Final repositories for high-level radioactive waste; Endlagerung hochradioaktiver Abfaelle

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-10-15

The brochure on final repositories for high-level radioactive waste covers the following issues: What is the origin of radioactive wastes? How large are the waste amounts? What is going to happen with the wastes? What is the solution for the Waste disposal? A new site search is started. Safety requirements for the final disposal of high-level radioactive wastes. Comparison of host rocks. Who is responsible and who will pay? Final disposal of high-level radioactive wastes worldwide. Short summary: History of the search for a final repository for high-level radioactive wastes in Germany.

The Radioactive Waste Management course: 14 High-yield editions

International Nuclear Information System (INIS)

Alonso, A.; Gallego, E.; Marco, M. L.; Falcon, S.

2003-01-01

The doctorate course on Radioactive Waste Management was initiated in February 1988, by initiative of the Chair of Nuclear Technology, under the sponsoring of the national radioactive waste management company (ENRESA), in a fruitful collaboration between the Institute Artigas of the Technical School of Industrial Engineering and the Institute of Formation on Energy of the research centre CIEMAT. The course is also offered as a post-graduate through both institutes. After completion of fourteen consecutive editions in 2002, the course constituted a landmark in the field of nuclear education in Spain. The last edition offered, along 35 lessons published in two books, the general aspects of generation, treatment and conditioning of radioactive wastes, the basic Safety and Radiological Protection criteria, the detailed technical questions of the management of both low-intermediate.activity and the high-activity level, together with the wastes generated during decommissioning and dismantling of installations, as well as the general and institutional aspects. Experts in each field, belonging either to ENRESA, CIEMAT, the Nuclear Safety Council, the UPM and the industry, present such wide programme. A technical visit to the low and intermediate radioactive waste repository of El Cabril was also offered to the participants as part of the course, as in previous years the visit to the dismantling workers of Vandellos I NPP. More than 500 engineers and graduates in different science branches have participated in the course along 14 years, with both students and professionals belonging to ENRESA, the Nuclear Safety Council, CIEMAT and other research centers, hospitals, civil protection at different levels, service and engineering companies related with the radioactive waste management. Altogether, it is possible to say, as the title is expressed, that the course has given in these 14 years a high-production yield. (Author)

Disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Glasby, G.P.

1977-01-01

Although controversy surrounding the possible introduction of nuclear power into New Zealand has raised many points including radiation hazards, reactor safety, capital costs, sources of uranium and earthquake risks on the one hand versus energy conservation and alternative sources of energy on the other, one problem remains paramount and is of global significance - the storage and dumping of the high-level radioactive wastes of the reactor core. The generation of abundant supplies of energy now in return for the storage of these long-lived highly radioactive wastes has been dubbed the so-called Faustian bargain. This article discusses the growth of the nuclear industry and its implications to high-level waste disposal particularly in the deep-sea bed. (auth.)

Proposed classification scheme for high-level and other radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Croff, A.G.

1986-01-01

The Nuclear Waste Policy Act (NWPA) of 1982 defines high-level (radioactive) waste (HLW) as (A) the highly radioactive material resulting from the reprocessing of spent nuclear fuel...that contains fission products in sufficient concentrations; and (B) other highly radioactive material that the Commission...determines...requires permanent isolation. This paper presents a generally applicable quantitative definition of HLW that addresses the description in paragraph B. The approach also results in definitions of other wastes classes, i.e., transuranic (TRU) and low-level waste (LLW). The basic waste classification scheme that results from the quantitative definitions of highly radioactive and requires permanent isolation is depicted. The concentrations of radionuclides that correspond to these two boundaries, and that may be used to classify radioactive wastes, are given

Disposal of high level radioactive wastes in geological formations

International Nuclear Information System (INIS)

Martins, L.A.M.; Carvalho Bastos, J.P. de

1978-01-01

The disposal of high-activity radioactive wastes is the most serious problem for the nuclear industry. Among the solutions, the disposal of wastes in approriated geological formations is the most realistic and feasible. In this work the methods used for geological disposal, as well as, the criteria, programs and analysis for selecting a bite for waste disposal are presented [pt

CIGeO geological disposal for high-level radioactive waste in France

International Nuclear Information System (INIS)

Ouzounian, Gerald; Bolia, Jelana

2014-01-01

Andra is the sole French organization responsible for the radioactive waste management in the country. Its work relies extensively on the legal basis provided by several major laws (Waste Act of 1991 and the Planning Act of 2006), which shaped the main principles of the waste management strategy and determined the corresponding implementation tools. Andra's industrial activities are essentially based around three of its national disposal facilities. Two of these operational facilities, by their design and comprehensive monitoring system, are considered worldwide as solid and proven reference solutions for the concerned types of radioactive waste. Andra is also charged with designing a future deep geological repository for intermediate-level long-lived and high-level waste and researching potential management and disposal solutions for the graphite and radium-bearing waste. The purpose of this article is to update the information to the readers about the Cigeo geological disposal project for high-level radioactive waste in France (authors)

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

Suggestions on R and D work of high-level radioactive waste disposal in China

International Nuclear Information System (INIS)

Xu Guoqing

2012-01-01

The difference between repository and generic underground facilities is described. Some differences and similarities of site selection between the low and medium radioactive waste disposal, nuclear power station and high-level radioactive waste repository are also discussed here. We trend to extremely emphasize the safety of high-level radioactive waste disposal because of high toxicity, long half-life and long safety disposal period of this kind of radioactive wastes; because radioactive waste in the repository is of high specific activities and buried in depth, it would be difficult to meddle with its safety. In case of repository system being destroyed, the author considers that in the stages of regional and area site selection, the first task is to investigate regional tectonic stability. Some problems about disposal options and others are also discussed in this paper. (author)

Underground storage of radioactive wastes

International Nuclear Information System (INIS)

Dietz, D.N.

1977-01-01

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

Disposal of high-activity nuclear wastes

International Nuclear Information System (INIS)

Hamilton, E.I.

1983-01-01

A discussion is presented on the deep sea ocean disposal for high-activity nuclear wastes. The following topics are covered: effect of ionizing radiation on marine ecosystems; pathways by which radionuclides are transferred to man from the marine environment; information about releases of radioactivity to the sea; radiological protection; storage and disposal of radioactive wastes and information needs. (U.K.)

Development for low-activation concrete design reducing radioactive waste

International Nuclear Information System (INIS)

Kimura, Ken-ichi; Kinno, Masaharu; Hasegawa, Akira

2008-01-01

Full text: Concrete is very valuable and inexpensive material, however it can be changed to be expensive and hard to deal with in use of a nuclear plant after long operation. One of the counter plans for the above is to use low-activation concrete instead of the ordinary concrete, that will reduce radioactive waste and could be even below clearance level in decommissioning and that is very useful in term of life cycle cost. Radioactive analysis showed that Co and Eu were the major target elements which decide the radioactivity level of reinforced concrete in decommissioning stage, and a several material were selected as a low-activation raw material from wide survey of raw materials for concrete (typically aggregates and cements). With the canditate of raw materials, several low-activation concrete were proposed for various portion of light water reactor plant, which reduction ratio were 1/10 to 1/30 which were mainly consist of limestone and low heat cement or white cement, and 1/100 to 1/300 which were mainly consist of alumina aggregate or quartz and high almina cement, comparing to the ordinary concrete in ΣDi/Ci unit, where 'Di' indicates concentration of each residual radioisotope, Ci defined by IAEA as a clearance level, and suffition of 'i' indicates each radioisotope. National funded project for development of low-activation design method for reduction of radioactive waste below clearance level were started from 2005 with aiming (1) development of a database on the content of target elements, which transform radioactive nuclides, in raw materials of reinforced concrete, (2) development of calculation tools for estimation of residual radioactivity of plant components, and (3) development of low-activation materials for concrete such as cements and reinforcing steel bars for structural components. For the optimized design for applying low-activation concrete to the reactor portion, effective evaluation of neutron spectrum in the certain portion including

Radioactive Waste Management Research Program Plan for high-level waste: 1987

International Nuclear Information System (INIS)

1987-05-01

This plan will identify and resolve technical and scientific issues involved in the NRC's licensing and regulation of disposal systems intended to isolate high level hazardous radioactive wastes (HLW) from the human environment. The plan describes the program goals, discusses the research approach to be used, lays out peer review procedures, discusses the history and development of the high level radioactive waste problem and the research effort to date and describes study objectives and research programs in the areas of materials and engineering, hydrology and geochemistry, and compliance assessment and modeling. The plan also details the cooperative interactions with international waste management research programs. Proposed Earth Science Seismotectonic Research Program plan for radioactive waste facilities is appended

Submission of the national commission of the public debate on the options concerning the long life high and medium activity radioactive wastes management

International Nuclear Information System (INIS)

2006-01-01

This document deals with the presentation of a public debate on the radioactive wastes management and the opportunities of its organization. It presents successively the long life high and medium activity radioactive wastes, the today radioactive wastes management policy and some questions and topics which could be discussed during the debate. (A.L.B.)

International Symposium on Disposal of Low Activity Radioactive Waste, Cordoba, Spain, 13-17 December 2004

CERN Document Server

2004-01-01

The topical issues addressed by the symposium were: policies and strategies for low activity radioactive waste; very low activity radioactive waste; low activity radioactive waste from decommissioning; long lived low activity radioactive waste and other materials; and unique low activity radioactive waste.

Basic approach to the disposal of low level radioactive waste generated from nuclear reactors containing comparatively high radioactivity

International Nuclear Information System (INIS)

Moriyama, Yoshinori

1998-01-01

Low level radioactive wastes (LLW) generated from nuclear reactors are classified into three categories: LLW containing comparatively high radioactivity; low level radioactive waste; very low level radioactive waste. Spent control rods, part of ion exchange resin and parts of core internals are examples of LLW containing comparatively high radioactivity. The Advisory Committee of Atomic Energy Commission published the report 'Basic Approach to the Disposal of LLW from Nuclear Reactors Containing Comparatively High Radioactivity' in October 1998. The main points of the proposed concept of disposal are as follows: dispose of underground deep enough not be disturb common land use (e.g. 50 to 100 m deep); dispose of underground where radionuclides migrate very slowly; dispose of with artificial engineered barrier which has the same function as the concrete pit; control human activities such as land use of disposal site for a few hundreds years. (author)

Radioactive waste treatment and handling in France

International Nuclear Information System (INIS)

Sivintsev, Yu.V.

1984-01-01

Classification of radioactive wastes customary in France and the program of radiation protection in handling them are discussed. Various methods of radioactive waste processing and burial are considered. The French classification of radioactive wastes differs from one used in the other countries. Wastes are classified under three categories: A, B and C. A - low- and intermediate-level radioactive wastes with short-lived radionuclides (half-life - less than 30 years, negligible or heat release, small amount of long-lived radionuclides, especially such as plutonium, americium and neptunium); B - low- and intermediate-level radioactive wastes with long-lived radionuclides (considerable amounts of long-lived radionuclides including α-emitters, low and moderate-level activity of β- and γ-emitters, low and moderate heat release); C - high-level radioactive wastes with long-lived radionuclides (high-level activity of β- and γ-emitters, high heat release, considerable amount of long-lived radionuclides). Volumetric estimations of wastes of various categories and predictions of their growth are given. It is noted that the concept of closed fuel cycle with radiochemical processing of spent fuel is customary in France

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

Radioecological activity limits for radioactive waste disposal

International Nuclear Information System (INIS)

Ahmet, E. Osmanlioglu

2006-01-01

Full text: Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides. Near surface disposal term includes broad range of facilities from simple trenches to concrete vaults. Principally, disposal of radioactive waste requires the implementation of measures that will provide safety for human health and environment now and in the future. For this reason preliminary activity limits should be determined to avoid radioecological problems. Radioactive waste has to be safely disposed in a regulated manner, consistent with internationally agreed principles and standards and with national legislations to avoid serious radioecological problems. The purpose of this study, presents a safety assessment approach to derive operational and post-closure radioecological activity limits for the disposal of radioactive waste. Disposal system has three components; the waste, the facility (incl. engineered barriers) and the site (natural barriers). Form of the waste (unconditioned or conditioned) is effective at the beginning of the migration scenerio. Existence of the engineered barriers in the facility will provide long term isolation of the waste from environment. The site characteristics (geology, groundwater, seismicity, climate etc.) are important for the safety of the system. Occupational exposure of a worker shall be controlled so that the following dose limits are not exceeded: an effective dose of 20mSv/y averaged over 5 consecutive years; and an effective dose of 50mSv in any single year. The effective dose limit for members of the public recommended by ICRP and IAEA is 1 mSv/y for exposures from all man-made sources [1,2]. Dose constraints are typically a fraction of the dose limit and ICRP recommendations (0.3 mSv/y) could be applied [3,4]. Radioecological activity concentration limits of each radionuclide in the waste (Bq/kg) were calculated. As a result of this study radioecological activity

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)

Alfredson, P.G.; Levins, D.M.

1975-08-01

Present and future methods of managing radioactive wastes in the nuclear industry are reviewed. In the stages from uranium mining to fuel fabrication, the main purpose of waste management is to limit and control dispersal into the environment of uranium and its decay products, particularly radium and radon. Nuclear reactors produce large amounts of radioactivity but release rates from commercial power reactors have been low and well within legal limits. The principal waste from reprocessing is a high activity liquid containing essentially all the fission products along with the transuranium elements. Most high activity wastes are currently stored as liquids in tanks but there is agreement that future wastes must be converted into solids. Processes to solidify wastes have been demonstrated in pilot plant facilities in the United States and Europe. After solidification, wastes may be stored for some time in man-made structures at or near the Earth's surface. The best method for ultimate disposal appears to be placing solid wastes in a suitable geological formation on land. (author)

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.)

Radioactive waste management

International Nuclear Information System (INIS)

Kawakami, Yutaka

2008-01-01

Radioactive waste generated from utilization of radioisotopes and each step of the nuclear fuel cycle and decommissioning of nuclear facilities are presented. On the safe management of radioactive waste management, international safety standards are established such as ''The Principles of Radioactive Waste Management (IAEA)'' and T he Joint Convention on the Safety of Radioactive Waste Management . Basic steps of radioactive waste management consist of treatment, conditioning and disposal. Disposal is the final step of radioactive waste management and its safety is confirmed by safety assessment in the licensing process. Safety assessment means evaluation of radiation dose rate caused by radioactive materials contained in disposed radioactive waste. The results of the safety assessment are compared with dose limits. The key issues of radioactive waste disposal are establishment of long term national strategies and regulations for safe management of radioactive waste, siting of repository, continuity of management activities and financial bases for long term, and security of human resources. (Author)

Method to determine the activity concentration and total activity of radioactive waste

International Nuclear Information System (INIS)

Angeles C, A.

2001-02-01

A characteristic system of radioactive waste is described to determine the concentration of radionuclides activity and the total activity of bundles of radioactive waste. The system this integrated by three subsystems: - Elevator of drums. - Electromechanics. - Gamma spectroscopy. In the system it is analyzed waste of issuing gamma specifically, and this designed for materials of relative low density and it analyzes materials of cylindrical recipients

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

Proposed classification scheme for high-level and other radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Croff, A.G.

1986-01-01

The Nuclear Waste Policy Act (NWPA) of 1982 defines high-level radioactive waste (HLW) as: (A) the highly radioactive material resulting from the reprocessing of spent nuclear fuel....that contains fission products in sufficient concentrations; and (B) other highly radioactive material that the Commission....determines....requires permanent isolation. This paper presents a generally applicable quantitative definition of HLW that addresses the description in paragraph (B). The approach also results in definitions of other waste classes, i.e., transuranic (TRU) and low-level waste (LLW). A basic waste classification scheme results from the quantitative definitions

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 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)

Regulation of radioactive waste management

International Nuclear Information System (INIS)

2002-01-01

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

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.)

Neotectonic movement feature in preselection area for high level radioactive waste repository

International Nuclear Information System (INIS)

Huang Xianfang; Gao Yang; He Jianguo; Li Jianzhong; Gao Honglei; Xu Guoqing

2010-01-01

Neotectonic activity intensity is an important criteria for evaluating high level radioactive waste repository. The guiding ideology, methods and application of neotectonic study are elaborated in the paper. According to comparison research between the south and north part of east Tianshan area, the south part of east Tianshan is regarded as relative stable or relative weak in neotectonic movement in Neogene period and was selected as preselection area for high level radioactive waste repository. (authors)

A proposed classification system for high-level and other radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Croff, A.G.

1987-06-01

This report presents a proposal for quantitative and generally applicable risk-based definitions of high-level and other radioactive wastes. On the basis of historical descriptions and definitions of high-level waste (HLW), in which HLW has been defined in terms of its source as waste from reprocessing of spent nuclear fuel, we propose a more general definition based on the concept that HLW has two distinct attributes: HLW is (1) highly radioactive and (2) requires permanent isolation. This concept leads to a two-dimensional waste classification system in which one axis, related to ''requires permanent isolation,'' is associated with long-term risks from waste disposal and the other axis, related to ''highly radioactive,'' is associated with shorter-term risks due to high levels of decay heat and external radiation. We define wastes that require permanent isolation as wastes with concentrations of radionuclides exceeding the Class-C limits that are generally acceptable for near-surface land disposal, as specified in the US Nuclear Regulatory Commission's rulemaking 10 CFR Part 61 and its supporting documentation. HLW then is waste requiring permanent isolation that also is highly radioactive, and we define ''highly radioactive'' as a decay heat (power density) in the waste greater than 50 W/m 3 or an external radiation dose rate at a distance of 1 m from the waste greater than 100 rem/h (1 Sv/h), whichever is the more restrictive. This proposal also results in a definition of Transuranic (TRU) Waste and Equivalent as waste that requires permanent isolation but is not highly radioactive and a definition of low-level waste (LLW) as waste that does not require permanent isolation without regard to whether or not it is highly radioactive

Disposal of high level and intermediate level radioactive wastes

International Nuclear Information System (INIS)

Flowers, R.H.

