...

Shallow ground disposal of radioactive wastes. A guidebook

Energy Technology Data Exchange (ETDEWEB)

1981-01-01

This guidebook outlines the factors to be considered in site selection, design, operation, shut-down and surveillance as well as the regulatory requirements of repositories for safe disposal of radioactive waste in shallow ground. No attempt is made to summarize the existing voluminous literature on the many facets of radioactive waste disposal. In the context of this guidebook, shallow ground disposal refers to the emplacement of radioactive waste, with or without engineered barriers, above or below the ground surface, where the final protective covering is of the order of a few metres thick. Deep geological disposal and other underground disposal methods, management of mill tailings and disposal into the sea have been or will be considered in other IAEA publications. These guidelines have been made sufficiently general to cover a broad variety of climatic, hydrogeological and biological conditions. They may need to be interpreted or modified to reflect local conditions and national regulations.

Estimation of the conditioning and storage costs of low- and intermediate-level solid radioactive wastes

International Nuclear Information System (INIS)

Lo Moro, A.; Panciatici, G.

1977-01-01

The conditioning and storage costs of low- and intermediate-level solid radioactive wastes are analyzed. The cost of direct labour is assumed as the reference cost for their computation and the storage cost is considered as resulting from the contract cost ''una tantum'' and from the leasing cost. As an example, the cost trends are reported, relevant to the solution adopted at CAMEN (conditioning in concrete containers and storage on concrete open-air bed)

Radioactive Waste Management Program Activities in Croatia

International Nuclear Information System (INIS)

Matanic, R.

2000-01-01

The concept of radioactive waste management in Croatia comprises three major areas: management of low and intermediate level radioactive waste (LILRW), spent fuel management and decommissioning. All the work regarding radioactive waste management program is coordinated by Hazardous Waste Management Agency (APO) and Croatian Power Utility (HEP) in cooperation with other relevant institutions. Since the majority of work has been done in developing low and intermediate level radioactive waste management program, the paper will focus on this part of radioactive waste management, mainly on issues of site selection and characterization, repository design, safety assessment and public acceptance. A short description of national radioactive waste management infrastructure will also be presented. (author)

Implementation of the Environmental Management System in Radioactive Waste Management

International Nuclear Information System (INIS)

Fabjan, M.; Kralj, M.; Rojc, J.

2008-01-01

Agency for Radwaste Management (ARAO) is a public institution assigned to provide effective, safe and responsible management of all kinds of radioactive waste in Slovenia from the moment they arise to their final disposal. Therefore it holds an important role in environmental protection. Its main assignment is to provide conditions for permanent disposal of radioactive waste. It is also authorised to perform public service of radioactive waste management from small producers that includes: collection of the waste from small producers at the producers' premises, transportation to the storage facility, treatment, conditioning storage of RW from small producers; acceptance of radioactive waste in case of emergency situation (e.g. transport accidents); acceptance of radioactive waste in case of unknown producer; operation and management of Central Interim Storage of Radioactive Waste. The quality of ARAO performance in carrying out its mission is assured by implementing the environmental management system according to the standard ISO 14001:2004. Its effectiveness was confirmed by certification in October 2007. The ISO 14001:2004 certificate represents a permanent commitment of ARAO to implement and improve the environmental management system and to include environmental aspects in all its activities, especially in performing the public service. We developed own evaluation criteria for determination of relevant environmental impacts and aspects. ARAO has defined its environmental policy and objectives, it evaluates its environmental impacts yearly, and defines its environmental programmes that not only fulfil legal requirements but tend even to reduce the impacts below legally set levels. A very important environmental programme in the last few years was the reconstruction of the storage facility. Public information and communication programmes are considered to be important also from the environmental management point of view, because public shows great interest in

Predisposal management of high level radioactive waste. Safety guide

International Nuclear Information System (INIS)

2005-01-01

Radioactive waste is generated in the generation of electricity in nuclear power plants and in the use of radioactive material in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized. The principles and requirements that govern the safety of the management of radioactive waste are presented in 'The Principles of Radioactive Waste Management', 'Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety' and 'Predisposal Management of Radioactive Waste, Including Decommissioning'. 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 principles and requirements established in Refs for the predisposal management of HLW. This Safety Guide applies to the predisposal management of HLW. For liquid HLW arising from the reprocessing of spent fuel the recommendations of this Safety Guide apply from when liquid waste from the first extraction process is collected for storage and subsequent processing. Recommendations and guidance on the storage of spent fuel, whether or not declared as waste, subsequent to its removal from the storage facility of a reactor are provided in Refs. For spent fuel declared as waste this Safety Guide applies to all activities subsequent to its removal from the storage facility of a reactor and prior to its disposal. Requirements pertaining to the transport of spent fuel, whether or not declared as waste, and of all forms of HLW are established. This Safety Guide provides recommendations on the safety aspects of managing HLW, including the planning, design, construction, commissioning, operation and decommissioning of equipment or facilities for the predisposal management of HLW. It addresses the following elements: (a) The characterization and processing (i.e. pretreatment

ASSESSMENT OF RADIOACTIVE AND NON-RADIOACTIVE CONTAMINANTS FOUND IN LOW LEVEL RADIOACTIVE WASTE STREAMS

International Nuclear Information System (INIS)

R.H. Little, P.R. Maul, J.S.S. Penfoldag

2003-01-01

This paper describes and presents the findings from two studies undertaken for the European Commission to assess the long-term impact upon the environment and human health of non-radioactive contaminants found in various low level radioactive waste streams. The initial study investigated the application of safety assessment approaches developed for radioactive contaminants to the assessment of nonradioactive contaminants in low level radioactive waste. It demonstrated how disposal limits could be derived for a range of non-radioactive contaminants and generic disposal facilities. The follow-up study used the same approach but undertook more detailed, disposal system specific calculations, assessing the impacts of both the non-radioactive and radioactive contaminants. The calculations undertaken indicated that it is prudent to consider non-radioactive, as well as radioactive contaminants, when assessing the impacts of low level radioactive waste disposal. For some waste streams with relatively low concentrations of radionuclides, the potential post-closure disposal impacts from non-radioactive contaminants can be comparable with the potential radiological impacts. For such waste streams there is therefore an added incentive to explore options for recycling the materials involved wherever possible

Sponsored research on radioactive waste management. Progress report January 1981 - March 1982

Energy Technology Data Exchange (ETDEWEB)

1983-01-01

The report is in chapters entitled: introduction (background, responsibilities, options, structure of the programme); strategy development; disposal of accumulations; disposal of radioactive waste arisings; quality assurance for waste conditioning quality assurance related to radioactive waste disposal (effectiveness of different rock types as natural barriers to the movement of radioactivity, and non-site specific factors in the design of repositories; radiological assessment; environmental studies; research and development to meet requirements specific to UKAEA wastes; long term research (processes for the solidification of highly active liquid wastes); plutonium contamination waste minimisation.

Handling, treatment, conditioning and storage of biological radioactive wastes. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

International Nuclear Information System (INIS)

1994-12-01

Biological materials that contain radioactive isotopes have many important applications. During the production and use of these materials, waste will inevitably arise which must be managed with particular care due to their potential biological as well as radiological hazards. This report deals with wastes that arise outside the nuclear fuel cycle and is directed primarily to countries without nuclear power programmes. It is intended to provide guidance to Member States in the handling, treatment and conditioning of biological radioactive materials. The objective of radioactive waste management is to handle, pretreat, treat, condition, store, transport and dispose of radioactive waste in a manner that protects human health and the environment without imposing undue burdens on future generations. 31 refs, 15 figs, 3 tabs

Handling, treatment, conditioning and storage of biological radioactive wastes. Technical manual for the management of low and intermediate level wastes generated at small nuclear research centres and by radioisotope users in medicine, research and industry

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-01

Biological materials that contain radioactive isotopes have many important applications. During the production and use of these materials, waste will inevitably arise which must be managed with particular care due to their potential biological as well as radiological hazards. This report deals with wastes that arise outside the nuclear fuel cycle and is directed primarily to countries without nuclear power programmes. It is intended to provide guidance to Member States in the handling, treatment and conditioning of biological radioactive materials. The objective of radioactive waste management is to handle, pretreat, treat, condition, store, transport and dispose of radioactive waste in a manner that protects human health and the environment without imposing undue burdens on future generations. 31 refs, 15 figs, 3 tabs.

Radioactivity and nuclear waste

International Nuclear Information System (INIS)

Saas, A.

1996-01-01

Radioactive wastes generated by nuclear activities must be reprocessed using specific treatments before packaging, storage and disposal. This digest paper gives first a classification of radioactive wastes according to their radionuclides content activity and half-life, and the amount of wastes from the different categories generated each year by the different industries. Then, the radiotoxicity of nuclear wastes is evaluated according to the reprocessing treatments used and to their environmental management (surface storage or burial). (J.S.)