1991-01-01

The waste products from the nuclear industry are relatively small in volume. Apart from a few minor gaseous and liquid waste streams, containing readily dispersible elements of low radiotoxicity, all these products are processed into stable solid packages for disposal in underground repositories. Because the volumes are small, and because radioactive wastes are latecomers on the industrial scene, a whole new industry with a world-wide technological infrastructure has grown up alongside the nuclear power industry to carry out the waste processing and disposal to very high standards. Some of the technical approaches used, and the Regulatory controls which have been developed, will undoubtedly find application in the future to the management of non-radioactive toxic wastes. The repository site outlined would contain even high-level radioactive wastes and spent fuels being contained without significant radiation dose rates to the public. Water pathway dose rates are likely to be lowest for vitrified high-level wastes with spent PWR fuel and intermediate level wastes being somewhat higher. (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)

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

High-level radioactive waste incorporation into (special) cements

International Nuclear Information System (INIS)

Roy, D.M.; Gouda, G.R.

1978-01-01

A feasibility study has demonstrated that very strong, durable, relatively impermeable cylinders may be prepared by hot pressing combinations of cements with simulated radioactive waste solids. While the properties have not been studied exhaustively, the results suggest an optional method for immobilization and isolation of radioactive waste. Samples prepared with calcium aluminate cements appeared to have properties superior to those with Portland cements. Four simulated radioactive waste compositions having high rare-earth oxide contents, and some containing a large excess of NaNO 3 , were studied. Modest temperatures [423 to 673 K (150 to 400 0 C)] were used for hot pressing at pressures from 178 to 345 MPa. Dense strong very low porosity specimens resulted when mixtures containing from 10 to 50% waste were hot pressed, incorporating also a small percentage of water. In addition, high-strength cement cylinders were prepared with the waste solid (approximately 20 wt% waste) in a separate core and were very resistant to leaching by water near its boiling point. With this configuration, even the NaNO 3 -containing wastes were resistant to leaching by water

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)

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.)

High-level radioactive wastes

International Nuclear Information System (INIS)

Grissom, M.C.

1982-10-01

This bibliography contains 812 citations on high-level radioactive wastes included in the Department of Energy's Energy Data Base from January 1981 through July 1982. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number

Management on radioactive wastes

International Nuclear Information System (INIS)

Balu, K.; Bhatia, S.C.

1979-01-01

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

A proposed classification system for high-level and other radioactive wastes

International Nuclear Information System (INIS)

Kocher, D.C.; Croff, A.G.

1989-01-01

On the basis of the definition of high-level wastes (HLW) in the Nuclear Waste Policy Act of 1982 and previous descriptions of reprocessing wastes, a definition is proposed based on the concept that HLW is any waste which is highly radioactive and requires permanent isolation. This conceptual definition of HLW leads to a two-dimensional waste classification system in which one axis, related to 'highly radioactive', is associated with shorter-term risks from waste management and disposal due to high levels of decay heat and external radiation, and the other axis, related to 'requires permanent isolation', is associated with longer-term risks from waste disposal. Wastes that are highly radioactive are defined quantitatively as wastes with a decay heat (power density) greater than 50 W/m 3 or an external dose-equivalent rate greater than 100 rem/h (1 Sv/h) at a distance of 1 m from the waste, whichever is more restrictive. Wastes that require permanent isolation are defined quantitatively as wastes with concentrations of radionuclides greater than the Class-C limits that are generally acceptable for near-surface land disposal, as obtained from the Nuclear Regulatory Commission's 10 CFR Part 61 and its associated methodology. This proposal leads to similar definitions of two other waste classes: transuranic (TRU) waste and equivalent is any waste that requires permanent isolation but is not highly radioactive; and low-level waste (LLW) is any waste that does not require permanent isolation, without regard to whether or not it is highly radioactive. 31 refs.; 3 figs.; 4 tabs

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.)

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

Removing radio-active wastes from nuclear power stations by the STEAG system

International Nuclear Information System (INIS)

Baatz, H.

1978-01-01

The mobile STEAG System for conditioning radio-active wastes from nuclear power stations represents a particularly safe and economic method of removing them in present day conditions. Cementation by the FAFNIR System is used for the greater part of the waste, the liquid concentrate (evaporator concentrate and filter slurry). For the special case of the medium active resin balls from the primary circuits, embedding in plastic by the FAMA process has proved to be the only available successful process so far. The highly active solid waste from the reactor core is decomposed by the MOSAIK System, is packed in transportable and storable containers and is removed from the fuel element storage pond. The systems are so safe that faults or interruptions of power station operation due to faults in removing radio-active wastes can be excluded. (orig.) [de

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

Spent fuel and high-level radioactive waste storage

International Nuclear Information System (INIS)

Trigerman, S.

1988-06-01

The subject of spent fuel and high-level radioactive waste storage, is bibliographically reviewed. The review shows that in the majority of the countries, spent fuels and high-level radioactive wastes are planned to be stored for tens of years. Sites for final disposal of high-level radioactive wastes have not yet been found. A first final disposal facility is expected to come into operation in the United States of America by the year 2010. Other final disposal facilities are expected to come into operation in Germany, Sweden, Switzerland and Japan by the year 2020. Meanwhile , stress is placed upon the 'dry storage' method which is carried out successfully in a number of countries (Britain and France). In the United States of America spent fuels are stored in water pools while the 'dry storage' method is still being investigated. (Author)

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

ONDRAF/NIRAS and high-level radioactive waste management in Belgium

International Nuclear Information System (INIS)

Decamps, F.

1993-01-01

The National Agency for Radioactive Waste and Enriched Fissile Materials, ONDRAF/NIRAS, is a public body with legal personality in charge of managing all radioactive waste on Belgian territory, regardless of its origin and source. It is also entrusted with tasks related to the management of enriched fissile materials, plutonium containing materials and used or unused nuclear fuel, and with certain aspects of the dismantling of closed down nuclear facilities. High-level radioactive waste management comprises essentially and for the time being the storage of high-level liquid waste produced by the former EUROCHEMIC reprocessing plant and of high-level and very high-level heat producing waste resulting from the reprocessing in France of Belgian spent fuel, as well as research and development (R and D) with regard to geological disposal in clay of this waste type

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

Source term evaluation model for high-level radioactive waste repository with decay chain build-up.

Science.gov (United States)

Chopra, Manish; Sunny, Faby; Oza, R B

2016-09-18

A source term model based on two-component leach flux concept is developed for a high-level radioactive waste repository. The long-lived radionuclides associated with high-level waste may give rise to the build-up of activity because of radioactive decay chains. The ingrowths of progeny are incorporated in the model using Bateman decay chain build-up equations. The model is applied to different radionuclides present in the high-level radioactive waste, which form a part of decay chains (4n to 4n + 3 series), and the activity of the parent and daughter radionuclides leaching out of the waste matrix is estimated. Two cases are considered: one when only parent is present initially in the waste and another where daughters are also initially present in the waste matrix. The incorporation of in situ production of daughter radionuclides in the source is important to carry out realistic estimates. It is shown that the inclusion of decay chain build-up is essential to avoid underestimation of the radiological impact assessment of the repository. The model can be a useful tool for evaluating the source term of the radionuclide transport models used for the radiological impact assessment of high-level radioactive waste repositories.

Managing the nation's commercial high-level radioactive waste

International Nuclear Information System (INIS)

1985-03-01

This report presents the findings and conclusions of OTA's analysis of Federal policy for the management of commercial high-level radioactive waste. It represents a major update and expansion of the Analysis presented to Congress in our summary report, Managing Commercial High-Level Radioactive Waste, published in April of 1982 (NWPA). This new report is intended to contribute to the implementation of NWPA, and in particular to Congressional review of three major documents that DOE will submit to the 99th Congress: a Mission Plan for the waste management program; a monitored retrievable storage (MRS) proposal; and a report on mechanisms for financing and managing the waste program. The assessment was originally focused on the ocean disposal of nuclear waste. OTA later broadened the study to include all aspects of high-level waste disposal. The major findings of the original analysis were published in OTA's 1982 summary report

Management of radioactive waste

International Nuclear Information System (INIS)

Neerdael, B.; Marivoet, J.; Put, M.; Van Iseghem, P.; Volckaert, G.; Wacquier, W.

1998-09-01

The document gives an overview of of different aspects of radioactive waste management in Belgium. The document discusses the radioactive waste inventory in Belgium, the treatment and conditioning of radioactive waste as well as activities related to the characterisation of different waste forms. A separate chapter is dedicated to research and development regarding deep geological disposal of radioactive waste. In the Belgian waste management programme, particular emphasis is on studies for disposal in clay. Main results of these studies are highlighted and discussed

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)

Researches on the management of high activity and long-lived radioactive wastes. Axis 1 - separation-transmutation

International Nuclear Information System (INIS)

2005-11-01

This document gathers the transparencies of seven presentations given at a technical workshop of the French nuclear energy society (SFEN) about the researches on separation-transmutation of high activity and long-lived radioactive wastes. The presentations deal with: inventory and radiotoxicity of the rad-wastes in concern; industrial experience; experience on chemical separation: molecules and processes; reactors physics and transmutation - reactors for transmutation; fuels and targets; scenarios that include transmutation; environmental impacts of these different scenarios. (J.S.)

Low activation material design methodology for reduction of radio-active wastes of nuclear power plant

International Nuclear Information System (INIS)

Hasegawa, A.; Satou, M.; Nogami, S.; Kakinuma, N.; Kinno, M.; Hayashi, K.

2007-01-01

Most of the concrete shielding walls and pipes around a reactor pressure vessel of a light water reactor become low level radioactive waste at decommission phase because they contain radioactive nuclides by thermal-neutron irradiation during its operation. The radioactivity of some low level radioactive wastes is close to the clearance level. It is very desirable in terms of life cycle cost reduction that the radioactivity of those low level radioactive wastes is decreased below clearance level. In case of light water reactors, however, methodology of low activation design of a nuclear plant has not been established yet because the reactor is a large-scale facility and has various structural materials. The Objectives of this work are to develop low activation material design methodology and material fabrication for reduction of radio-active wastes of nuclear power plant such as reinforced concrete. To realize fabrication of reduced radioactive concrete, it is necessary to develop (1) the database of the chemical composition of raw materials to select low activation materials, (2) the tool for calculation of the neutron flux and the spectrum distribution of nuclear plants to evaluate radioactivity of reactor components, (3) optimization of material process conditions to produce the low activation cement and the low activation steels. Results of the data base development, calculation tools and trial production of low activation cements will be presented. (authors)

Radioactive waste processing method

International Nuclear Information System (INIS)

Sakuramoto, Naohiko.

1992-01-01

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

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

Treatment and conditioning of historical radioactive waste

International Nuclear Information System (INIS)

Dogaru, Ghe.; Dragolici, F.; Ionascu, L.; Rotarescu, Ghe.

2009-01-01

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

Radioactive wastes. Management

International Nuclear Information System (INIS)

Guillaumont, R.

2001-01-01

Many documents (journal articles, book chapters, non-conventional documents..) deal with radioactive wastes but very often this topic is covered in a partial way and sometimes the data presented are contradictory. The aim of this article is to precise the definition of radioactive wastes and the proper terms to describe this topic. It describes the main guidelines of the management of radioactive wastes, in particular in France, and presents the problems raised by this activity: 1 - goal and stakes of the management; 2 - definition of a radioactive waste; 3 - radionuclides encountered; 4 - radio-toxicity and radiation risks; 5 - French actors of waste production and management; 6 - French classification and management principles; 7 - wastes origin and characteristics; 8 - status of radioactive wastes in France per categories; 9 - management practices; 10 - packages conditioning and fabrication; 11 - storage of wastes; 12 - the French law from December 30, 1991 and the opportunities of new ways of management; 13 - international situation. (J.S.)

Disposal of high-level radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Costello, J M [Australian Atomic Energy Commission Research Establishment, Lucas Heights

1982-03-01

The aims and options for the management and disposal of highly radioactive wastes contained in spent fuel from the generation of nuclear power are outlined. The status of developments in reprocessing, waste solidification and geologic burial in major countries is reviewed. Some generic assessments of the potential radiological impacts from geologic repositories are discussed, and a perspective is suggested on risks from radiation.

Some legal aspects on high level radioactive waste disposal in Japan

International Nuclear Information System (INIS)

Tanabe, Tomoyuki

1997-01-01

In Japan, it is considered to be an urgent problem to prepare the system for the research and execution of high level radioactive waste disposal. Under what regulation scheme the disposal should be done has not been sufficiently examined. In this research, the examination was carried out on the legal aspects of high level radioactive waste disposal as follows. First, the current legislation on the disposal in Japan was analyzed, and it was made clear that high level radioactive waste disposal has not been stipulated clearly. Next, on the legal choices which are conceivable on the way the legislation for high level radioactive waste disposal should be, from the aspects of applying the law on regulating nuclear reactors and others, applying the law on nuclear power damage reparation, and industrialization by changing the government ordinances, those were arranged in six choices, and the examination was carried out for each choice from the viewpoints of the relation with the base stipulation for waste-burying business, the speciality of high level radioactive waste disposal as compared with other actions of nuclear power business, the coordination with existing nuclear power of nuclear power business, the coordination with existing nuclear power law system and the formation of national consensus. In this research, it was shown that the execution of high level radioactive waste disposal as the business based on the separate legislation is the realistic choice. (K.I.)

Technical development for geological disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Asano, Hidekazu; Sugino, Hiroyuki; Kawakami, Susumu; Yamanaka, Yumiko

1997-01-01

Technical developments for geological disposal of high-level radioactive wastes materials research and design technique for engineered barriers (overpack and buffer material) were studied to evaluate more reliable disposal systems for high-level radioactive wastes. A lifetime prediction model for the maximum corrosion depth of carbon steel was developed. A preferable alloys evaluation method for crevice corrosion was established for titanium. Swelling pressure and water permeability of bentonite as a buffer material was measured, and coupled hydro-thermo-mechanical analysis code for bentonite was also studied. The CIP (cold isostatic pressing) method for monolithically formed buffer material was tested. A concept study on operation equipment for the disposal site was performed. Activities of microorganisms involved in underground performance were investigated. (author)

10 CFR 72.108 - Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste...

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Spent fuel, high-level radioactive waste, or reactor... RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE Siting Evaluation Factors § 72.108 Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste transportation. The...

High level radioactive wastes: Considerations on final disposal

International Nuclear Information System (INIS)

Ciallella, Norberto R.

2000-01-01

When at the beginnings of the decade of the 80 the National Commission on Atomic Energy (CNEA) in Argentina decided to study the destination of the high level radioactive wastes, was began many investigations, analysis and multidisciplinary evaluations that be origin to a study of characteristics never before carried out in Argentina. For the first time in the country was faced the study of an environmental eventual problem, several decades before that the problem was presented. The elimination of the high level radioactive wastes in the technological aspects was taken in advance, avoiding to transfer the problems to the future generations. The decision was based, not only in technical evaluations but also in ethical premises, since it was considered that the future generations may enjoy the benefits of the nuclear energy and not should be solve the problem. The CNEA in Argentina in 1980 decided to begin a feasibility study and preliminary engineering project for the construction of the final disposal of high level radioactive wastes

The development of a high level radioactive waste management strategy

International Nuclear Information System (INIS)

Beale, H.

1979-11-01

The management of high level radioactive waste, from the removal of spent fuel from reactors to final disposal of vitrified waste, involves a complex choice of operational variables which interact one with another. If the various operations are designed and developed in isolation it will almost certainly lead to suboptimal choice. Management of highly active waste should therefore be viewed as a complete system and analysed in such a way that account is taken of the interactions between the various operations. This system must have clearly defined and agreed objectives as well as criteria against which performance can be judged. A thorough analysis of the system will provide a framework within which the necessary research and development can be carried out in a co-ordinated fashion and lead to an optimised strategy for managing highly active wastes. (author)

Cementification for radioactive waste including high-concentration sodium sulfate and high-concentration radioactive nuclide

International Nuclear Information System (INIS)

Miyamoto, Shinya; Sato, Tatsuaki; Sasoh, Michitaka; Sakurai, Jiro; Takada, Takao

2005-01-01

For the cementification of radioactive waste that has large concentrations of sodium sulfate and radioactive nuclide, a way of fixation for sulfate ion was studied comprising the pH control of water in contact with the cement solid, and the removal of the excess water from the cement matrix to prevent hydrogen gas generation with radiolysis. It was confirmed that the sulfate ion concentration in the contacted water with the cement solid is decreased with the formation of ettringite or barium sulfate before solidification, the pH value of the pore water in the cement solid can control less than 12.5 by the application of zeolite and a low-alkali cement such as alumina cement or fly ash mixed cement, and removal of the excess water from the cement matrix by heating is possible with aggregate addition. Consequently, radioactive waste including high-concentration sodium sulfate and high-concentration radioactive nuclide can be solidified with cementitious materials. (author)

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.

Vitrification of high-level radioactive and hazardous wastes

International Nuclear Information System (INIS)

Lutze, W.

1993-12-01

The main objective is to summarize work conducted on glasses as waste forms for high-level radioactive fission product solutions up to the late 1980's (section I and II). Section III addresses the question, whether waste forms designed for the immobilization of radioactive residues can be used for the same purpose for hazardous wastes. Of particular interest are those types of hazardous wastes, e.g., fly ashes from municipal combustion plants, easy to convert into glasses or ceramic materials. A large number of base glass compositions has been studied to vitrify waste from reprocessing but only borosilicate glasses with melting temperatures between 1100 C and 1200 C and very good hydrolytic stability is used today. (orig./HP) [de

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

Spanish high level radioactive waste management system issues

International Nuclear Information System (INIS)

Espejo, J.M.; Beceiro, A.R.