Study on hazardous substances contained in radioactive waste

International Nuclear Information System (INIS)

Kuroki, Ryoichiro; Takahashi, Kuniaki

2008-01-01

It is necessary that the technical criteria is established concerning waste package for disposal of the TRU waste generated in Japan Atomic Energy Agency. And it is important to consider the criteria not only in terms of radioactivity but also in terms of chemical hazard and criticality. Therefore the environmental impact of hazardous materials and possibility of criticality were investigated to decide on technical specification of radioactive waste packages. The contents and results are as following. (1) Concerning hazardous materials included in TRU waste, regulations on disposal of industrial wastes and on environmental preservation were investigated. (2) The assessment methods for environmental impact of hazardous materials included in radioactive waste in U.K, U.S.A. and France were investigated. (3) The parameters for mass transport assessment about migration of hazardous materials in waste packages around disposal facilities were compiled. And the upper limits of amounts of hazardous materials in waste packages to satisfy the environmental standard were calculated with mass transport assessment for some disposal concepts. (4) It was suggested from criticality analysis for waste packages in disposal facility that the occurrence of criticality was almost impossible under the realistic conditions. (author)

Disposal method of radioactive wastes

International Nuclear Information System (INIS)

Uetake, Naoto; Fukazawa, Tetsuo.

1986-01-01

Purpose: To improve the safety of underground disposal of radioactive wastes for a long period of time by surrounding the periphery of the radioactive wastes with materials that can inhibit the migration of radioactive nuclides and are physically and chemically stable. Method: Hardening products prepared from a water-hardenable calcium silicate compound and an aqueous solution of alkali silicate have compression strength as comparable with that of concretes, high water tightness and adsorbing property to radioactive isotopes such as cobalt similar to that of concretes and they also show adsorption to cesium which is not adsorbed to concretes. Further, the kneaded slurry thereof is excellent in the workability and can be poured even into narrow gaps. Accordingly, by alternately charging granular radioactive wastes and this slurry before hardening into the ground, the radioactive wastes can be put to underground disposal stably with simple procedures. (Kamimura, M.)

Classification of Radioactive Waste. General Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-11-15

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.

Classification of Radioactive Waste. General Safety Guide

International Nuclear Information System (INIS)

2009-01-01

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

Proposed goals for radioactive waste management

International Nuclear Information System (INIS)

Bishop, W.P.; Hoos, I.R.; McGrath, P.E.; Metlay, D.S.; Stoneman, W.C.

1978-05-01

A special, seven member, interdisciplinary task group of consultants was established in January 1976 to propose goals for the national waste management program. This is the report of that group. The proposed goals are intended as a basis for the NRC to establish a policy by which to guide and coordinate the activities of government, business, and academic organizations whose responsibility it will be to manage radioactive wastes. The report is based on findings, interpretations and analysis by the authors who examined selected primary literature and interviewed many individuals concerned with waste management. The authors extended the scope of their inquiry and proposed goals to cover 'all technical and societal aspects necessary to an operating waste management system, rather than dealing with the regulatory process alone.' The waste management goals as developed are simple statements of principles which appear to the authors to be important conditions to insure the proper establishment and operation of a system to manage radioactive wastes.' In brief, the goals are designed to protect people and things of value in an equitable manner

Handling and disposing of radioactive waste

International Nuclear Information System (INIS)

Trauger, D.B.

1983-01-01

Radioactive waste has been separated by definition into six categories. These are: commercial spent fuel; high-level wastes; transuranium waste; low-level wastes; decommissioning and decontamination wastes; and mill tailings and mine wastes. Handling and disposing of these various types of radioactive wastes are discussed briefly

Descriptive catalogue of radioactive waste families

International Nuclear Information System (INIS)

2004-01-01

This document describes the different types of radioactive wastes produced in France or which are expected to be produced in the future. The wastes have been shared into different families having similar characteristics. A description is made for each family: general presentation, photos, position of the family in the French classification, industrial origin, status of production. Some informations about the raw waste and its conditioning process are also given. The qualitative description is completed by some numerical data like: the quantity produced in the past and to be produced in the future, the evaluation of the radioactivity in 2002 and 2020, and the evaluation of the thermal power when it exists. Finally, some informations are given about the risk of toxicity of some chemical species or compounds. (J.S.)

Specified radioactive waste final disposal act

International Nuclear Information System (INIS)

Yasui, Masaya

2001-01-01

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)

Characterization, treatment and conditioning of radioactive graphite from decommissioning of nuclear reactors

International Nuclear Information System (INIS)

2006-09-01

Graphite has been used as a moderator and reflector of neutrons in more than 100 nuclear power plants and in many research and plutonium-production reactors. It is used primarily as a neutron reflector or neutron moderator, although graphite is also used for other features of reactor cores, such as fuel sleeves. Many of the graphite-moderated reactors are now quite old, with some already shutdown. Therefore radioactive graphite dismantling and the management of radioactive graphite waste are becoming an increasingly important issue for a number of IAEA Member States. Worldwide, there are more than 230 000 tonnes of radioactive graphite which will eventually need to be managed as radioactive waste. Proper management of radioactive graphite waste requires complex planning and the implementation of several interrelated operations. There are two basic options for graphite waste management: (1) packaging of non-conditioned graphite waste with subsequent direct disposal of the waste packages, and (2) conditioning of graphite waste (principally either by incineration or calcination) with separate disposal of any waste products produced, such as incinerator ash. In both cases, the specific properties of graphite - such as Wigner energy, graphite dust explosibility, and radioactive gases released from waste graphite - have a potential impact on the safety of radioactive graphite waste management and need to be carefully considered. Radioactive graphite waste management is not specifically addressed in IAEA publications. Only general and limited information is available in publications dealing with decommissioning of nuclear reactors. This report provides a comprehensive discussion of radioactive graphite waste characterization, handling, conditioning and disposal throughout the operating and decommissioning life cycle. The first draft report was prepared at a meeting on 23-27 February 1998. A technical meeting (TM) was held in October 1999 in coincidence with the Seminar on

Management of Radioactive Wastes in Developing Countries

International Nuclear Information System (INIS)

Abdel Ghani, A.H.

1999-01-01

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

Directions in low-level radioactive waste management: A brief history of commercial low-level radioactive waste disposal

International Nuclear Information System (INIS)

1990-10-01

This report presents a history of commercial low-level radioactive waste management in the United States, with emphasis on the history of six commercially operated low-level radioactive waste disposal facilities. The report includes a brief description of important steps that have been taken during the 1980s to ensure the safe disposal of low-level waste in the 1990s and beyond. These steps include the issuance of Title 10 Code of Federal Regulations Part 61, Licensing Requirements for the Land Disposal of Radioactive Waste, the Low-Level Radioactive Waste Policy Act of 1980, the Low-Level Radioactive Waste Policy Amendments Act of 1985, and steps taken by states and regional compacts to establish additional disposal sites. 42 refs., 13 figs., 1 tab

Radioactive waste management

International Nuclear Information System (INIS)

Tsoulfanidis, N.

1991-01-01

The management of radioactive waste is a very important part of the nuclear industry. The future of the nuclear power industry depends to a large extent on the successful solution of the perceived or real problems associated with the disposal of both low-level waste (LLW) and high-level waste (HLW). All the activities surrounding the management of radioactive waste are reviewed. The federal government and the individual states are working toward the implementation of the Nuclear Waste Policy Act and the Low-Level Waste Policy Act. The two congressional acts are reviewed and progress made as of early 1990 is presented. Spent-fuel storage and transportation are discussed in detail as are the concepts of repositories for HLW. The status of state compacts for LLW is also discussed. Finally, activities related to the decommissioning of nuclear facilities are also described

Management of radioactive wastes arising from the use of Australian radioisotopes

International Nuclear Information System (INIS)

Costello, J.M.

1986-01-01

The medical, industrial and research use of radioisotopes in Australia has given rise to approximately 30 m 3 of solid radioactive waste containing about 5 TBq of radioactivity. This waste is stored at State hospitals, universities and research centres. A further 10 m 3 of waste containing 300 GBq of radioactivity is stored by the Commonwealth at the St Mary's Munitions Filling factory. About 700 m 3 of waste containing 1.5 PBq of radioactivity resulting from operation of the HIFAR nuclear reactor and the production of radioisotopes is in storage at the Lucas Heights Research Establishment. The source, nature and rate of arising of these wastes is reviewed, together with national developments in waste classification, storage procedures and eventual disposal. Some research at Lucas Heights on the conditioning of radioisotope waste to facilitate disposal is briefly noted

Gamma-ray spectrometry method used for radioactive waste drums characterization for final disposal at National Repository for Low and Intermediate Radioactive Waste--Baita, Romania.

Science.gov (United States)

Done, L; Tugulan, L C; Dragolici, F; Alexandru, C

2014-05-01

The Radioactive Waste Management Department from IFIN-HH, Bucharest, performs the conditioning of the institutional radioactive waste in concrete matrix, in 200 l drums with concrete shield, for final disposal at DNDR - Baita, Bihor county, in an old exhausted uranium mine. This paper presents a gamma-ray spectrometry method for the characterization of the radioactive waste drums' radionuclides content, for final disposal. In order to study the accuracy of the method, a similar concrete matrix with Portland cement in a 200 l drum was used. © 2013 The Authors. Published by Elsevier Ltd All rights reserved.