1992-01-01

The Empresa Nacional de Residuos Radiactivos, S.A. (ENRESA) has been limited liability company to be responsible for the management of all kind of radioactive wastes in Spain. This paper provides an overview of the strategy and main lines of action stated in the third General Radioactive Waste Plan, currently in force, for the management of spent nuclear fuel and high - level wastes, as well as an outline of the main related projects, either being developed or foreseen. Aspects concerning the organizational structure, the economic and financing system and the international cooperation are also included

High-level radioactive waste in Canada. Background paper

International Nuclear Information System (INIS)

Fawcett, R.

1993-11-01

The disposal of radioactive waste is one of the most challenging environmental problems facing Canada today. Since the Second World War, when Canadian scientists first started to investigate nuclear reactions, there has been a steady accumulation of such waste. Research reactors built in the early postwar years produced small amounts of radioactive material but the volume grew steadily as the nuclear power reactors constructed during the 1960s and 1970s began to spawn used fuel bundles. Although this radioactive refuse has been safely stored for the short term, no permanent disposal system has yet been fully developed and implemented. Canada is not alone in this regard. A large number of countries use nuclear power reactors but none has yet put in place a method for the long-term disposal of the radioactive waste. Scientists and engineers throughout the world are investigating different possibilities; however, enormous difficulties remain. In Canada, used fuel bundles from nuclear reactors are defined as high-level waste; all other waste created at different stages in the nuclear fuel cycle is classified as low-level. Although disposal of low-level waste is an important issue, it is a more tractable problem than the disposal of high-level waste, on which this paper will concentrate. The paper discusses the nuclear fuel waste management program in Canada, where a long-term disposal plan has been under development by scientists and engineers over the past 15 years, but will not be completed for some time. Also discussed are responses to the program by parliamentary committees and aboriginal and environmental groups, and the work in the area being conducted in other countries. (author). 1 tab

High-level radioactive waste in Canada. Background paper

Energy Technology Data Exchange (ETDEWEB)

Fawcett, R [Library of Parliament, Ottawa, ON (Canada). Science and Technology Div.

1993-11-01

The disposal of radioactive waste is one of the most challenging environmental problems facing Canada today. Since the Second World War, when Canadian scientists first started to investigate nuclear reactions, there has been a steady accumulation of such waste. Research reactors built in the early postwar years produced small amounts of radioactive material but the volume grew steadily as the nuclear power reactors constructed during the 1960s and 1970s began to spawn used fuel bundles. Although this radioactive refuse has been safely stored for the short term, no permanent disposal system has yet been fully developed and implemented. Canada is not alone in this regard. A large number of countries use nuclear power reactors but none has yet put in place a method for the long-term disposal of the radioactive waste. Scientists and engineers throughout the world are investigating different possibilities; however, enormous difficulties remain. In Canada, used fuel bundles from nuclear reactors are defined as high-level waste; all other waste created at different stages in the nuclear fuel cycle is classified as low-level. Although disposal of low-level waste is an important issue, it is a more tractable problem than the disposal of high-level waste, on which this paper will concentrate. The paper discusses the nuclear fuel waste management program in Canada, where a long-term disposal plan has been under development by scientists and engineers over the past 15 years, but will not be completed for some time. Also discussed are responses to the program by parliamentary committees and aboriginal and environmental groups, and the work in the area being conducted in other countries. (author). 1 tab.

Long-term management of high-level radioactive waste. The meaning of a demonstration

International Nuclear Information System (INIS)

1983-01-01

The ''demonstration'' of the safe management of high level radioactive waste is a prerequisite for the further development of nuclear energy. It is therefore essential to be clear about both the meaning of the term ''demonstration'' and the practical means to satisfy this request. In the complex sequence of operations necessary to the safe management of high level waste, short term activities can be directly demonstrated. For longer term activities, such as the long term isolation of radioactive waste in deep undergroung structures, demonstration must be indirect. The ''demonstration'' of deep underground disposal for high level radioactive waste involves two steps: one direct, to prove that the system could be built, operated and closed safely and at acceptable costs, and one indirect, to make a convincing evaluation of the system's performance and long term safety on the basis of predictive analyses confirmed by a body of varied technical and scienfic data, much of it deriving from experimental work. The assessment of the evidence collected from current operations, existing experience in related fields and specific research and development activities, calls for specialized scientific expertise. Uncertainties in far future situations and probabilistic events can be taken into account in a scientific assessment. Competent national authorithies will have to satisfy themselves that the proposed waste management solutions can meet long term safety objectives. An element of judgement will always be needed in determining the acceptability of a waste disposal concept. However, the level of confidence in our ability to predict the performance of waste management systems will increase as supporting evidence is collected from current research and development activities and as our predictive techniques improve

Cementation of liquid radioactive waste with high content of borate salts

International Nuclear Information System (INIS)

Gorbunova, O.

2015-01-01

The report reviews the ways of optimization of cementation of boron-containing liquid radioactive waste. The most common way to hardening the low-level liquid radioactive waste (LRW) is the cementation. However, boron-containing liquid radioactive waste with low pH values cannot be cemented without alkaline additives, to neutralize acid forms of borate compounds. Cement setting without additives happens only on 14-56 days, the compounds have low strength, and hence an insufficient reliability of radionuclides fixation in the cement matrix. The alkaline additives increase the volume of the final cement compound which enhances financial and operational costs. In order to control the speed of hardening of cement solution with a boron-containing liquid radioactive waste and to remove the components that prevent hardening of cement solution, it is proposed an electromagnetic treatment of LRW in the vortex layer of ferromagnetic particles. The results of infrared spectroscopy show, that electromagnetic treatment of liquid radioactive waste changes the ionic forms of the borates and raises the pH due to the dissociation of the oxygen and hydrogen bonds in the aqueous solutions of the boron compounds. The various types of ferromagnetic activators of the vortex layer have been investigated, including the highly dispersed nano-powders and the magnetic phases of the iron oxides. It has been determined the technological parameters of the electromagnetic treatment of liquid radioactive waste and the subsequent cementation of this type of LRW. By using the method of scanning electron microscopy it has been shown, that the nano-particles of magnetic phases of the ferric oxides are involved in phase formation of hydro-aluminum-calcium ferrites in the early stages of hardening and improving strength of the cement compounds with liquid radioactive waste. (authors)

High-level radioactive waste disposal type and theoretical analyses

International Nuclear Information System (INIS)

Lu Yingfa; Wu Yanchun; Luo Xianqi; Cui Yujun

2006-01-01

Study of high-level radioactive waste disposal is necessary for the nuclear electrical development; the determination of nuclear waste depository type is one of importance safety. Based on the high-level radioactive disposal type, the relative research subjects are proposed, then the fundamental research characteristics of nuclear waste disposition, for instance: mechanical and hydraulic properties of rock mass, saturated and unsaturated seepage, chemical behaviors, behavior of special soil, and gas behavior, etc. are introduced, the relative coupling equations are suggested, and a one dimensional result is proposed. (authors)

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)

Remote ignitability analysis of high-level radioactive waste

International Nuclear Information System (INIS)

Lundholm, C.W.; Morgan, J.M.; Shurtliff, R.M.; Trejo, L.E.

1992-09-01

The Idaho Chemical Processing Plant (ICPP), was used to reprocess nuclear fuel from government owned reactors to recover the unused uranium-235. These processes generated highly radioactive liquid wastes which are stored in large underground tanks prior to being calcined into a granular solid. The Resource Conservation and Recovery Act (RCRA) and state/federal clean air statutes require waste characterization of these high level radioactive wastes for regulatory permitting and waste treatment purposes. The determination of the characteristic of ignitability is part of the required analyses prior to calcination and waste treatment. To perform this analysis in a radiologically safe manner, a remoted instrument was needed. The remote ignitability Method and Instrument will meet the 60 deg. C. requirement as prescribed for the ignitability in method 1020 of SW-846. The method for remote use will be equivalent to method 1020 of SW-846

Radioactive waste management

International Nuclear Information System (INIS)

2003-01-01

Almost all IAEA Member States use radioactive sources in medicine, industry, agriculture and scientific research, and countries remain responsible for the safe handling and storage of all radioactively contaminated waste that result from such activities. In some cases, waste must be specially treated or conditioned before storage and/or disposal. The Department of Technical Co-operation is sponsoring a programme with the support of the Nuclear Energy Department aimed at establishing appropriate technologies and procedures for managing radioactive wastes. (IAEA)

Desactivation of liquid radioactive wastes of low and medium activity

International Nuclear Information System (INIS)

Golinski, M.; Charomska, K.

1978-01-01

The results of research made according to the prodranm of scientific and technical cooperation of the CMEA countries are discussed. The main direction of these research works is on future improvement of installations for purification of liquid radioactive wastes by chemical methods of coprecipitation and coagulation, ion exchange, sorption, distillation and electrolysis. It was shown that methods of coprecipitation and coagulation have low efficiency and the activity reduction factor seldom was more than 10. In sorption processes different sorbents, both organic and nonorganic were used. The modified bentonite used as a sorbent agent has shown high selectivity towards zesium ions. Waste concentration by means of distillation is an universal but rather expensive method and is applied mainly in the cases of high salts concentration and high specific activity of liquid wastes. Electrolysis, as a method of the liquid wastes purification is used in the USSR and has high efficiency with low energy consumption. (I.T.) [ru

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

Radioactivity evaluation method for pre-packed concrete packages of low-level dry active wastes

International Nuclear Information System (INIS)

Sakai, Toshiaki; Funahashi, Tetsuo; Watabe, Kiyomi; Ozawa, Yukitoshi; Kashiwagi, Makoto

1998-01-01

Low-level dry active wastes of nuclear power plants are grouted with cement mortal in a container and planned to disposed into the shallow land disposal site. The characteristics of radionuclides contained in dry active wastes are same as homogeneous solidified wastes. In the previous report, we reported the applicability of the radioactivity evaluation methods established for homogeneous solidified wastes to pre-packed concrete packages. This report outlines the developed radioactivity evaluation methods for pre-packed concrete packages based upon recent data. Since the characteristics of dry active wastes depend upon the plant system in which dry active wastes originate and the types of contamination, sampling of wastes and activity measurement were executed to derive scaling factors. The radioactivity measurement methods were also verified. The applicability of non-destructive methods to measure radioactivity concentration of pre-packed concrete packages was examined by computer simulation. It is concluded that those methods are accurate enough to measure actual waste packages. (author)

National Plan for the management of radioactive materials and wastes 2013-2015

International Nuclear Information System (INIS)

2013-02-01

This new release of the National Plan for the management of radioactive materials and wastes (PNGMDR) first addresses the principles and objectives of this management: presentation of radioactive materials and wastes, principles to be taken into account to define the different management ways, legal and institutional framework for waste management, societal dimension and memory safeguarding, waste management cost and financing. It proposes an assessment and draws perspectives for the existing management practices: management of historical situations, management of residues of mine processing and mine tailings, management of radioactive wastes, waste management with respect to radioactive decay, valorization of radioactive wastes, incineration of radioactive wastes, storage of very-low-activity wastes, of storage of low- and medium-activity and short-life wastes, management of reinforced natural radioactivity wastes. The third part gives an overview of needs and perspectives for management methods: wastes requiring a specific processing, low-activity long-life wastes, and high-activity and medium-activity long-life wastes

Spanish high level radioactive waste management system issues

International Nuclear Information System (INIS)

Ulibarri, A.; Veganzones, A.

1993-01-01

The Empresa Nacional de Residuous Radiactivos, S.A. (ENRESA) was set up in 1984 as a state-owned limited liability company to be responsible for the management of all kinds of radioactive wastes in Spain. This paper provides an overview of the strategy and main lines of action stated in the third General Radioactive Waste Plan, currently in force, for the management of spent nuclear fuel and high-level wastes, as well as an outline of the main related projects, either being developed or foreseen. Aspects concerning the organizational structure, the economic and financing system and the international co-operational are also included

Study on the development of safety regulations for geological disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Wei Fangxin

2012-01-01

The development of regulations under Regulations on Safety Management of Radioactive Waste has become necessary as the issuance of it. The regulations related to geological disposal of high-level radioactive waste can promote the progress of research and development on geological disposal of high-level radioactive waste in China. This paper has present suggestions on development of regulations on geological disposal of high-level radioactive waste by analyzing development of safety regulations on geological disposal of high-level radioactive waste in foreign countries and problems occurred in China and discussed important issues related to the development of safety regulations on geological disposal of high-level radioactive waste. (author)

Radioactive waste immobilization in protective ceramic forms by the HIP method at high pressures

International Nuclear Information System (INIS)

Sayenko, S.Yu.; Kantsedal, V.P.; Tarasov, R.V.; Starchenko, V.A.; Lyubtsev, R.I.

1993-01-01

Intense research activities have been carried out in recent years at the Kharkov Institute of Physics and Technology (KIPT) to develop the method of hot isostatic pressing (HIP) for immobilizing radioactive (primarily, high-level) wastes. With this method, the radioactive material is immobilized in a matrix under the simultaneous action of high pressures (up to 6,000 atm) and appropriate temperatures. The process has 2 variants: (1) radioactive wastes are treated as powders of oxides resulting from calcination during chemical treatment of spent fuel. In this case the radioactive material enters into the crystalline structure of the immobilized matrix or is distributed in the matrix as a homogeneous mixture; (2) protective barrier layers are pressed on spent fuel rods or their pieces as radioactive wastes, by the HIP method (fuel rod encapsulation in a protective form). Based on numerous results from various studies, the authors suggest that various ceramic compositions should be used as protective materials. Here the authors report two trends of their investigations: (1) development of ecologically clean process equipments for radioactive waste treatment by the HIP method; (2) manufacture of promising protective ceramic compositions and investigation of their physico-mechanical properties

Evaluation of radionuclide concentrations in high-level radioactive wastes

International Nuclear Information System (INIS)

Fehringer, D.J.

1985-10-01

This report describes a possible approach for development of a numerical definition of the term ''high-level radioactive waste.'' Five wastes are identified which are recognized as being high-level wastes under current, non-numerical definitions. The constituents of these wastes are examined and the most hazardous component radionuclides are identified. This report suggests that other wastes with similar concentrations of these radionuclides could also be defined as high-level wastes. 15 refs., 9 figs., 4 tabs

The development of a strategy for the management of high level radioactive wastes

International Nuclear Information System (INIS)

Beale, H.

1981-07-01

An assessment is made of the options available for the management of high level radioactive wastes. This preliminary study leads to the conclusion that the high active liquor should be vitrified at the earliest possible date and points to the advantages of storing the vitrified waste for an extended period in reinforced concrete casks. (author)

Spent Fuel and High-Level Radioactive Waste Transportation Report

International Nuclear Information System (INIS)

1992-03-01

This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by SSEB in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ''comprehensive overview of the issues.'' This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste Issues. In addition. this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages will be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list

Spent fuel and high-level radioactive waste transportation report

Energy Technology Data Exchange (ETDEWEB)

1989-11-01

This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by the Southern States Energy Board (SSEB) in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ``comprehensive overview of the issues.`` This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste issues. In addition, this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages sew be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list.

Spent fuel and high-level radioactive waste transportation report

International Nuclear Information System (INIS)

1989-11-01

This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by the Southern States Energy Board (SSEB) in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ''comprehensive overview of the issues.'' This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste issues. In addition, this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages sew be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list

Spent fuel and high-level radioactive waste transportation report

International Nuclear Information System (INIS)

1990-11-01

This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by the Southern States Energy Board (SSEB) in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ''comprehensive overview of the issues.'' This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste issues. In addition, this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages will be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list

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

Andra. Everything on the management of radioactive wastes

International Nuclear Information System (INIS)

2014-08-01

This publication briefly presents the ANDRA, the French National Agency for the management of radioactive wastes, its mission, its activities, its financing, and some key figures. It briefly presents the phenomenon of radioactivity, radioactive wastes and their storage. It presents the different classes of radioactive wastes (very-low-level, low- and intermediate-level and short-lived, low-level and long-lived, high-level and intermediate-level and long-lived) and their storage principles. It sketches the pathway followed by a waste from its production to its storage. It presents the various ANDRA sites

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.)

First days of R and D in radioactive waste management

International Nuclear Information System (INIS)

1993-01-01

The first meeting of R and D in radioactive waste management was organized by ENRESA on 21,22,23 April 1993. The main objective was to disseminate the most relevant works within the 2nd R and D plan, and to establish and adequate form involved for discussion R and D radioactive waste management. (Author) The meeting was articulated in 50 sessions: I.- Low and medium radioactive wastes II.- High level radioactive wastes: activities of ENRESA III.- High level radioactive wastes: near field. IV.- Biosphere, radiological protection, behaviour evaluation V.- Dismantling and decommissioning nuclear facilities VI.- Geosphere

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

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.)

High-level radioactive waste management

International Nuclear Information System (INIS)

Schneider, K.J.; Liikala, R.C.

1974-01-01

High-level radioactive waste in the U.S. will be converted to an encapsulated solid and shipped to a Federal repository for retrievable storage for extended periods. Meanwhile the development of concepts for ultimate disposal of the waste which the Federal Government would manage is being actively pursued. A number of promising concepts have been proposed, for which there is high confidence that one or more will be suitable for long-term, ultimate disposal. Initial evaluations of technical (or theoretical) feasibility for the various waste disposal concepts show that in the broad category, (i.e., geologic, seabed, ice sheet, extraterrestrial, and transmutation) all meet the criteria for judging feasibility, though a few alternatives within these categories do not. Preliminary cost estimates show that, although many millions of dollars may be required, the cost for even the most exotic concepts is small relative to the total cost of electric power generation. For example, the cost estimates for terrestrial disposal concepts are less than 1 percent of the total generating costs. The cost for actinide transmutation is estimated at around 1 percent of generation costs, while actinide element disposal in space is less than 5 percent of generating costs. Thus neither technical feasibility nor cost seems to be a no-go factor in selecting a waste management system. The seabed, ice sheet, and space disposal concepts face international policy constraints. The information being developed currently in safety, environmental concern, and public response will be important factors in determining which concepts appear most promising for further development

10 CFR 72.128 - Criteria for spent fuel, high-level radioactive waste, reactor-related greater than Class C waste...

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Criteria for spent fuel, high-level radioactive waste, reactor-related greater than Class C waste, and other radioactive waste storage and handling. 72.128... STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

Problems related to final disposal of high-level radioactive waste in Russia

International Nuclear Information System (INIS)

Velichkin, Vasily I.