Monitoring of radioactive wastes

International Nuclear Information System (INIS)

Houriet, J.Ph.

1982-08-01

The estimation of risks presented by final disposal of radioactive wastes depends, among other things, on what is known of their radioisotope content. The first aim of this report is to present the current state of possibilities for measuring (monitoring) radionuclides in wastes. The definition of a global monitoring system in the framework of radioactive waste disposal has to be realized, based on the information presented here, in accordance with the results of work to come and on the inventory of wastes to be stored. Designed for direct measurement of unpackaged wastes and for control of wastes ready to be stored, the system would ultimately make it possible to obtain all adaquate information about their radioisotope content with regard to the required disposal safety. The second aim of this report is to outline the definition of such a global system of monitoring. Designed as a workbase and reference source for future work by the National Cooperative for the Storage of Radioactive Waste on the topic of radioactive waste monitoring, this report describes the current situation in this field. It also makes it possible to draw some preliminary conclusions and to make several recommendations. Centered on the possibilities of current and developing techniques, it makes evident that a global monitoring system should be developed. However, it shows that the monitoring of packaged wastes will be difficult, and should be avoided as far as possible, except for control measurements

Safety Aspects in Radioactive Waste Management

Directory of Open Access Journals (Sweden)

Peter W. Brennecke

2007-01-01

Full Text Available In recent years, within the framework of national as well as international programmes, notable advances and considerable experience have been reached, particularly in minimising of the production of radioactive wastes, conditioning and disposal of short-lived, low and intermediate level waste, vitrification of fission product solutions on an industrial scale and engineered storage of long-lived high level wastes, i.e. vitrified waste and spent nuclear fuel. Based on such results, near-surface repositories have successfully been operated in many countries. In contrast to that, the disposal of high level radioactive waste is still a scientific and technical challenge in many countries using the nuclear power for the electricity generation. Siting, planning and construction of repositories for the high level wastes in geological formations are gradually advancing. The site selection, the evaluation of feasible sites as well as the development of safety cases and performance of site-specific safety assessments are essential in preparing the realization of such a repository. In addition to the scientific-technical areas, issues regarding economical, environmental, ethical and political aspects have been considered increasingly during the last years. Taking differences in the national approaches, practices and the constraints into account, it is to be recognised that future developments and decisions will have to be extended in order to include further important aspects and, finally, to enhance the acceptance and confidence in the safety-related planning work as well as in the proposed radioactive waste management and disposal solutions.

Geological Disposal of Radioactive Waste

International Nuclear Information System (INIS)

Dody, A.; Klein, Ben; David, O.

2014-01-01

Disposal of radioactive waste imposes complicated constrains on the regulator to ensure the isolation of radioactive elements from the biosphere. The IAEA (1995) states that T he objective of radioactive waste management is to deal with radioactive waste in a manner that protects human health and the environment now and the future without imposing undue burdens on future generation . The meaning of this statement is that the operator of the waste disposal facilities must prove to the regulator that in routine time and in different scenarios the dose rate to the public will not exceed 0.3 mSv/y in the present and in the future up to 10,000 years

Croatian radioactive waste management program: Current status

International Nuclear Information System (INIS)

Matanic, R.; Lebegner, J.

2001-01-01

Croatia has a responsibility to develop a radioactive waste management program partly due to co-ownership of Krsko nuclear power plant (Slovenia) and partly because of its own medical and industrial radioactive waste. The total amount of generated radioactive waste in Croatia is stored in temporary storages located at two national research institutes, while radioactive waste from Krsko remains in temporary storage on site. National power utility Hrvatska Elektroprivreda (HEP) and Hazardous Waste Management Agency (APO) coordinate the work regarding decommissioning, spent fuel management and low and intermediate level radioactive waste (LILRW) management in Croatia. Since the majority of work has been done in developing the LILRW management program, the paper focuses on this part of radioactive waste management. Issues of site selection, repository design, safety assessment and public acceptance are being discussed. A short description of the national radioactive waste management infrastructure has also been presented. (author)

Study on melting conditions of radioactive miscellaneous solid waste. Contract research

International Nuclear Information System (INIS)

Fukui, Toshiki; Nakashio, Nobuyuki; Isobe, Motoyasu; Otake, Atsushi; Wakui, Takuji; Nakashima, Mikio; Hirabayashi, Takakuni