1999-01-01

According to this presentation, the radioactivity of the total amount of radioactive waste accumulated in Russia to date is 1.5*10 9 Ci and of spent fuel 4.5*10 9 Ci. A table is given that shows the source, type, volume activity and storage type under the responsibility of the different departments and enterprises. 99.9% of the wastes are accumulated at the enterprises of Minatom of the Russian Federation. Some companies inject their liquid wastes from ionisation sources and intermediate liquid waste from the nuclear power industry into deep-seated reliably isolated aquifers. The Mayak plant has released liquid low-level and intermediate wastes into artificial reservoirs and Lake Karachay. Liquid high-level wastes are always stored in special tanks at interim storage facilities. A large number of nuclear submarines are laid up in North-Western Russia and East Russia, with spent fuel still in place as the interim storages in these regions are filled up and there are no conditioning plants. Underground disposal is considered the best way of isolating radioactive waste for as long as it is hazardous to the environment. Two new technologies are discussed. One involves including long-lived isotopes in high-stable mineral matrices, the other uses selective separation from the bulk of wastes. The matrices should be disposed of deep in the Earth's crust, at least 2-3 km down. Liquid waste of caesium-strontium fraction must be transformed into glass-like form and stored underground at a depth of a few hundred metres. Short-lived low level and intermediate level wastes should be conditioned and then deposited in subsurface ferroconcrete repositories constructed in clays. Finally, the presentation discusses the selection of sites and conditions for radioactive waste disposal. Two sites are discussed, the Mayak plant and a possible site at Mining Chemical Combine in Krasnoyarsk-26

Methods for estimating costs of transporting spent fuel and defense high-level radioactive waste for the civilian radioactive waste management program

International Nuclear Information System (INIS)

Darrough, M.E.; Lilly, M.J.

1989-01-01

The US Department of Energy (DOE), through the Office of Civilian Radioactive Waste Management, is planning and developing a transportation program for the shipment of spent fuel and defense high-level waste from current storage locations to the site of the mined geologic repository. In addition to its responsibility for providing a safe transportation system, the DOE will assure that the transportation program will function with the other system components to create an integrated waste management system. In meeting these objectives, the DOE will use private industry to the maximum extent practicable and in a manner that is cost effective. This paper discusses various methodologies used for estimating costs for the national radioactive waste transportation system. Estimating these transportation costs is a complex effort, as the high-level radioactive waste transportation system, itself, will be complex. Spent fuel and high-level waste will be transported from more than 100 nuclear power plants and defense sites across the continental US, using multiple transport modes (truck, rail, and barge/rail) and varying sizes and types of casks. Advance notification to corridor states will be given and scheduling will need to be coordinated with utilities, carriers, state and local officials, and the DOE waste acceptance facilities. Additionally, the waste forms will vary in terms of reactor type, size, weight, age, radioactivity, and temperature

The stakes in managing radioactive wastes

International Nuclear Information System (INIS)

Boissier, F.

2012-01-01

Like any human activity, the nuclear industry produces wastes. The wastes containing radioactive substances have to be managed as a function of the related risks. Nowadays, 1.300.000 tons of radioactive wastes have accumulated in France. More than 90% of them have short half-lives and are stored on the ground by ANDRA (national agency for the management of radioactive wastes) on 2 sites in the Aube district. ANDRA also designs solutions for stocking the other wastes. Those with long half-lives and very high activity will be stored deep underground (500 meter deep) at Cigeo in the Meuse and Haute-Marne districts. The wastes with long half-lives but low activity (less than 10 5 decays/s for graphite and less than a few thousands decays/s for radium contaminated wastes) will be disposed in a specific way. Implementing a storage solution for each type of waste is necessary for the nuclear industry's sustainability, but it does not dispense the latter from pursuing its efforts to reduce the quantity and danger of the wastes produced. This holds in particular for the so-called 'fourth generation' of future installations. It is important to take stock of all the issues related to managing nuclear wastes

High activity waste disposal

International Nuclear Information System (INIS)

Gaul, W.C.

1990-01-01

Chem-Nuclear Environmental Services (CNES) has developed a container that is capable of containing high activity waste and can be shipped as a regular DOT Type A shipment. By making the container special form the amount of activity that can be transported in a Type A shipment is greatly enhanced. Special form material presents an extra degree of protection to the environment by requiring the package to be destroyed to get access to the radioactive material and must undergo specific testing requirements, whereas normal form material can allow access to the radioactive material. With the special form container up to 10 caries of radium can be transported in a single package. This paper will describe the considerations that were taken to develop these products

Radioactive wastes: sources, treatment, and disposal

International Nuclear Information System (INIS)

Wymer, R.G.; Blomeke, J.O.

1975-01-01

Sources, treatment, and disposal of radioactive wastes are analyzed in an attempt to place a consideration of the problem of permanent disposal at the level of established or easily attainable technology. In addition to citing the natural radioactivity present in the biosphere, the radioactive waste generated at each phase of the fuel cycle (mills, fabrication plants, reactors, reprocessing plants) is evaluated. The three treatment processes discussed are preliminary storage to permit decay of the short-lived radioisotopes, solidification of aqueous wastes, and partitioning the long-lived α emitters for separate and long-term storage. Dispersion of radioactive gases to the atmosphere is already being done, and storage in geologically stable structures such as salt mines is under active study. The transmutation of high-level wastes appears feasible in principle, but exceedingly difficult to develop

The European Community's research and development activities on the management of radioactive waste from decommissioning

International Nuclear Information System (INIS)

Huber, B.

1984-01-01

The Commission of the European Communities is conducting an R and D programme on the decommissioning of nuclear power plants. The activities carried out within this framework that concern, in particular, management of the radioactive waste arising from the decommissioning are outlined. Characterization of the radioactivity inventory of nuclear power plants at the end of their useful life is of fundamental importance in this context. Research in this field comprises analyses of the trace elements in reactor materials which are relevant for the formation of long-lived radionuclides by neutron activation, as well as examinations of samples taken from activated and contaminated plant components. Most of the radioactive plant components are only surface contaminated. Highly efficient decontamination techniques are being developed with the objective of achieving conditions permitting unrestricted release of the material treated. Other activities concern the conditioning of steel and concrete waste for disposal, and the management of graphite waste from gas-cooled reactors. Large containers are being developed for transport and disposal of radioactive components. Finally, the methods of radiological evaluation and measurement are being studied which are required to decide whether material from the dismantling of nuclear power plants has to be disposed of as radioactive waste or not. (author)

Study on rich alumina alkali-activated slag clay minerals cementitious materials for immobilization of radioactive waste

International Nuclear Information System (INIS)

Li Yuxiang; Qian Guangren; Yi Facheng; Shi Rongming; Fu Yibei; Li Lihua; Zhang Jun

1999-01-01

The composition and some properties of its pastes of rich alumina alkali-activated slag clay minerals (RAAASCM) cementitious materials for immobilization of radioactive waste are studied. Experimental results show that heat activated kaolinite, Xingjiang zeolite, modified attapulgite clay are better constituents of RAAASCM. RAAASCM cementitious materials pastes exhibit high strength, low porosity, fewer harmful pore, and high resistance to sulphate corrosion as well as gamma irradiation. The Sr 2+ , Cs + leaching portion of the simulated radioactive waste forms based on RAAASCM, is low

Radioactive waste management

International Nuclear Information System (INIS)

2013-01-01

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

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

Radioactive wastes management development in Chile

International Nuclear Information System (INIS)

Mir, S.A.; Cruz, P.F.; Rivera, J.D.; Jorquera, O.H.

1994-01-01

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

Managing the nation's commercial high-level radioactive waste

International Nuclear Information System (INIS)

Cotton, T.

1985-01-01

With the passage of the Nuclear Waste Policy Act of 1982 (NWPA), Congress for the first time established in law a comprehensive Federal policy for commercial high-level radioactive waste management, including interim storage and permanent disposal. NWPA provides sufficient authority for developing and operating a high-level radioactive waste management system based on disposal in mined geologic repositories. Authorization for other types of waste facilities will not be required unless major problems with geologic disposal are discovered, and studies to date have identified no insurmountable technical obstacles to developing geologic repositories. The NWPA requires the Department of Energy (DOE) to submit to Congress three key documents: (1) a Mission Plan, containing both a waste management plan with a schedule for transferring waste to Federal facilities and an implementation program for choosing sites and developing technologies to carry out that plan; (2) a monitored retrievable storage (MRS) proposal, to include a site-specific design for a long-term federal storage facility, an evaluation of whether such an MRS facility is needed and feasible, and an analysis of how an MRS facility would be integrated with the repository program if authorized by Congress; and (3) a study of alternative institutional mechanisms for financing and managing the radioactive waste system, including the option of establishing an independent waste management organization outside of DOE. The Mission Plan and the report on alternative institutional mechanisms were submitted to the 99th US Congress in 1985. The MRS proposal is to be submitted in early 1986. Each of these documents is discussed following an overview of the Nuclear Waste Policy Act of 1982

United Kingdom government policy towards radioactive waste

International Nuclear Information System (INIS)

Pritchard, G.

1986-01-01

There are three areas of radioactive waste management which exemplify, beyond any reasonable doubt, that the United Kingdom has in the past (and intends in the future), to pursue a policy of dispersal and disposal of radioactive wastes: These are: (I) dumping of low-level waste in the deep ocean and, on a parallel, seabed emplacement of highly active waste; (II) the liquid discharges from Windscale into the Irish Sea; and (III) land dumping of low- and intermediate-level waste

ANDRA - National Radioactive Waste Management Agency. Activity report 2015. Financial report 2015

International Nuclear Information System (INIS)

2016-01-01

Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity and financial report of the Andra for the year 2015

ANDRA - National Radioactive Waste Management Agency. Activity report 2016. Financial report 2016

International Nuclear Information System (INIS)

2017-01-01

Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity and financial report of the Andra for the year 2016

Alternative processes for managing existing commercial high-level radioactive wastes

International Nuclear Information System (INIS)

1976-04-01

A number of alternatives are discussed for managing high-level radioactive waste presently stored at the West Valley, New York, plant owned by Nuclear Fuel Services, Inc. These alternatives (liquid storage, conversion to cement, shale fracturing, shale cement, calcination, aqueous silicate, conversion to glass, and salt cake) are limited to concepts presently under active investigation by ERDA. Each waste management option is described and examined regarding the status of the technology; its applications to managing NFS waste; its advantages and disadvantages; the research and development needed to implement the option; safety considerations; and estimated costs and time to implement the process

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

On risk assessment of high level radioactive waste disposal

International Nuclear Information System (INIS)

Smith, C.F.; Kastenberg, W.E.

1976-01-01

One of the major concerns with the continued growth of the nuclear power industry is the production of the high level radioactive wastes. The risks associated with the disposal of these wastes derives from the potential for release of radioactive materials into the environment. The development of a methodology for risk analysis is carried out. The methodology suggested involves the probabilistic analysis of a general accident consequence distribution. In this analysis, the frequency aspect of the distribution is treated separately from the normalized probability function. In the final stage of the analysis, the frequency and probability characteristics of the distribution are recombined to provide an estimate of the risk. The characterization of the radioactive source term is accomplished using the ORIGEN computer code. Calculations are carried out for various reactor types and fuel cycles, and the overall waste hazard for a projected 35 year nuclear power program is determined. An index of relative nuclide hazard appropriate to problems involving the management of high level radioactive wastes is developed. As an illustration of the methodology, risk analyses are made for two proposed methods for waste management: extraterrestrial disposal and interim surface storage. The results of these analyses indicate that, within the assumptions used, the risks of these management schemes are small compared with natural background radiation doses. (Auth.)

Current status of high level radioactive waste disposal in Japan and foreign countries

International Nuclear Information System (INIS)

Tanaka, Satoru; Tanabe, Hiromi; Inagaki, Yusuke; Ishida, Hisahiro; Kato, Osamu; Kurata, Mitsuyuki; Yamachika, Hidehiko

2002-01-01

At a time point of 2002, there is no country actually disposing high level radioactive wastes into grounds, but in most of countries legislative preparation and practicing agents are carried out and site selection is promoted together with energetic advancement of its R and Ds. As disposal methods of the high level radioactive wastes, various methods such as space disposal, oceanic bottom disposal, ice bed disposal, ground disposal, and so on have been examined. And, a processing technology called partitioning and transmutation technology separating long-lived radionuclides from liquid high level radioactive waste and transmutation into short-lived or harmless radionuclides has also been studied. Here was introduced their wrestling conditions in Japan and main foreign countries, as a special issue of the Current status of high level radioactive waste disposal in Japan and foreign countries'. The high level radioactive wastes (glassification solids or spent nuclear fuels) are wastes always formed by nuclear power generation and establishment of technologies is an important subject for nuclear fuel cycle. (G.K.)

The management of low activity radioactive waste: IAEA guidance and perspectives

International Nuclear Information System (INIS)

Louvat, D.; Rowat, J.H.; Potier, J.M.

2005-01-01

This paper describes the safety standards and reports of the International Atomic Energy Agency (IAEA) applicable to the management and disposal of low activity radioactive waste and provides some historical perspective on their development. Some of the most important current issues in the area of low activity radioactive waste management are discussed in the context of related ongoing IAEA activities. At the end of the paper, a number of issues and questions are raised for consideration and discussion at this symposium. (author)

Deep geologic storage of high level radioactive wastes: conceptual generic designs

International Nuclear Information System (INIS)

1995-01-01

This report summarizes the studies on deep geologic storage of radioactive wastes and specially for the high-level radioactive wastes. The study is focussed to the geotechnical assessment and generic-conceptual designs. Methodology analysis, geotechnical feasibility, costs and operation are studied

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 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)

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.)

Status of activities: Low-level radioactive waste management in the United States

International Nuclear Information System (INIS)

Ozaki, C.B.; Shilkett, R.C.; Kirkpatrick, T.D.

1989-01-01

A primary objective of low-level radioactive waste management in the United States is to protect the health and safety of the public and the quality of the environment. In support of this objective is the development of waste treatment and disposal technologies designed to provide stabilization and long-term institutional control of low-level radioactive wastes. Presented herein is a technical review of specific low-level radioactive waste management activities in the United States. Waste treatment and disposal technologies are discussed along with the performance objectives of the technologies aimed at protecting the health and safety of the public and the quality of the environment. 13 refs., 4 figs

Midwestern High-Level Radioactive Waste Transportation Project

International Nuclear Information System (INIS)

1993-01-01

On February 17,1989, the Midwestern Office of The Council of State Governments and the US Department of Energy entered into a cooperative agreement authorizing the initiation of the Midwestern High-Level Radioactive Waste Transportation Project. The transportation project continued to receive funding from DOE through amendments to the original cooperative agreement, with December 31, 1993, marking the end of the initial 5-year period. This progress report reflects the work completed by the Midwestern Office from February 17,1989, through December 31,1993. In accordance with the scopes of work governing the period covered by this report, the Midwestern Office of The Council of State Governments has worked closely with the Midwestern High-Level Radioactive Waste Committee. Project staff have facilitated all eight of the committee's meetings and have represented the committee at meetings of DOE's Transportation Coordination Group (TCG) and Transportation External Coordination Working Group (TEC/WG). Staff have also prepared and submitted comments on DOE activities on behalf of the committee. In addition to working with the committee, project staff have prepared and distributed 20 reports, including some revised reports (see Attachment 1). Staff have also developed a library of reference materials for the benefit of committee members, state officials, and other interested parties. To publicize the library, and to make it more accessible to potential users, project staff have prepared and distributed regular notices of resource availability

Radioactive waste from non-licensed activities - identification of waste, compilation of principles and guidance, and proposed system for final management

International Nuclear Information System (INIS)

Jones, C.; Pers, K.

2001-07-01

Presently national guidelines for the handling of radioactive waste from non-licensed activities are lacking in Sweden. Results and information presented in this report are intended to form a part of the basis for decisions on further work within the Swedish Radiation Protection Institute on regulations or other guidelines on final management and final disposal of this type of waste. An inventory of radioactive waste from non-licensed activities is presented in the report. In addition, existing rules and principles used in Sweden - and internationally - on the handling of radioactive and toxic waste and non-radioactive material are summarized. Based on these rules and principles a system is suggested for the final management of radioactive material from non-licensed activities. A model is shown for the estimation of dose as a consequence of leaching of radio-nuclides from different deposits. The model is applied on different types of waste, e.g. peat ashes, light concrete and low-level waste from a nuclear installation

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

Radioactive waste solidification material

International Nuclear Information System (INIS)

Nishihara, Yukio; Wakuta, Kuniharu; Ishizaki, Kanjiro; Koyanagi, Naoaki; Sakamoto, Hiroyuki; Uchida, Ikuo.

1992-01-01

The present invention concerns a radioactive waste solidification material containing vermiculite cement used for a vacuum packing type waste processing device, which contains no residue of calcium hydroxide in cement solidification products. No residue of calcium hydroxide means, for example, that peak of Ca(OH) 2 is not recognized in an X ray diffraction device. With such procedures, since calcium sulfoaluminate clinker and Portland cement themselves exhibit water hardening property, and slugs exhibit hydration activity from the early stage, the cement exhibits quick-hardening property, has great extension of long term strength, further, has no shrinking property, less dry- shrinkage, excellent durability, less causing damages such as cracks and peeling as processing products of radioactive wastes, enabling to attain highly safe solidification product. (T.M.)

Waste management assessment and technical review programme. WATRP. An international peer review service for radioactive waste management activities

International Nuclear Information System (INIS)

1994-09-01

International Atomic Energy Agency provides international peer review services in radioactive waste management to those Member States that have established radioactive waste management programmes. Such services are provided within Waste Management Assessment and Technical Review Programme (WATRP). The main objective of WATRP is to provide international expertise and information on a requested subject in the field of radioactive waste management and to validate that programmes and activities are sound and performing well. Refs, figs and tabs

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)

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 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

Risk communication system for high level radioactive waste disposal

International Nuclear Information System (INIS)

Kugo, Akihide; Uda, Akinobu; Shimoda, Hirosi; Yoshikawa, Hidekazu; Ito, Kyoko; Wakabayashi, Yasunaga

2005-01-01

In order to gain a better understanding and acceptance of the task of implementing high level radioactive waste disposal, a study on new communication system about social risk information has been initiated by noticing the rapid expansion of Internet in the society. First, text mining method was introduced to identify the core public interest, examining public comments on the technical report of high level radioactive waste disposal. Then we designed the dialog-mode contents based on the theory of norm activation by Schwartz. Finally, the discussion board was mounted on the web site. By constructing such web communication system which includes knowledge base contents, introspective contents, and interactive discussion board, we conducted the experiment for verifying the principles such as that the basic technical knowledge and trust, and social ethics are indispensable in this process to close the perception gap between nuclear specialists and the general public. The participants of the experiment increased their interest in the topics with which they were not familiar and actively posted their opinions on the BBS. The dialog-mode contents were significantly more effective than the knowledge-based contents in promoting introspection that brought people into a greater awareness of problems such as social dilemma. (author)

Radioactive wastes

International Nuclear Information System (INIS)

Straub, C.P.

1975-01-01

A review is presented on the environmental behavior of radioactive wastes. The management of high-level wastes and waste disposal methods were discussed. Some topics included were ore processing, coagulation, absorption and ion exchange, fixation, ground disposal, flotation, evaporation, transmutation and extraterrestrial disposal. Reports were given of the 226 Ra, 224 Ra and tritium activity in hot springs, 90 Sr concentrations in the groundwater and in White Oak Creek, radionuclide content of algae, grasses and plankton, radionuclides in the Danube River, Hudson River, Pacific Ocean, Atlantic Ocean, Lake Michigan, Columbia River and other surface waters. Analysis showed that 239 Pu was scavenged from Lake Michigan water by phytoplankton and algae by a concentration factor of up to 10,000. Benthic invertebrates and fish showed higher 239 Pu concentrations than did their pelagic counterparts. Concentration factors are also given for 234 Th, 60 Co, Fe and Mr in marine organisms. Two models for predicting the impact of radioactivity in the food chain on man were mentioned. In an accidental release from a light-water power reactor to the ocean, the most important radionuclides discharged were found to be 90 Sr, 137 Cs, 239 Pu and activation products 65 Zr, 59 Fe, and 95 Zr

Risk comparison of different treatment and disposal strategies of high level liquid radioactive waste

International Nuclear Information System (INIS)

Fang Dong

1997-01-01

The risk of different treatment and disposal strategies of high level liquid radioactive waste from spent fuel reprocessing is estimated and compared. The conclusions obtained are that risk difference from these strategies is very small and high level liquid waste can be reduced to middle and low level waste, if the decontamination factor for 99 Tc is large enough, which is the largest risk contributor in the high level radioactive waste from spent fuel reprocessing. It is also shown that the risk of high level radioactive waste could be reduced by the technical strategy of combining partitioning and transmutation

Managing commercial high-level radioactive waste: summary

International Nuclear Information System (INIS)

1982-04-01

This summary presents the findings and conclusions of OTA's analysis of Federal policy for the management of commercial high-level radioactive waste - an issue that has been debated over the last decade and that now appears to be moving toward major congressional action. After more than 20 years of commercial nuclear power, the Federal Government has yet to develop a broadly supported policy for fulfilling its legal responsibility for the final isolation of high-level radioactive waste. OTA's study concludes that until such a policy is adopted in law, there is a substantial risk that the false starts, shifts of policy, and fluctuating support that have plagued the final isolation program in the past will continue. The continued lack of final isolation facilities has raised two key problems that underlie debates about radioactive waste policy. First, some question the continued use of nuclear power until it is shown that safe final isolation for the resulting wastes can and will be accomplished, and argue that the failure to develop final isolation facilities is evidence that it may be an insoluble problem. Second, because there are no reprocessing facilities or federal waste isolation facilities to accept spent fuel, existing reactors are running out of spent fuel storage space, and by 1986 some may face a risk of shutting down for some period. Most of the 72,000 metric tons of spent fuel expected to be generated by the year 2000 will still be in temporary storage at that time. While it is possible that utilities could provide all necessary additional storage at reactor sites before existing basins are filled, some supplemental storage may be needed if there are delays in their efforts

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

Developing a Pre-disposal radioactive waste management framework for malawi

International Nuclear Information System (INIS)

Guasi, Ephron

2016-04-01

In Malawi, uranium mining and other potential radioactive waste generating activities are on the increase. An elaborate national policy document and strategy on radioactive waste management is however not available. A national policy is important because it provides overall direction and the basis for decision making with respect to the management of radioactive waste in a country. Thus the absence of the national policy creates a gap in the country’s regulatory framework for ensuring safety and protection of people and the environment from sources of ionizing radiation. The present study was undertaken to minimize the impact of this regulatory framework gap by proposing a predisposal radioactive waste management framework for Malawi. This was achieved by analyzing the current and anticipated applications of radioactive materials and activities. The international and national regulatory requirements related to predisposal radioactive waste management were also reviewed and analyzed. The study found out that a predisposal radioactive waste management frame work comprised of onsite management of wastes from hospitals and uranium mining and export of high activity disused sources to supplier or management facilities in nearby countries would be the best for Malawi for now and the next ten years. (au)

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

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

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.

Educational support programs: Office of Civilian Radioactive Waste Management

International Nuclear Information System (INIS)

Williamson, R.C.

1989-01-01

The Office of Civilian Radioactive Waste Management (OCRWM) currently sponsors two educationally related programs: the Radioactive Waste Management Fellowship Program and the Radioactive Waste Management Research Program for Historically Black Colleges and Universities (HBCU). The graduate fellowship program was implemented in 1985 to meet the US Department of Energy's (DOE's) expected manpower needs for trained scientists and engineers to assist in carrying out the activities of the Nuclear Waste Policy Act. It is recognized that a shortage of master's and doctoral level scientists and engineers in disciplines supportive of the nation's high-level radioactive waste management (RWM) program may impede the DOE's ability to properly carry out its mission under the act. The fellowship program encourages talented undergraduate students to enter graduate programs designed to educate and train them in fields directly related to RWM. The program supports graduate students in various disciplines, including nuclear science and engineering, health physics, and certain area of geology and chemical engineering. It also encourages universities to support and improve research activities and academic programs related to the management of spent nuclear fuel and high-level radioactive waste

Radioactive waste management - an educational challenge

International Nuclear Information System (INIS)

Tulenko, J.S.

1991-01-01

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

Radiation protection challenges in the management of radioactive waste from high-energy accelerators.

Science.gov (United States)

Ulrici, Luisa; Algoet, Yvon; Bruno, Luca; Magistris, Matteo

2015-04-01

The European Laboratory for Particle Physics (CERN) has operated high-energy accelerators for fundamental physics research for nearly 60 y. The side-product of this activity is the radioactive waste, which is mainly generated as a result of preventive and corrective maintenance, upgrading activities and the dismantling of experiments or accelerator facilities. Prior to treatment and disposal, it is common practice to temporarily store radioactive waste on CERN's premises and it is a legal requirement that these storage facilities are safe and secure. Waste treatment typically includes sorting, segregation, volume and size reduction and packaging, which will depend on the type of component, its chemical composition, residual activity and possible surface contamination. At CERN, these activities are performed in a dedicated waste treatment centre under the supervision of the Radiation Protection Group. This paper gives an overview of the radiation protection challenges in the conception of a temporary storage and treatment centre for radioactive waste in an accelerator facility, based on the experience gained at CERN. The CERN approach consists of the classification of waste items into 'families' with similar radiological and physical-chemical properties. This classification allows the use of specific, family-dependent techniques for radiological characterisation and treatment, which are simultaneously efficient and compliant with best practices in radiation protection. The storage was planned on the basis of radiological and other possible hazards such as toxicity, pollution and fire load. Examples are given of technical choices for the treatment and radiological characterisation of selected waste families, which could be of interest to other accelerator facilities. © The Author 2014. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

World ocean and radioactive wastes

International Nuclear Information System (INIS)

Kiknadze, O.E.; Sivintsev, Yu.V.

2000-01-01

The radioecological situation that took shape in the Arctic, North Atlantic Ocean and Far East regions as a result of radioactive waste marine disposal was assessed. Accurate account of radionuclides formation and decay in submerged water-water reactors of nuclear submarines suggests that total activity of radioactive waste disposed near the Novaya Zemlya amounted to 107 kCi by the end of 1999. Activity of radioactive waste disposed in the North Atlantic currently is not in excess of 430 kCi. It is pointed out that the Far East region heads the list in terms of total activity disposed (529 kCi). Effective individual dose for critical groups of population in the Arctic, North Atlantic and Far East regions was determined. The conclusion was made that there is no detrimental effect of the radioactive waste disposed on radioecological situation in the relevant areas [ru

The Activities of Nuclear Training Centre Ljubljana in the Area of Radioactive Waste Management

International Nuclear Information System (INIS)

Jencic, I.

2006-01-01

Nuclear Training Centre Ljubljana has several activities related to radioactive waste management. These activities include training of professionals in the area of nuclear physics and nuclear technology, radiation protection courses, organization of international courses and workshops in the area of radioactive waste management, and public information on radioactivity and waste management. The paper will describe the specifics and the extent of training related to radioactive waste. Recently we have participated in a European coordination action CETRAD and an overview of the results of this project will also be presented. Very important component of our activity is public information that is based on an information centre and live lectures to organized groups of visitors, mostly schoolchildren. About one half of one school generation of Slovenia visits the Information centre every year. A poll is conducted among visitors every year and its results are a very useful tool to follow the evolution of public opinion on nuclear energy and radioactive waste disposal. The latter is, at least in Slovenia, still considered as the major obstacle against the use of nuclear energy. (authors)

Final disposal of high-level radioactive waste. State of knowledge and development for safety assessment

International Nuclear Information System (INIS)

Sato, Seichi; Muraoka, Susumu; Murano, Toru

1995-01-01

In Europe and USA, the formation disposal of high level radioactive waste entered the stage of doing the activities aiming at its execution. Also in Japan, the storage of high level waste began in the spring of 1995. Regarding the utilization of nuclear power, the establishment of the technology for disposing radioactive waste is the subject of fist priority, and the stage that requires its social recognition has set in. There are the features of formation disposal in that the disposal is in the state of confining extremely large amount of radioactivity, and that the assessment of long term safety exceeding tens of thousands years is demanded. The amount of occurrence and the main nuclides of high level radioactive waste, the disposal as seen in the Coady report and in the IAEA standard, the selection of dispersion or confinement and the selection of passive system or long term human participation, the reason why formation disposal is selected, the features of formation disposal and the way of advancing the research, the general techniques of safety assessment, artificial barriers and natural barriers for formation disposal, and the subjects of formation disposal are described. (K.I.) 57 refs

What are Spent Nuclear Fuel and High-Level Radioactive Waste?

International Nuclear Information System (INIS)

2002-01-01

Spent nuclear fuel and high-level radioactive waste are materials from nuclear power plants and government defense programs. These materials contain highly radioactive elements, such as cesium, strontium, technetium, and neptunium. Some of these elements will remain radioactive for a few years, while others will be radioactive for millions of years. Exposure to such radioactive materials can cause human health problems. Scientists worldwide agree that the safest way to manage these materials is to dispose of them deep underground in what is called a geologic repository

RADWASS update. Radioactive Waste Safety Standards Programme

International Nuclear Information System (INIS)

Delattre, D.

2000-01-01

By the late 1980s, the issue of radioactive wastes and their management was becoming increasingly politically important. The IAEA responded by establishing a high profile family of safety standards, the Radioactive Waste Safety Standards (RADWASS). By this means, the IAEA intended to draw attention to the fact that well-established procedures for the safe management of radioactive wastes already were in place. The programme was intended to establish an ordered structure for safety documents on waste management and to ensure comprehensive coverage of all relevant subject areas. RADWASS documents are categorized under four subject areas - discharges, predisposal, disposal, and environmental restoration. The programme is overseen through a formalized review and approval mechanism that was established in 1996 for all safety standards activities. The Waste Safety Standards Committee (WASSC) is a standing body of senior regulatory officials with technical expertise in radioactive waste safety. To date, three Safety Requirements and seven Safety Guides have been issued

Information about activity, status and radiation conditions of Republic radioactive waste repository

International Nuclear Information System (INIS)

Saidumarov, P.

2000-01-01

All radioactive wastes in the Republic of Uzbekistan are stored in the Republic Radioactive Waste Repository in Parkent district of Tashkent region. In the facility there are 2 tanks for solid radioactive waste, each of 800 m 3 , one of them is full, second is in operation; 2 tanks for liquid radioactive waste each tank of 200 m 3 , both of them are empty; 6 storages, each of 3 m 3 all of them are empty; 3 storages for spent radioactive sources, one of them is full, 2 of them are in operation; 4 storages for high level radioactive waste, each storage of 3.5 m 3 , one of them is in operation, 3 are empty; one sealed storage containing 135 m 3 of concrete blocks with waste from electronic industry. According to conclusions of a few competent examinations RRWR does not cause damage to the environment. Geographic location and technical conditions of the repository are satisfactory. Low deposition of underground water (62 m) excludes penetration of radioisotopes. There were no radiation accidents during the repository operation

Radioactive waste management in the VS military nuclear industry

International Nuclear Information System (INIS)

Kobal'chuk, O.V.; Kruglov, A.K.; Sokolova, I.D.; Smirnov, Yu.V.

1989-01-01

Organization and plans of radioactive waste management in the US military nuclear industry, determining transition from the policy of temporal waste storage to their final and safe disposal are presented. Programs of long-term management of high-level, transuranium and low-level wastes, the problems of the work financing and the structure of management activities related to the radioactive waste processing military nuclear industry enterprises are considered

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)

Radioactive waste management

International Nuclear Information System (INIS)

Pahissa Campa, Jaime; Pahissa, Marta H. de

2000-01-01

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

High-level radioactive wastes. Supplement 1

International Nuclear Information System (INIS)

McLaren, L.H.

1984-09-01

This bibliography contains information on high-level radioactive wastes included in the Department of Energy's Energy Data Base from August 1982 through December 1983. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number. 1452 citations

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

OCRWM [Office of Civilian Radioactive Waste Management] publications catalog on high-level radioactive waste management

International Nuclear Information System (INIS)

1987-07-01

The US Department of Energy's (DOE's) Office of Civilian Radioactive Waste Management (OCRWM) is publishing this catalog to provide citations of selected technical and public information on the subject of high-level radioactive waste management. The catalog is a resource and reference tool. It will be updated and printed annually. The online catalog will be available for review through OCRWM's Product Record System (PRS) and can eventually be made available to the public. The printed catalog version is suitable for libraries and those individuals needing either a broad base of information or a particular source; the computerized catalog version provides the most current information resources available, since updates to citations will be made as they are received. The number of documents suitable for listing in this catalog is expected to grow significantly each year

Processing vessel for high level radioactive wastes

International Nuclear Information System (INIS)

Maekawa, Hiromichi

1998-01-01

Upon transferring an overpack having canisters containing high level radioactive wastes sealed therein and burying it into an underground processing hole, an outer shell vessel comprising a steel plate to be fit and contained in the processing hole is formed. A bury-back layer made of dug earth and sand which had been discharged upon forming the processing hole is formed on the inner circumferential wall of the outer shell vessel. A buffer layer having a predetermined thickness is formed on the inner side of the bury-back layer, and the overpack is contained in the hollow portion surrounded by the layer. The opened upper portion of the hollow portion is covered with the buffer layer and the bury-back layer. Since the processing vessel having a shielding performance previously formed on the ground, the state of packing can be observed. In addition, since an operator can directly operates upon transportation and burying of the high level radioactive wastes, remote control is no more necessary. (T.M.)

Radioactive waste management practices in India: achievements and challenges

International Nuclear Information System (INIS)

Wattal, P.K.; Basu, S.

2013-01-01

Safe and effective management of radioactive waste has been given utmost importance from the very inception of nuclear industry in India. This article gives an account of the basic principles, practices being followed in our country to achieve this objective. A brief description of the existing methods for management of diverse kinds of radioactive wastes including high level radioactive waste and also the research and development activities to address the future challenges is presented in the article. (author)

Ocean disposal of radioactive waste: Status report

International Nuclear Information System (INIS)

Calmet, D.P.