2001-02-01

Improvement of fluidity of molten slag is one of the most important factors for plasma melting treatment of low level radioactive miscellaneous wastes generated from nuclear facilities. In general, it is considered that elevating molten slag temperature of addition of flux is of certain use in improvement of fluidity of molten slag. However, these ways are not necessarily suitable from the viewpoints of refractory erosion or reduction of waste volume. In this report, we suggested that fluidity of molten slag could be improved by controlling chemical compositions of molten slag. On the Basic of the investigation using phase diagram and viscosity data, FeO was selected as a key component for improving fluidity: Viscosity and melting point of molten slag decreased with increasing relative concentration of FeO in molten slag. Accordingly, we concluded that it is important to adjust basicity of molten slag for melting treatment of low-level radioactive miscellaneous solid wastes. (author)

Thermal treatment of historical radioactive solid and liquid waste into the CILVA incinerator

International Nuclear Information System (INIS)

Deckers, Jan; Mols, Ludo

2007-01-01

Since the very beginning of the nuclear activities in Belgium, the incineration of radioactive waste was chosen as a suitable technique for achieving an optimal volume reduction of the produced waste quantities. Based on the 35 years experience gained by the operation of the old incinerator, a new industrial incineration plant started nuclear operation in May 1995, as a part of the Belgian Centralized Treatment/Conditioning Facility named CILVA. Up to the end of 2006, the CILVA incinerator has burnt 1660 tonne of solid waste and 419 tonne of liquid waste. This paper describes the type and allowable radioactivity of the waste, the incineration process, heat recovery and the air pollution control devices. Special attention is given to the treatment of several hundreds of tonne historical waste from former reprocessing activities such as alpha suspected solid waste, aqueous and organic liquid waste and spent ion exchange resins. The capacity, volume reduction, chemical and radiological emissions are also evaluated. BELGOPROCESS, a company set up in 1984 at Dessel (Belgium) where a number of nuclear facilities were already installed is specialized in the processing of radioactive waste. It is a subsidiary of ONDRAF/NIRAS, the Belgian Nuclear Waste Management Agency. According to its mission statement, the activities of BELGOPROCESS focus on three areas: treatment, conditioning and interim storage of radioactive waste; decommissioning of shut-down nuclear facilities and cleaning of contaminated buildings and land; operating of storage sites for conditioned radioactive waste. (authors)

Material chemistry challenges in vitrification of high level radioactive waste

International Nuclear Information System (INIS)

Kaushik, C.P.

2008-01-01

Full text: Nuclear technology with an affective environmental management plan and focused attention on safety measures is a much cleaner source of electricity generation as compared to other sources. With this perspective, India has undertaken nuclear energy program to share substantial part of future need of power. Safe containment and isolation of nuclear waste from human environment is an indispensable part of this programme. Majority of radioactivity in the entire nuclear fuel cycle is high level radioactive liquid waste (HLW), which is getting generated during reprocessing of spent nuclear fuels. A three stage strategy for management of HLW has been adopted in India. This involves (i) immobilization of waste oxides in stable and inert solid matrices, (ii) interim retrievable storage of the conditioned waste product under continuous cooling and (iii) disposal in deep geological formation. Borosilicate glass matrix has been adopted in India for immobilization of HLW. Material issue are very important during the entire process of waste immobilization. Performance of the materials used in nuclear waste management determines its safety/hazards. Material chemistry therefore has a significant bearing on immobilization science and its technological development for management of HLW. The choice of suitable waste form to deploy for nuclear waste immobilization is difficult decision and the durability of the conditioned product is not the sole criterion. In any immobilization process, where radioactive materials are involved, the process and operational conditions play an important role in final selection of a suitable glass formulation. In remotely operated vitrification process, study of chemistry of materials like glass, melter, materials of construction of other equipment under high temperature and hostile corrosive condition assume significance for safe and un-interrupted vitrification of radioactive to ensure its isolation waste from human environment. The present

Environmental aspects of commercial radioactive waste management

International Nuclear Information System (INIS)

1979-05-01

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

The management of radioactive wastes in China

International Nuclear Information System (INIS)