1989-01-01

For hundreds of years, the seas have been used as a place to dispose of wastes resulting from human activities and although no high level radioactive waste (HLW) has been disposed of into the sea, variable amounts of packaged low level radioactive waste (LLW) have been dumped at more than 50 sites in the northern part of the Atlantic and Pacific oceans. So far, samples of sea water, sediments and deep sea organisms collected on the various sites have not shown any excess in the levels of radionuclides above those due to nuclear weapons fallout except on certain occasions where caesium and plutonium were detected at higher levels in samples taken close to packages at the dumping site. Since 1957, the date of its first meeting to design methodologies to assess the safety of ''radioactive waste disposal into the sea'', the IAEA has provided guidance and recommendations for ensuring that disposal of radioactive wastes into the sea will not result in unacceptable hazards to human health and marine organisms, damage to amenities or interference with other legitimate uses of the sea. Since the Convention for the Prevention of Marine Pollution by Dumping of Wastes and Other Matter (referred to as the London Dumping Convention) came into force in 1975, the dumping of waste has been regulated on a global scale. The London Dumping Convention entrusted IAEA with specific responsibilities for the definition of high level radioactive wastes unsuitable for dumping at sea, and for making recommendations to national authorities for issuing special permits for ocean dumping of low level radioactive wastes. This paper presents a status report of immersion operations of low-level radioactive waste and the current studies the IAEA is undertaking on behalf of the LDC

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)

Development plan. High activity-long living wastes project. Abstract

International Nuclear Information System (INIS)

2007-01-01

This brochure presents the actions that the ANDRA (the French national agency of radioactive wastes) has to implement in the framework of the project of high activity-long living (HALL) radioactive wastes (HAVL project) conformably to the requirements of the program defined in the law from June 28, 2006 (law no 2006-739). This law precises the three, complementary, research paths to explore for the management of this type of wastes: separation and transmutation of long-living radioactive elements, reversible disposal in deep geologic underground, and long duration storage. The ANDRA's action concerns the geologic disposal aspect. The following points are presented: the HALL wastes and their containers, the reversible disposal procedure, the HAVL project: financing of researches, storage concepts, development plan of the project (dynamics, information and dialogue approach, input data, main steps, schedule); the nine programs of the HAVL project (laboratory experiments and demonstration tests, surface survey, scientific program, simulation program, surface engineering studies and technological tests, information and communication program, program of environment and facilities surface observation and monitoring, waste packages management, monitoring and transport program, disposal program); the five transverse technical and scientific activities (safety, reversibility, cost, health and occupational safety, impact study). (J.S.)

IAEA decadal activities in the field of radioactive gaseous waste management

International Nuclear Information System (INIS)

Plumb, G.R.

1991-01-01

The IAEA has long recognized that gaseous waste management is vital in the design and safe operation of all nuclear facilities such that in the decade of the 1980's the IAEA program covered the important aspects of the entire field. The activities reviewed in this paper were marked at the outset by a comprehensive international symposium on the subject in February 1980 organized by the IAEA jointly with the Nuclear Energy Agency of the OECD when the detailed state-of-the-art was established in 43 papers. In the interim, experts have been convened in IAEA sponsored meetings to result in sixteen technical documents which included summaries of three substantial Co-ordinated Research Programs. Early IAEA activities paid particular attention to management of gas radionuclides which from a matured nuclear industry, could be judged to build-up to long-term sources of irradiation for regional and global populations. Mid-term ongoing activities in handling and retention of gaseous radionuclides arising from abnormal operations in nuclear power plants were given much emphasis following the Chernobyl accident. In the latter years the IAEA activities included detailed examinations of the design and operation of gas cleaning systems for the range of nuclear facilities. Technical reports on gaseous waste management were issued relating to high-level liquid waste conditioning plants (including control of semi-volatiles), nuclear power plants, low- and intermediate-level radioactive materials handling facilities and radioactive waste incinerators

FERRATE TREATMENT FOR REMOVING CHROMIUM FROM HIGH-LEVEL RADIOACTIVE TANK WASTE

International Nuclear Information System (INIS)

Sylvester, Paul; Rutherford, Andy; Gonzalez-Martin, Anuncia; Kim, J.; Rapko, Brian M.; Lumetta, Gregg J.

2000-01-01

A method has been developed for removing chromium from alkaline high-level radioactive tank waste. Removing chromium from these wastes is critical in reducing the volume of waste requiring expensive immobilization and deep geologic disposition. The method developed is based on the oxidation of insoluble chromium(III) compounds to soluble chromate using ferrate. The tests conducted with a simulated Hanford tank sludge indicate that the chromium removal with ferrate is more efficient at 5 M NaOH than at 3 M NaOH. Chromium removal increases with increasing Fe(VI)/Cr(III) molar ratio, but the chromium removal tends to level out for Fe(VI)/Cr(III) greater than 10. Increasing temperature leads to better chromium removal, but higher temperatures also led to more rapid ferrate decomposition. Tests with radioactive Hanford tank waste generally confirmed the simulant results. In all cases examined, ferrate enhanced the chromium removal, with a typical removal of around 60-70% of the total chromium present in the washed sludge solids. The ferrate leachate solutions did not contain significant concentrations of transuranic elements, so these solutions could be handled as low-activity waste

Modeling for speciation of radionuclides in waste packages with high-level radioactive wastes

International Nuclear Information System (INIS)

Weyand, Torben; Bracke, Guido; Seher, Holger

2016-10-01

Based on a literature search on radioactive waste inventories adequate thermodynamic data for model inventories were derived for geochemical model calculations using PHREEQC in order to determine the solid phase composition of high-level radioactive wastes in different containers. The calculations were performed for different model inventories (PWR-MOX, PWR-UO2, BWR-MOX, BMR-UO2) assuming intact containers under reduction conditions. The effect of a defect in the container on the solid phase composition was considered in variation calculations assuming air contact induced oxidation.

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

Canadian high-level radioactive waste management system issues

International Nuclear Information System (INIS)

Allan, C.J.; Gray, B.R.

1992-01-01

In Canada responsibility for the management of radioactive wastes rests with the producer of those wastes. This fundamental principle applies to such diverse wastes as uranium mine and mill tailings, low-level wastes from universities and hospitals, wastes produced at nuclear research establishments, and wastes produced at nuclear generating stations. The federal government has accepted responsibility for historical wastes for which the original producer can no longer be held accountable. Management of radioactive wastes is subject to the regulatory control of the Atomic Energy Control Board, the federal agency responsible for regulating the nuclear industry. In this paper the authors summarize the current situation concerning the management of high level (used nuclear fuel) wastes. In 1981 the two governments also announced that selection of a disposal site would not proceed, and responsibility for site selection and operation would not be assigned until the Concept for used fuel disposal had been reviewed and assessed. Thus the concept assessment is generic rather than site specific. The Concept that has been developed has been designed to conform with safety and performance criteria established by the Atomic Energy Control Board. It is based on burial deep in plutonic rock of the Canadian Shield, using a multi-barrier approach with a series of engineered and natural barriers: these include the waste form, container, buffer and backfill, and the host rock

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)

High-level radioactive wastes. Supplement 1

Energy Technology Data Exchange (ETDEWEB)

McLaren, L.H. (ed.)

1984-09-01

This bibliography contains information on high-level radioactive wastes included in the Department of Energy's Energy Data Base from August 1982 through December 1983. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number. 1452 citations.

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

Recent IAEA activities to support utilisation of cementitious materials in radioactive waste management

International Nuclear Information System (INIS)

Ojowan, M.I.; Samanta, S.K.

2015-01-01

The International Atomic Energy Agency promotes a safe and effective management of radioactive waste and has suitable programmes in place to serve the needs of Member States in this area. In support of these programmes the Waste Technology Section fosters technology transfer, promotes information exchange and cooperative research, as well as builds capacity in Member States to manage radioactive wastes, resulting both from the nuclear fuel cycle and nuclear applications. Technical assistance in pre disposal area covers all of these activities and is delivered through established Agency mechanisms including publication of technical documents. While the Agency does not conduct any in-house research activities, its Coordinated Research Projects (CRPs) foster research in Member States. There are 2 CRPs concerning cementitious materials: a CRP on cements and an on-going CRP on irradiated graphite waste. The CRP on cements has resulted in the recent IAEA publication TECDOC-1701. An important activity concerned with characterisation of cementitious waste forms is the LABONET network of laboratory-based centres of expertise involved in the characterization of low and intermediate level radioactive wastes. The Waste Technology Section is preparing a series of comprehensive state of the art technical handbooks

Volume reduction through incineration of low-activity radioactive wastes

International Nuclear Information System (INIS)

Eymeri, J.; Gauthey, J.C.; Chaise, D.; Lafite, G.

1993-01-01

The aim of the waste treatment plant, designed by Technicatome (CEA) for an Indonesian Nuclear Research Center, is to reduce through incineration the volume of low-activity radioactive wastes such as technological solids (cotton, PVC, paper board), biological solids (animal bones) and liquids (cutting fluids...). The complete combustion is realized with a total air multi-fuel burner (liquid wastes) and flash pyrolysis-complete combustion (solid wastes). A two stage flue gas filtration system, a flue gas washing system, and an ash recovery system are used. A test platform has been built. 3 figs

Recycling of radioactive mineral waste by activity separation

International Nuclear Information System (INIS)

Schartmann, F.; Cramer, T.; Meier-Kortwig, J.; Diedenhofen, S.; Wotruba, H.

2005-01-01

The AST process is a device for the recycling of building rubble originating from the dismantling of nuclear installations. Due to the activity separation in the process, a major part of rubble which would have otherwise been radioactive waste can now be cleared. The AST process has been developed in the course of the combined research project ''Aufbereitung radioaktiver mineralischer Rueckstaede durch Aktivitaetsseparation (Recycling of radioactive mineral waste by activity separation)'' which was sponsored by the BMBF (Federal Ministry for Education and Research). The first step was to investigate the activity distribution between the various constituents of activated heavy concrete (additions: hematite, magnetite, iron cuttings), of contaminated heavy and normal concrete, as well as of composition floor. Heavy concrete with metal additions showed a selective activation of the various constituents. Contaminated rubble often exhibits a selective enrichment of the activity in the cement in contrast to the aggregate. The AST facility for activity separation was designed on the basis of these results. Trial operation with various types of building rubble was carried out using three methods for sorting, screening according to grain size, magnetic separation and radiometric sorting. The use of these three methods was adapted to the material. (orig.)

The puzzle of nuclear wastes. Radioactive threat to your health..

International Nuclear Information System (INIS)

2007-01-01

This document, published by the French association 'Sortir du nucleaire' (Get out of nuclear), gives some information on what is radioactivity, the radioactive materials as a risk for living organisms, nuclear wastes all over France (list and map of the storage sites, power plants and fuel cycle centers), nuclear wastes at every step of the nuclear connection, the insolvable problem of high activity wastes, burying nuclear wastes in order to better forget them, radioactivity as a time bomb for our health, radioactive effluents as an under-estimated risk, artificial radioactivity already responsible for the death of 61 million people in the world, and so on

Defense radioactive waste management

International Nuclear Information System (INIS)

Hindman, T.B. Jr.

1988-01-01

The Office of Defense Programs (DP), U.S. Department of Energy, is responsible for the production of nuclear weapons and materials for national defense. Pursuant to this mission, DP operates a large industrial complex that employs over 60,000 people at various installations across the country. As a byproduct of their activities, these installations generate radioactive, hazardous, or mixed wastes that must be managed in a safe and cost-effective manner in compliance with all applicable Federal and STate environmental requirements. At the Federal level such requirements derive primarily from the Atomic Energy Act, the Resource Conservation and Recovery Act (RCRA), the comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and the Superfund Amendments and Reauthorization Act (SARA). Responsibility for DP activities in connection with the disposal of defense wastes is consolidated within the Office of Defense Waste and Transportation Management (DWTM). This paper discusses these activities which consist of five principal elements: the environmental restoration of inactive DP facilities and sites, the processing storage and disposal of wastes associated with ongoing operations at active DP facilities, research and development directed toward the long-term disposal of radioactive, hazardous, mixed wastes, technology development directly supporting regulatory compliance, and the development of policies, procedures, and technologies for assuring the safe transportation of radioactive and hazardous materials

Radioactive Demonstrations Of Fluidized Bed Steam Reforming As A Supplementary Treatment For Hanford's Low Activity Waste And Secondary Wastes

International Nuclear Information System (INIS)

Jantzen, C.; Crawford, C.; Cozzi, A.; Bannochie, C.; Burket, P.; Daniel, G.

2011-01-01

The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. Currently there are approximately 56 million gallons of highly radioactive mixed wastes awaiting treatment. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Therefore, Supplemental Treatment is required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. The Supplemental Treatment chosen will immobilize that portion of the retrieved LAW that is not sent to the WTP's LAW Vitrification facility into a solidified waste form. The solidified waste will then be disposed on the Hanford site in the Integrated Disposal Facility (IDF). In addition, the WTP LAW vitrification facility off-gas condensate known as WTP Secondary Waste (WTP-SW) will be generated and enriched in volatile components such as Cs-137, I-129, Tc-99, Cl, F, and SO4 that volatilize at the vitrification temperature of 1150 C in the absence of a continuous cold cap. The current waste disposal path for the WTP-SW is to recycle it to the supplemental LAW treatment to avoid a large steady state accumulation in the pretreatment-vitrification loop. Fluidized Bed Steam Reforming (FBSR) offers a moderate temperature (700-750 C) continuous method by which LAW and/or WTP-SW wastes can be processed irrespective of whether they contain organics, nitrates, sulfates/sulfides, chlorides

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

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

ANDRA - National Radioactive Waste Management Agency. Activity report 2006. Management report - Financial statements 2006

International Nuclear Information System (INIS)

2007-06-01

Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity report with the management and financial statements report of the Andra for the year 2006

The Radioactive Waste Management at Studsvik

Energy Technology Data Exchange (ETDEWEB)

Hedlund, R; Lindskog, A

1966-04-15

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

The Radioactive Waste Management at Studsvik

International Nuclear Information System (INIS)

Hedlund, R.; Lindskog, A.

1966-04-01

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

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.)

Key scientific challenges in geological disposal of high level radioactive waste

International Nuclear Information System (INIS)

Wang Ju

2007-01-01

The geological disposal of high radioactive waste is a challenging task facing the scientific and technical world. This paper introduces the latest progress of high level radioactive disposal programs in the latest progress of high level radioactive disposal programs in the world, and discusses the following key scientific challenges: (1) precise prediction of the evolution of a repository site; (2) characteristics of deep geological environment; (3) behaviour of deep rock mass, groundwater and engineering material under coupled con-ditions (intermediate to high temperature, geostress, hydraulic, chemical, biological and radiation process, etc); (4) geo-chemical behaviour of transuranic radionuclides with low concentration and its migration with groundwater; and (5) safety assessment of disposal system. Several large-scale research projects and several hot topics related with high-level waste disposal are also introduced. (authors)

Radioactive waste packages stored at the Aube facility for low-intermediate activity wastes. A selective and controlled storage

International Nuclear Information System (INIS)

2005-01-01

The waste package is the first barrier designed to protect the man and the environment from the radioactivity contained in wastes. Its design is thus particularly stringent and controlled. This brochure describes the different types of packages for low to intermediate activity wastes like those received and stored at the Aube facility, and also the system implemented by the ANDRA (the French national agency of radioactive wastes) and by waste producers to safely control each step of the design and fabrication of these packages. (J.S.)

Treatment and Storage of High-Level Radioactive Wastes. Proceedings of the Symposium on Treatment and Storage of High-Level Radioactive Wastes

International Nuclear Information System (INIS)

1963-01-01

A variety of radioactive materials having no immediate use result from the utilization of atomic energy. The manner in which these materials are handled has repercussions on reactor economy and technology, on the health and safety of persons and populations and on atomic legislation. Excellent progress has been made in developing a technology capable of safely and economically dealing with these materials so that no immediate problems exist. The highly radioactive ''wastes'' arising from the reprocessing of irradiated fuel pose long-range problems, however, and methods for the ultimate disposal of these wastes must be developed and evaluated. Such development and evaluation can be materially assisted by providing the scientists doing the work with an opportunity of exchanging ideas and information on their experience. Therefore, the IAEA, as part of its programme of promoting nuclear technology, convened in Vienna from 8-12 October 1962 the Symposium on the Treatment and Storage of High-level Radioactive Wastes. The Symposium was attended by 130 scientists from 19 countries and two international organizations. Thirty-three papers were presented and discussed in full and formed a background for a panel discussion of chairmen near the end of the Symposium. The papers and a record of the discussions are published in this single volume. It is hoped that the information thus recorded will achieve the desired purpose of assisting the peaceful development of atomic energy

Characterization of the solid radioactive waste from Cernavoda NPP

International Nuclear Information System (INIS)

Iordache, M.; Lautaru, V.; Bujoreanu, D.

2005-01-01

During the operation of a nuclear plant significant quantities of radioactive waste result that have a very large diversity. At Cernavoda NPP large amounts of wastes are either non-radioactive wastes or radioactive wastes, each of these being managed completely different from each other. For a CANDU type reactor, the occurrence of radioactive wastes is due to contamination with the following types of radioactive substances: - fission products resulting from nuclear fuel burning; - activated products from materials composing the technological systems; - activated products in process fluids. Radioactive wastes can be in solid, liquid or gas form. At Cernavoda NPP the solid wastes represent about 70% of the waste volume which is produced during plant operation and as a consequence of maintenance and decontamination operations. The most important types of solid wastes that are obtained and then handled, processed (if necessary) and temporarily stored are: solid low-level radioactive wastes (classified as compactible and non-compactible), solid medium radioactive wastes, spent resins, used filters and filter cartridges. The liquid radioactive waste class includes organic liquids (used oil, scintillator liquids and used solvents) and aqueous wastes resulting from process system operating, from decontamination and maintenance operations. Radioactive gas wastes occur subsequently to the fission process inside the fuel elements as well as due to the neutron activation of process fluids in the reactor systems. As result of plant operation, iodine, noble gases, tritium and radioactive particles occur and are passed toward the ventilation stack in a controlled manner so that environmental release of radioactive materials with concentrations exceeding the maximum permissible level could not occur. (authors)

USDOE activities in low-level radioactive waste treatment

International Nuclear Information System (INIS)

Vath, J.E.

1981-01-01

This paper describes current research, development and demonstration (R, D and D) programs sponsored by the US Department of Energy in the area of low-level radioactive waste treatment. During the twelve month period ending September 30, 1981, 14 prime US Department of Energy contractors were involved with over 40 low-level radioactive waste disposal technology projects. Three specific projects or task areas have been selected for discussion to illustrate new and evolving technologies, and application of technology developed in other waste management areas to low-level waste treatment. The areas to be discussed include a microwave plasma torch incinerator, application of waste vitrification, and decontamination of metal waste by melting

Radioactive Waste and Clean-up: Introduction

International Nuclear Information System (INIS)

Collard, G.