Teng Lijun

2001-01-01

Full text: This paper wants to introduce the management of radioactive wastes in China. The Management System. The management system of radioactive waste consists of the institutional system and the regulatory system. During the recent 30 years, more than 50 national standards and trades standards have been issued, will be published, or are being prepared, covering essentially all the process of wastes management. State Environmental Protection Administration (SEPA) is in charge of not only the environmental protection view but also nuclear safety surveillance of radioactive waste management, especially in the aspect of HLW disposal. China Atomic Energy Authority (CAEA) is a centralized management of the government responsible. China National Nuclear Corp. (CNNC) is responsible for the management work of radioactive wastes within its system, implementing national policies on wastes management, and siting, construction and operation of LILW repositories and HLW deep geological repository. The Policies of Radioactive Waste Management. The LILW for temporary storage shall be solidified as early as possible. Regional repository for disposal of low-and intermediate-level wastes shall be built. HLW is Centralized disposal in geological repository. The radioactive wastes and waste radioisotope sources must be collected to the signified place (facilities) for a relatively centralized management in each province, The Accompanying Mineral radioactive wastes can be stored in the tailing dumps or connected to the storage place for a temporal storage, then transported to the nearby tailing dumps of installation or tailing dumps of mineral-accompanying waste for an eventual storage. Activities in the Wastes Management Radioactive wastes treatment and conditioning Since 1970, the study on the HLLW vitrification has been initiated. In 1990, a cold test bench for the vitrification (BVPM), introduced from Germany, was completed in Sichuan Province. As for the LILW, the cementation

Disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

Hendee, W.R.

1986-01-01

The generation of low-level radioactive waste is a natural consequence of the societal uses of radioactive materials. These uses include the application of radioactive materials to the diagnosis and treatment of human disease and to research into the causes of human disease and their prevention. Currently, low level radioactive wastes are disposed of in one of three shallow land-burial disposal sites located in Washington, Nevada, and South Carolina. With the passage in December 1980 of Public Law 96-573, The Low-Level Radioactive Waste Policy Act, the disposal of low-level wastes generated in each state was identified as a responsibility of the state. To fulfill this responsibility, states were encouraged to form interstate compacts for radioactive waste disposal. At the present time, only 37 states have entered into compact agreements, in spite of the clause in Public Law 96-573 that established January 1, 1986, as a target date for implementation of state responsibility for radioactive wastes. Recent action by Congress has resulted in postponement of the implementation date to January 1, 1993

Characterization of radioactive waste forms. Volume 1

International Nuclear Information System (INIS)

Brodersen, K.; Nilsson, K.

1989-01-01

This document is the second yearbook for Task 3 of the European Communities 1985-89 programme of research on radioactive waste management and disposal carried out by public organizations and private firms in the Community through costsharing contracts with the Commission of the European Communities. The report, in two volumes, describes progress made in 1987 within the field of Task 3: Testing and evaluation of conditioned waste and engineered barriers. The first volume of the report covers Item 3.1 Characterization of low and medium-level radioactive waste forms and Item 3.5 Development of test methods for quality assurance. The second volume covers Item 3.2: High-level and alpha waste characterization and Item 3.3: Other engineered barriers. Item 3.4 on the round robin study will be treated in a separate report

National inventory of radioactive wastes

International Nuclear Information System (INIS)

1997-01-01

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.)

Radioactive wastes

International Nuclear Information System (INIS)

Devarakonda, M.S.; Melvin, J.M.

1994-01-01

This paper is part of the Annual Literature Review issue of Water Environment Research. The review attempts to provide a concise summary of important water-related environmental science and engineering literature of the past year, of which 40 separate topics are discussed. On the topic of radioactive wastes, the present paper deals with the following aspects: national programs; waste repositories; mixed wastes; waste processing and decommissioning; environmental occurrence and transport of radionuclides; and remedial actions and treatment. 178 refs

Remediation of the Provisional Storage of Radioactive Waste near Zavratec

International Nuclear Information System (INIS)

Zeleznik, N.; Mele, I.

1998-01-01

In 1996 the remediation of the provisional storage situated near village Zavratec in western part of Slovenia started. In this storage radioactive waste contaminated with radium has been stored for many decades The RAO Agency organized remedial works, in which these activities inventorying and repacking of radioactive waste were carried out. Simultaneously with these activities a detailed programme for covering public relations was prepared and implemented. On the basis of the experimental results and general storage conditions relocation of radioactive waste to the Slovenian central storage was recommended and it is planned to be concluded by the end of 1998. In this paper main remedial activities in the provisional storage of radioactive waste near Zavratec are presented. An important and most challenging part of these activities represent PR activities. (author)

Principles and objective of radioactive waste management

International Nuclear Information System (INIS)

Warnecke, E.