2007-01-01

geological disposal of high active waste. Therefore SCK-CEN, NIRAS/ONDRAF and the Economic Interest Grouping EURIDICE join their effort to demonstrate the feasibility of geological disposal of radioactive waste and spent fuel in Boom clay. A first step of this demonstration is the PRACLAY project. The objectives of the PRACLAY project are the demonstration of the reference design for vitrified HLW, as well as the characterization, verification, confirmation and demonstration of relevant elements of the disposal system and their behaviour by means of a combination of small surface and large in situ experiments

Technical career opportunities in high-level radioactive waste management

International Nuclear Information System (INIS)

1993-01-01

Technical career opportunities in high-level radioactive waste management are briefly described in the areas of: Hydrology; geology; biological sciences; mathematics; engineering; heavy equipment operation; and skilled labor and crafts

Safe disposal of high-level radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Ringwood, A E [Australian National Univ., Canberra. Research School of Earth Sciences

1980-10-01

Current strategies in most countries favour the immobilisation of high-level radioactive wastes in borosilicate glasses, and their burial in large, centralised, mined repositories. Strong public opposition has been encountered because of concerns over safety and socio-political issues. The author develops a new disposal strategy, based on immobilisation of wastes in an extremely resistant ceramic, SYNROC, combined with burial in an array of widely dispersed, very deep drill holes. It is demonstrated that the difficulties encountered by conventional disposal strategies can be overcome by this new approach.

Status report on Texas Low-Level Radioactive Waste Disposal Authority activities

International Nuclear Information System (INIS)

Avant, R.V. Jr.

1990-01-01

In 1981, the Texas Low-Level Radioactive Waste Disposal Authority was created by Article 4590f-1 to site, develop, operate, decommission, and close a low-level radioactive waste disposal facility for Texas generated waste. In 1989, the Authority's act was recodified by the Texas legislature in the Health and Safety Code., Title 5. Sanitation and Environmental Quality, Subtitle D. Nuclear and Radioactive Materials, Chapter 402. The Authority is governed by a Board of Directors appointed by the Governor, composed of a certified health physicist, geologist, attorney, medical doctor, and two private citizens. Under the statute, low-level radioactive waste is defined as any radioactive material with a half-life of 35 years or less or having less than 10 nanocuries per gram of transuranics. Materials with half-lives of greater than 35 years may be classed as low-level waste if special criteria are established by the Texas Department of Health Bureau of Radiation Control. Subsequent sessions of the legislature have amended the act to revise siting criteria, require consideration of state land, create a Citizen's Advisory Committee, incorporate alternative designs, and establish a special low-level radioactive waste account in the state treasury. The Authority began its activities in 1982. The Authority has proposed a site in far West Texas near Fort Hancock, but El Paso County, the neighboring county to the west, has instituted three separate lawsuits to slow or stop the site selection process. Particular attention was paid early in the site selection process to items which could be fatal flaws from a licensing standpoint. This paper discusses the Fort Hancock site description, site evaluation studies, siting issues, waste volume projections, facility design, license application, cost and schedule

Radioactive wastes and spent fuels management in Argentina

International Nuclear Information System (INIS)

Maset, Elvira R.

2006-01-01

CNEA was created in 1950 and since then has carried out research and development activities, production of radioisotopes, medical and industrial applications, and those activities related with the nuclear fuel cycle, including the operation of two nuclear power stations. More ever, different public and private institutions use radioactive materials in medical, industrial and research activities. These activities generate different types of radioactive waste, desuse sealed sources and spent fuel. The management of radioactive waste of all types produced in the country, as the spent nuclear fuel of power and research reactors and the used radioactive sources was always and it is at present a CNEA's responsibility. In February 2003, according to the Law No. 25.018, called 'Management of Radioactive Waste Regimen', the 'Radioactive Waste Management National Programme' was created by CNEA to fulfill the institutional functions and responsibilities established in the Law, in order to guarantee the safe management of radioactive waste according to the regulations established by the Argentine Nuclear Regulatory Agency and to the legislation in force. (author) [es

Efficient handling of high-level radioactive cell waste in a vitrification facility analytical laboratory

International Nuclear Information System (INIS)

Roberts, D.W.; Collins, K.J.

1998-01-01

The Savannah River Site''s (SRS) Defense Waste Processing Facility (DWPF) near Aiken, South Carolina, is the world''s largest and the United State''s first high level waste vitrification facility. For the past 1.5 years, DWPF has been vitrifying high level radioactive liquid waste left over from the Cold War. The vitrification process involves the stabilization of high level radioactive liquid waste into borosilicate glass. The glass is contained in stainless steel canisters. DWPF has filled more than 200 canisters 3.05 meters (10 feet) long and 0.61 meters (2 foot) diameter. Since operations began at DWPF in March of 1996, high level radioactive solid waste continues to be generated due to operating the facility''s analytical laboratory. The waste is referred to as cell waste and is routinely removed from the analytical laboratories. Through facility design, engineering controls, and administrative controls, DWPF has established efficient methods of handling the high level waste generated in its laboratory facility. These methods have resulted in the prevention of undue radiation exposure, wasted man-hours, expenses due to waste disposal, and the spread of contamination. This level of efficiency was not reached overnight, but it involved the collaboration of Radiological Control Operations and Laboratory personnel working together to devise methods that best benefited the facility. This paper discusses the methods that have been incorporated at DWPF for the handling of cell waste. The objective of this paper is to provide insight to good radiological and safety practices that were incorporated to handle high level radioactive waste in a laboratory setting

Radioactive waste programme in Latvia

International Nuclear Information System (INIS)

Salmins, A.

2000-01-01

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

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 in Belgium

International Nuclear Information System (INIS)

Dejonghe, P.

1977-01-01

In 1975 the research association BELGOWASTE was founded in order to prepare a technical and administrative plan for radioactive waste management in Belgium and to take the preliminary steps for establishing an organization which would be responsible for this activity. The association made a survey of all forecasts concerning radioactive waste production by power reactors and the fuel cycle industry based on various schemes of development of the nuclear industry. From the technical point of view, the reference plan for waste management envisages: Purification at the production site of large volumes of low-level effluents; construction of a central facility for the treatment and intermediate storage of process concentrates (slurries, resins, etc.) and medium-level waste; centralization assumes the making of adequate arrangements for transporting waste before final treatment; maximum recovery of plutonium from waste and treatment of resiudal material by incineration at very high temperatures; treatment at the production site of high-level effluents from irradiated fuel reprocessing; construction of an underground long-term storage site for high-level treated waste and plutonium fuel fabrication waste; deep clay formations are at present preferred; disposal of low-level treated waste into the Atlantic ocean. It is intended to entrust the entire responsibility for treatment, disposal and storage of treated waste to a single body with participation by the State, the Nuclear Energy Research Centre (CEN/SCK), the electricity companies and Belgonucleaire. The partners intend to set up their facilities and services in the area of Mol [fr

Ferrate treatment for removing chromium from high-level radioactive tank waste.

Science.gov (United States)

Sylvester, P; Rutherford, L A; Gonzalez-Martin, A; Kim, J; Rapko, B M; Lumetta, G J

2001-01-01

A method has been developed for removing chromium from alkaline high-level radioactive tank waste. Removing chromium from these wastes is critical in reducing the volume of waste requiring expensive immobilization and deep geologic disposition. The method developed is based on the oxidation of insoluble chromium(III) compounds to soluble chromate using ferrate. This method could be generally applicable to removing chromium from chromium-contaminated solids, when coupled with a subsequent reduction of the separated chromate back to chromium(III). The tests conducted with a simulated Hanford tank sludge indicate that the chromium removal with ferrate is more efficient at 5 M NaOH than at 3 M NaOH. Chromium removal increases with increasing Fe(VI)/Cr(II) molar ratio, but the chromium removal tends to level out for Fe(VI)/ Cr(III) greaterthan 10. Increasingtemperature leadsto better chromium removal, but higher temperatures also led to more rapid ferrate decomposition. Tests with radioactive Hanford tank waste generally confirmed the simulant results. In all cases examined, ferrate enhanced the chromium removal, with a typical removal of around 60-70% of the total chromium present in the washed sludge solids. The ferrate leachate solutions did not contain significant concentrations of transuranic elements, so these solutions could be disposed as low-activity 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

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.

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)

Characterization of the solid radioactive waste From Cernavoda NPP

International Nuclear Information System (INIS)

Iordache, M.; Laotaru, V.

2005-01-01

Full text: During the operation of a nuclear plant significant quantities of radioactive waste result that have a very large diversity. At Cernavoda NPP large amounts of wastes are either non-radioactive wastes or radioactive wastes, each of these being managed completely different from which other. For a CANDU type reactor, the appearance of radioactive wastes is due to contamination with the following types of radioactive substances: - fission products resulting from nuclear fuel burning; - activated products from materials composing the technological systems; - activated products in process fluids. Radioactive wastes can be in solid, liquid or gas form. At Cernavoda NPP the solid wastes represent about 70% of the waste volume which is produced during plant operation and as a consequence of maintenance and decontamination operations. The most important types of solid wastes that are obtained and then handled, processed (if necessary) and temporarily stored are: solid low-level radioactive wastes (classified as compactible and non-compactible), solid medium radioactive wastes, spent resins, used filters and filter cartridges. The liquid radioactive waste class includes organic liquids (used oil, scintillator liquids and used solvents) and aqueous wastes resulting from process system operating, from decontamination and maintenance operations. Radioactive gas wastes occur subsequently to the fission process inside the fuel elements as well as due to the neutron activation of process fluids in the reactor systems. As result of plant operation, iodine, noble gases, tritium and radioactive particles occur and are passed toward the ventilation stack in a controlled manner so that environmental release of radioactive materials with concentrations exceeding the maximum permissible level could not occur. (authors)

Managing the nation's commercial high-level radioactive waste

International Nuclear Information System (INIS)

1985-03-01

This report presents the findings and conclusions of OTA's analysis of Federal policy for the management of commercial high-level radioactive waste. It is intended to contribute to the implementation of Nuclear Waste Policy Act of 1982 (NWPA). The major conclusion of that review is that NWPA provides sufficient authority for developing and operating a waste management system based on disposal in geologic repositories. Substantial new authority for other facilities will not be required unless major unexpected problems with geologic disposal are encountered. OTA also concludes that DOE's Draft Mission Plan published in 1984 falls short of its potential for enhancing the credibility and acceptability of the waste management program

Risk assessments for the disposal of high level radioactive wastes

International Nuclear Information System (INIS)

Smith, C.F.

1975-01-01

The risks associated with the disposal of high level wastes derive from the potential for release of radioactive materials into the environment. The assessment of these risks requires a methodology for risk analysis, an identification of the radioactive sources, and a method by which to express the relative hazard of the various radionuclides that comprise the high level waste. The development of a methodology for risk analysis is carried out after a review of previous work in the area of probabilistic risk assessment. The methodology suggested involves the probabilistic analysis of a general accident consequence distribution. In this analysis, the frequency aspect of the distribution is treated separately from the normalized probability function. At the final stage of the analysis, the frequency and probability characteristics of the distribution are recombined to provide an estimate of the risk. The characterization of the radioactive source term is accomplished using the ORIGEN computer code. Calculations are carried out for various reactor types and fuel cycles, and the overall waste hazard for a projected thirty-five year nuclear power program is determined

Method for processing powdery radioactive wastes

International Nuclear Information System (INIS)

Yasumura, Keijiro; Matsuura, Hiroyuki; Tomita, Toshihide; Nakayama, Yasuyuki.

1978-01-01

Purpose: To solidify radioactive wastes with ease and safety at a high reaction speed but with no boiling by impregnating the radioactive wastes with chlorostyrene. Method: Beads-like dried ion exchange resin, powdery ion exchange resin, filter sludges, concentrated dried waste liquor or the like are mixed or impregnated with a chlorostyrene monomer dissolving therein a polymerization initiator such as methyl ethyl ketone peroxide and benzoyl peroxide. Mixed or impregnated products are polymerized to solid after a predetermined of time through curing reaction to produce solidified radioactive wastes. Since inflammable materials are used, this process has a high safety. About 70% wastes can be incorporated. The solidified products have a strength as high as 300 - 400 kg/cm 3 and are suitable to ocean disposal. The products have a greater radioactive resistance than other plastic solidification products. (Seki, T.)

Processing method and processing device for liquid waste containing surface active agent and radioactive material

International Nuclear Information System (INIS)

Nishi, Takashi; Matsuda, Masami; Baba, Tsutomu; Yoshikawa, Ryozo; Yukita, Atsushi.

1998-01-01

Washing liquid wastes containing surface active agents and radioactive materials are sent to a deaerating vessel. Ozone is blown into the deaerating vessel. The washing liquid wastes dissolved with ozone are introduced to a UV ray irradiation vessel. UV rays are irradiated to the washing liquid wastes, and hydroxy radicals generated by photodecomposition of dissolved ozone oxidatively decompose surface active agents contained in the washing liquid wastes. The washing liquid wastes discharged from the UV ray irradiation vessel are sent to an activated carbon mixing vessel and mixed with powdery activated carbon. The surface active agents not decomposed in the UV ray irradiation vessel are adsorbed to the activated carbon. Then, the activated carbon and washing liquid wastes are separated by an activated carbon separating/drying device. Radioactive materials (iron oxide and the like) contained in the washing liquid wastes are mostly granular, and they are separated and removed from the washing liquid wastes in the activated carbon separating/drying device. (I.N.)

National plan for the radioactive and recyclable wastes management of the national inventory of the radioactive and recyclable wastes to an account and a prospective outlook of the pathways of long dated management of radioactive wastes in France

International Nuclear Information System (INIS)

2005-07-01

The introduction recalls the context of the development of the national plan of radioactive and recyclable wastes management (PNGDR-MV), its objectives and its position in the today studies on radioactive wastes. The first part is devoted to the description of existing radioactive wastes management solutions, or engaged by today activities. The second part concerns the radioactive materials of the nuclear industry, which are not considered as wastes, but which can be recyclable because of their high energy potential as fuels for reactors of the future. The third part examines the pathways coherence. The last part is a synthesis of the evaluation, with more attention on the identifies problems. (A.L.B.)

''Project Crystal'' for ultimate storage of highly radioactive waste

International Nuclear Information System (INIS)

Anon.

1983-01-01

NAGRA (The National Association for storage of radioactive waste) in Baden has launched in North Switzerland an extensive geological research program. The current research program, under the title of ''Project Crystal'', aims at providing the scientific knowledge which is required for the assessment of the suitability of the crystalline sub-soil of North Switzerland for the ultimate storage of highly radioactive waste. Safety and feasibility of such ultimate storage are in the forefront of preoccupations. Scientific institutes of France, Germany, USA and Canada are cooperating more particularly on boring research and laboratory analyses. Technical data are given on the USA and German installations used. (P.F.K.)

Design concepts of definitive disposal for high level radioactive wastes

International Nuclear Information System (INIS)

Badillo A, V.E.; Alonso V, G.

2007-01-01

It is excessively known the importance about finding a solution for the handling and disposition of radioactive waste of all level. However, the polemic is centered in the administration of high level radioactive waste and the worn out fuel, forgetting that the more important volumes of waste its are generated in the categories of low level wastes or of very low level. Depending on the waste that will be confined and of the costs, several technological modalities of definitive disposition exist, in function of the depth of the confinement. The concept of deep geologic storage, technological option proposed more than 40 years ago, it is a concept of isolation of waste of long half life placed in a deep underground installation dug in geologic formations that are characterized by their high stability and their low flow of underground water. In the last decades, they have registered countless progresses in technical and scientific aspects of the geologic storage, making it a reliable technical solution supported with many years of scientific work carried out by numerous institutions in the entire world. In this work the design concepts that apply some countries for the high level waste disposal that its liberate heat are revised and the different geologic formations that have been considered for the storage of this type of wastes. (Author)

Technical report from Radioactive Waste Management Funding and Research Center

International Nuclear Information System (INIS)

2007-10-01

As the only one Japanese organization specialized in radioactive waste, RWMC (Radioactive Waste Management Funding and Research Center) has been conducting the two major roles; R and D and the fund administration for radioactive waste management. The focus of its studies includes land disposal of LLW (Low-level radioactive wastes) and it has gradually extended to research on management and disposal techniques for high-level (HLW) and TRU wastes and studies on securing and managing the funds required for disposal of these wastes. The present document is the yearly progress report of 2006 and the main activities and research results are included on spent fuel disposal techniques including radon diffusion and emanation problem, performance studies on underground facilities for radioactive waste disposal and its management, technical assessment for geological environment, remote control techniques, artificial barrier systems proposed and its monitoring systems, and TRU disposals. (S. Ohno)

Education and training in radioactive waste topics

International Nuclear Information System (INIS)

Falcon Cabrera, S.; Marco Arboli, M.

2003-01-01

Tecnologically developed countries rely on nuclear fission as an important source for the production of electrical power. some of th epower plants in current generation will continue to be operated for at least 20 years, and there exist plans for the future. As a consequence, these countries take part in R and D projects oriented towards progress to be made in the management of radioactive waste, and particularly in the industrial implementation of technical solutions for the management of long-lived waste. The great experience of CIEMAT in this field has made it possible that different standard and re-creation training actions were carried out in the last years. At national level, these actions have covered both the question of reducing the impact of radioactive waste and the problem of its management. In the first subject, actions have been focused to the following aspects: Characterization of radioactive waste, where the present-day knowledge on efficient technologies of physicochemical and radiological characterization of low and medium activity waste are provided. Partitioning and Transmutation, where the development of new technologies like the Accelerator Driven Systems (ADS) and the climination by transmutation, that reduce the hazards associated with waste of high activity are shown. Decommissioning of nuclear ficilities, development of techniques which will allow to mange these wastes with minimum radioactive waste generation, using new techniques for the decontamination and cutting of contaminated materials that have to be immobilized. On the second subject Management of Radioactive Wastes, a doctorate course organised in collaboration with the Polytechnic University of Madrid, and sponsored by ENRESA. At the international level, CIEMAT usually takes part in training activities of the technical assistance programmes of the International Atomic Energy agency (IAEA). In particular, actions related to Safety assessment methodologies for near surface

Regulation of Federal radioactive waste activities. Summary of report to Congress on extending the Nuclear Regulatory Commission's licensing or regulatory authority to Federal radioactive waste storage and disposal activities

International Nuclear Information System (INIS)

Smith, R.D.