1995-01-01

Radioactive waste is generated in various nuclear applications, for example, in the use of radionuclides in medicine, industry and research or in the nuclear fuel cycle. It must be managed in a safe way independent of its very different characteristics. Establishing the basic safety philosophy is an important contribution to promoting and developing international consensus in radioactive waste management. The principles of radioactive waste management were developed with supporting text to provide such a safety philosophy. They cover the protection of human health and the environment now and in the future within and beyond national borders, the legal framework, the generation and management of radioactive wastes, and the safety of facilities. Details of the legal framework are provided by defining the roles and responsibilities of the Member State, the regulatory body and the waste generators and operators of radioactive waste management facilities. These principles and the responsibilities in radioactive waste management are contained in two recently published top level documents of the Radioactive Waste Safety Standards (RADWASS) programme which is the IAEA's contribution to foster international consensus in radioactive waste management. As the two documents have to cover all aspects of radioactive waste management they have to be formulated in a generic way. Details will be provided in other, more specific documents of the RADWASS programme as outlined in the RADWASS publication plant. The RADWASS documents are published in the Agency's Safety Series, which provides recommendations to Member Sates. Using material from the top level RADWASS documents a convention on the safety of radioactive waste management is under development to provide internationally binding requirements for radioactive waste management. (author). 12 refs

Supercompaction of radioactive waste at NPP Krsko

International Nuclear Information System (INIS)

Fink, K.; Sirola, P.

1996-01-01

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)

Mixed radioactive and chemotoxic wastes (RMW)

International Nuclear Information System (INIS)

Dejonghe, I.P.

1991-01-01

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)

Italian experience on the processing of solid radioactive wastes

International Nuclear Information System (INIS)

Costa, A.; De Angelis, G.

1989-12-01

Experimental work is under way in Italy for treatment and conditioning of different types of solid radioactive wastes. The following wastes are taken into account in this paper: Magnox fuel element debris, solid compactable wastes, radiation sources and contaminated carcasses. The metallic debris, consisting of Magnox splitters and braces, are conditioned, after drying and separation of corrosion products, by means of a two component epoxy system (base product + hardener). Solid compactable wastes are reduced in volume by using a press. The resulting pellets are transferred to a final container and conditioned with a cement mortar of a suitable consistency. As to the radiation sources, mainly contained in lightning-rods, gas detectors and radioactive thickness gauges, the encapsulation in a cementitious grout is a common practice for their incorporation. Early experiments, with satisfactory results, have also been conducted for the cementation of contaminated carcasses. (author)

Understanding radioactive waste

International Nuclear Information System (INIS)

Murray, R.L.

1989-01-01

This book discusses the sources and health effects of radioactive wastes. It reveals the techniques to concentrate and immobilize radioactivity and examines the merits of various disposal ideas. The book, which is designed for the lay reader, explains the basic science of atoms,nuclear particles,radioactivity, radiation and health effects

Future prospects for the management of radioactive waste in greece

International Nuclear Information System (INIS)

Savidou, A.

2015-01-01

In Greece, there isn.t yet any decision for construction of a disposal facility. Since the predisposal management of radioactive waste should be aligned with the disposal solutions, the determination of the disposal options is essential for the selection of the technology needed for treatment and conditioning of the wastes. The scope of the present study is the investigation of the disposal options for Greece. Firstly, the study deals with the preliminary inventory as well as the classification of the existing radioactive waste and the prediction of the expected waste from decommissioning of the open pool type at 5 MW Greek Research Reactor (GRR-1). The existing radioactive waste includes the institutional waste from the operation of GRR-1 and associated facilities as well as orphan sources and other radioactive items collected in the frame of emergency by the Greek Atomic Energy Commission (GAEC) and kept at the interim storage of the National Centre for Scientific Research ''Demokritos'' NCSR ''D''. Based on the present inventory of radioactive waste, the establishment of a small scale and LILW geological repository seems to be the appropriate and most acceptable by the public disposal solution. (authors)

Radioactive waste material melter apparatus

Science.gov (United States)

Newman, D.F.; Ross, W.A.

1990-04-24

An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs.

Radioactive waste material melter apparatus

International Nuclear Information System (INIS)

Newman, D.F.; Ross, W.A.

1990-01-01

An apparatus for preparing metallic radioactive waste material for storage is disclosed. The radioactive waste material is placed in a radiation shielded enclosure. The waste material is then melted with a plasma torch and cast into a plurality of successive horizontal layers in a mold to form a radioactive ingot in the shape of a spent nuclear fuel rod storage canister. The apparatus comprises a radiation shielded enclosure having an opening adapted for receiving a conventional transfer cask within which radioactive waste material is transferred to the apparatus. A plasma torch is mounted within the enclosure. A mold is also received within the enclosure for receiving the melted waste material and cooling it to form an ingot. The enclosure is preferably constructed in at least two parts to enable easy transport of the apparatus from one nuclear site to another. 8 figs

The transport of radioactive waste