1979-09-01

The NRC Authorization Bill for FY 1979 directed NRC to conduct a study of extending the Commission's licensing or regulatory authority to include categories of existing and future Federal radioactive waste storage and disposal activities not presently subject to such authority. The report includes a complete listing and inventory of all radioactive waste storage and disposal activities now being conducted or planned by Federal agencies. The NRC study has attempted to present a general comparison of the relative hazards associated with defense-generated and commercial wastes. Options for extending Commission authority were developed and analyzed. The implications of NEPA were analyzed in the context of these options. The national security implications of extending NRC's regulatory authority over DOE programs are examined and evaluated. Costs and benefits are identified and assessed. The Commission's recommendations, based on the study, are to extend licensing authority over new DOE disposal activities involving transuranic wastes and non-defense low-level waste and to initiate a pilot program to test the feasibility of NRC playing a consultative role in the evaluation of existing DOE activities

Radioactive waste interim storage in Germany

International Nuclear Information System (INIS)

2015-12-01

The short summary on the radioactive waste interim storage in Germany covers the following issues: importance of interim storage in the frame of radioactive waste management, responsibilities and regulations, waste forms, storage containers, transport of vitrified high-level radioactive wastes from the reprocessing plants, central interim storage facilities (Gorleben, Ahaus, Nord/Lubmin), local interim storage facilities at nuclear power plant sites, federal state collecting facilities, safety, radiation exposure in Germany.

Radioactive waste management: a summary of state laws and administration. National Low-Level Radioactive Waste Mangement Program

International Nuclear Information System (INIS)

1983-05-01

This is the first quarterly update of Radioactive Waste Management: A Summary of State Laws and Administration. Because states have been very active on waste management issues, the whole report is being reissued in this update. It covers the administration, the legislature and the laws in the 50 states related to radioactive waste. The report for each state is divided into four sections: Cover Page; Administrative; Legislative; and Applicable Legislation. The cover page indicates whether or not it is an Agreement State, the low-level waste compacts in which the state is listed as an eligible state, and the high-level waste repository site screening regions in which the state or a portion of it is located. The administrative section provides information on the governor, lead agencies, other involved administrative agencies, relevant commissions, boards and councils and various contacts. The Legislative section provides general information on the legislature and lists legislative leaders, the relevant committees and their chairs and a legislative contact. In the section covering Applicable Legislation, laws related to radiation protection, low-level waste and high-level waste have been summarized. Hazardous waste siting laws are included for states that do not have a siting law covering radioactive waste. The section also contains summaries of relevant bills introduced in 1982 and 1983 legislative sessions and their disposition. In general, the information in this report is accurate as of 15 April 1983

Radioactive waste management

International Nuclear Information System (INIS)

Slansky, C.M.

1975-01-01

High-level radioactive waste is produced at Idaho Chemical Processing Plant (ICPP) during the recovery of spent highly enriched nuclear fuels. Liquid waste is stored safely in doubly contained tanks made of steel. The liquid waste is calcined to a solid and stored safely in a retrievable form in doubly contained underground bins. The calcine can be treated further or left untreated in anticipation of ultimate storage. Fluidized bed calcination has been applied to many kinds of high-level waste. The environmental impact of high-level waste management at the ICcP has been negligible and should continue to be negligible. 13 refs

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

Designing shafts for handling high-level radioactive wastes in mined geologic repositories

International Nuclear Information System (INIS)

Hambley, D.F.; Morris, J.R.

1988-01-01

Waste package conceptual designs developed in the United States by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management are the basis for specifying the dimensions and weights of the waste package and transfer cask combinations to be hoisted in the waste handling shafts in mined geologic repositories for high-level radioactive waste. The hoist, conveyance, counterweight, and hoist ropes are then sized. Also taken into consideration are overwind and underwind arrestors and safety features required by the U.S. Nuclear Regulatory Commission. Other design features such as braking systems, chairing system design, and hoisting speed are considered in specifying waste hoisting system parameters for example repository sites

Radioactive waste management policy for nuclear power

International Nuclear Information System (INIS)

Andrei, V.; Glodeanu, F.; Simionov, V.

1998-01-01

Nuclear power is part of energy future as a clean and environmental friendly source of energy. For the case of nuclear power, two specific aspects come more often in front of public attention: how much does it cost and what happens with radioactive waste. The competitiveness of nuclear power vs other sources of energy is already proved in many developed and developing countries. As concerns the radioactive wastes treatment and disposal, industrial technologies are available. Even final solutions for disposal of high level radioactive waste, including spent fuel, are now fully developed and ready for large scale implementation. Policies and waste management strategies are established by all countries having nuclear programs. Once, the first nuclear power reactor was commissioned in Romania, and based on the national legal provisions, our company prepared the first issue of a general strategy for radioactive waste management. The general objective of the strategy is to dispose the waste according to adequate safety standards protecting the man and the environment, without undue burden on future generations. Two target objectives were established for long term: an interim spent fuel dry storage facility and a low and intermediate level waste repository. A solution for spent fuel disposal will be implemented in the next decade, based on international experience. Principles for radioactive waste management, recommended by IAEA are closely followed in the activities of our company. The continuity of responsibilities is considered to be very important. The radioactive waste management cost will be supported by the company. A tax on unit price of electricity will be applied. The implementation of radioactive waste management strategy includes as a major component the public information. A special attention will be paid by the company to an information program addressed to different categories of public in order to have a better acceptance of our nuclear power projects

Uncertainties in the geological disposal for high-level radioactive waste

International Nuclear Information System (INIS)

Liu Xiaodong; Wang Changxuan

2008-01-01

Geological disposal, referring to the disposal of high-level solid radioactive waste in a facility located underground in a stable geological formation, was considered the most favourable methods to provide long term isolation of the radionuclides in the waste from the biosphere, and was adopted by IAEA and the developed nations with nuclear facilities. Over 50 years studies have been proved the technical feasibility of geological disposal for radioactive waste. However, there are many subjective and objective uncertainties on development, operation and closure of a geological disposal facility. For providing flexibility in responding to new technical information, advances in waste management and materials technologies, and in enabling social, economic and political aspects to be addressed, it is necessary to evaluate the uncertainties for all the R and D steps of a geological disposal program. (authors)

High-level radioactive waste isolation by incorporation in silicate rock

International Nuclear Information System (INIS)

Schwartz, L.L.; Cohen, J.J.; Lewis, A.E.; Braun, R.L.

1978-01-01

A number of technical possibilities for isolating high-level radioactive materials have been theoretically investigated at various times and places. Isolating such wastes deep underground to ensure long term removal from the biosphere is one such possibility. The present concept involves as a first step creating the necessary void space at considerable depth, say 2 to 5 km, in a very-low-permeability silicate medium such as shale. Waste in dry, calcined or vitrified form is then lowered into the void space, and the access hole or shaft sealed. Energy released by the radioactive decay raises the temperature to a point where the surrounding rock begins to melt. The waste is then dissolved in it. The extent of this melt region grows until the heat generated is balanced by conduction away from the molten zone. Resolidification then begins, and ends when the radioactive decay has progressed to the point that the temperature falls below the melting point of the rock-waste solution. Calculations are presented showing the growth and resolidification process. A nuclear explosion is one way of creating the void space. (author)

Safety of geologic disposal of high level radioactive waste

International Nuclear Information System (INIS)

Zaitsu, Tomohisa; Ishiguro, Katsuhiko; Masuda, Sumio

1992-01-01

This article introduces current concepts of geologic disposal of high level radioactive waste and its safety. High level radioactive waste is physically stabilized by solidifying it in a glass form. Characteristics of deep geologic layer are presented from the viewpoint of geologic disposal. Reconstruction of multi-barrier system receives much attention to secure the safety of geologic disposal. It is important to research performance assessment of multi-barrier system for preventing dissolution or transfer of radionuclides into the ground water. Physical and chemical modeling for the performance assessment is outlined in the following terms: (1) chemical property of deep ground water, (2) geochemical modeling of artificial barrier spatial water, (3) hydrology of deep ground water, (4) hydrology of the inside of artificial barrier, and (5) modeling of radionuclide transfer from artificial barrier. (N.K.)

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.).

Office of Civilian Radioactive Waste Management: Support for university research and education

International Nuclear Information System (INIS)

Brownstein, A.B.

1990-01-01

The U.S. Department of Energy's (DOE's) Office of Civilian Radioactive Waste Management (OCRWM) currently sponsors two programs that provide funding to universities and graduate students. The OCRWM graduate fellowship program and the OCRWM research program for historically black colleges and universities (HBCU) are designed to enhance the involvement of universities in the nation's high-level radioactive waste program. The specific goals of these programs are to (a) attract talented young scientists and engineers into OCRWM and OCRWM support contractor high-level radioactive waste management programs, (b) improve the quality of graduate education in disciplines directly related to high-level radioactive waste management, and (c) encourage university faculty to become involved in OCRWM mission-related activities

Radioactive waste management in Belgium

International Nuclear Information System (INIS)

Dejonghe, P.

1977-01-01

In 1975 the research association BelgoWaste was founded in order to prepare a technical and administrative plan for radioactive waste management in Belgium and to take the preliminary steps for establishing an organization which would be responsible for this activity. The association made a survey of all forecasts concerning radioactive waste production by power reactors and the fuel cycle industry based on various schemes of development of the nuclear industry. From the technical point of view, the reference plan for waste management envisages: purification at the production site of large volumes of low-level effluents; construction of a central facility for the treatment and intermediate storage of process concentrates (slurries, resins, etc.) and medium-level waste, centralization assuming that adequate arrangements are made for transporting waste before final treatment; maximum recovery of plutonium from waste and treatment of residual material by incineration at very high temperatures; treatment at the production site of high-level effluents from irradiated fuel reprocessing; construction of an underground long-term storage site for high-level treated waste and plutonium fuel fabrication waste (deep clay formations are at present preferred); and disposal of low-level treated waste into the Atlantic Ocean. It is intended to entrust the entire responsibility for treatment, disposal and storage of treated waste to a single body with participation by the State, the Nuclear Energy Research Centre (CEN/SCK), the electricity companies and Belgonucleaire. The partners intend to set up their facilities and services in the area of Mol. (author)

Management of radioactive wastes in China

International Nuclear Information System (INIS)

Pan Ziqiang

1994-01-01

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

Will vitrified high active reactor waste be deposited on the seabed

International Nuclear Information System (INIS)

Koksvik, R.M.

1978-01-01

The NRPB in the UK has carried out a preliminary study on the consequences of the disposal of high active waste on the ocean bed at great depths. This is reported in 'Assessment of the radiological protection aspects of disposal of high level waste on the ocean floor', by P.D. Grimswood and G.A.M. Webb (NRPB-R 48). This report is here briefly summarised and commented on. It deals with the radiological consequences to man of the erosion and corrosion of glassified (vitrified) radioactive waste, in the deep (>4000m) ocean, radionuclide migration and path ways to man. The conclusion is that considerations of radiological protection do not preclude the disposal of specially treated radioactive waste on the ocean bed. (JIW)

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

ANDRA - National Radioactive Waste Management Agency. 2014 Activity report - Responsibility in action. Financial report 2014

International Nuclear Information System (INIS)

2015-01-01

Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity and financial report of the Andra for the year 2014

ANDRA - National Radioactive Waste Management Agency. Activity report and sustainable development 2013. Financial report 2013

International Nuclear Information System (INIS)

2014-01-01

Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity and Sustainable Development Report, with the financial report, of the Andra for the year 2013

Radioactive Demonstration Of Mineralized Waste Forms Made From Hanford Low Activity Waste (Tank Farm Blend) By Fluidized Bed Steam Reformation (FBSR)

International Nuclear Information System (INIS)

Jantzen, C. M.; Crawford, C. L.; Bannochie, C. J.; Burket, P. R.; Cozzi, A. D.; Daniel, W. E.; Hall, H. K.; Miller, D. H.; Missimer, D. M.; Nash, C. A.; Williams, M. F.

2013-01-01

The U.S. Department of Energy's Office of River Protection (ORP) is responsible for the retrieval, treatment, immobilization, and disposal of Hanford's tank waste. A key aspect of the River Protection Project (RPP) cleanup mission is to construct and operate the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The WTP will separate the tank waste into high-level and low-activity waste (LAW) fractions, both of which will subsequently be vitrified. The projected throughput capacity of the WTP LAW Vitrification Facility is insufficient to complete the RPP mission in the time frame required by the Hanford Federal Facility Agreement and Consent Order, also known as the Tri-Party Agreement (TPA), i.e. December 31, 2047. Supplemental Treatment is likely to be required both to meet the TPA treatment requirements as well as to more cost effectively complete the tank waste treatment mission. The Supplemental Treatment chosen will immobilize that portion of the retrieved LAW that is not sent to the WTP's LAW Vitrification facility into a solidified waste form. The solidified waste will then be disposed on the Hanford site in the Integrated Disposal Facility (IDF). Fluidized Bed Steam Reforming (FBSR) offers a moderate temperature (700-750°C) continuous method by which LAW can be processed irrespective of whether the waste contain organics, nitrates, sulfates/sulfides, chlorides, fluorides, volatile radionuclides or other aqueous components. The FBSR technology can process these wastes into a crystalline ceramic (mineral) waste form. The mineral waste form that is produced by co-processing waste with kaolin clay in an FBSR process has been shown to be comparable to LAW glass, i.e. leaches Tc-99, Re and Na at 6 (the Hanford IDF criteria for Na) in the first few hours. The granular and monolithic waste forms also pass the EPA Toxicity Characteristic Leaching Procedure (TCLP) for all Resource Conservation and Recovery Act (RCRA) components at the Universal Treatment

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.)

Preliminary site characterization at Beishan northwest China-A potential site for China's high-level radioactive waste repository

International Nuclear Information System (INIS)

Wang Ju; Su Rui; Xue Weiming; Zheng Hualing

2004-01-01

Chinese nuclear power plants,radioactive waste and radioactive waste disposal are introduced. Beishan region (Gansu province,Northwest China)for high-level radioactive waste repository and preliminary site characterization are also introduced. (Zhang chao)

The radioactive waste management at IAEA laboratories

International Nuclear Information System (INIS)

Deron, S.; Ouvrard, R.; Hartmann, R.; Klose, H.

1992-10-01

The report gives a brief description of the nature of the radioactive wastes generated at the IAEA Laboratories in Seibersdorf, their origin and composition, their management and monitoring. The management of the radioactive waste produced at IAEA Laboratories in Seibersdorf is governed by the Technical Agreements of 1985 between the IAEA and the Austrian Health Ministry. In the period of 1982 to 1991 waste containers of low activity and radiotoxicity generated at laboratories other than the Safeguards Analytical Laboratory (SAL) were transferred to the FZS waste treatment and storage plant: The total activity contained in these drums amounted to < 65 MBq alpha activity; < 1030 MBq beta activity; < 2900 MBq gamma activity. The radioactive waste generated at SAL and transferred to the FZs during the same period included. Uranium contaminated solid burnable waste in 200 1 drums, uranium contaminated solid unburnable waste in 200 1 drums, uranium contaminated liquid unburnable waste in 30 1 bottles, plutonium contaminated solid unburnable waste in 200 1 drums. In the same period SAL received a total of 146 Kg uranium and 812 g plutonium and exported out of Austria, unused residues of samples. The balance, i.e.: uranium 39 kg, plutonium 133 g constitutes the increase of the inventory of reference materials, and unused residues awaiting export, accumulated at SAL and SIL fissile store as a result of SAL operation during this 10 year period. The IAEA reexports all unused residues of samples of radioactive and fissile materials analyzed at his laboratories, so that the amount of radioactive materials ending in the wastes treated and stored at FZS is kept to a minimum. 5 refs, 7 figs, 3 tabs

II Meeting of R and D in radioactive waste management, Madrid 14-16 June, 1995

International Nuclear Information System (INIS)

1995-01-01

The second meeting of R and D in radioactive waste management was organized by ENRESA on 14-16 June 1995 The main objective was to disseminate the most relevant works within the 2nd R and d plan, and to establish and adequate form involved for discussion R and D radioactive waste management. The meeting was articulated in 50 sessions: I.- Low and medium radioactive wastes. II.- High level radioactive wastes: activities of ENRESA III.- High level radioactive wastes: near field. IV.- Biosphere, radiological protection, behaviour evaluation. V.- Dismantling and decommissioning nuclear facilities VI.- Geosphere

Andra - Everything you ever wanted to know about radioactive waste management

International Nuclear Information System (INIS)

2014-08-01

Andra is a publicly owned industrial and commercial body, set up by the French act of 30 December 1991. Its role was expanded by the 2006 Planning Act on the long-term management of radioactive materials and waste. Andra is independent of the producers of radioactive waste, and is under the supervision of the ministries responsible for energy, research and the environment. Andra is responsible for identifying, implementing and guaranteeing safe management solutions for all French radioactive waste, in order to protect present and future generations from the risks inherent in such substances. Andra's role involves a number of activities: running the two existing above-ground disposal facilities in the Aube, the first one for low- and intermediate- level, short-lived waste (LILW-SL) and the other one for very-low-level waste (VLLW), the Cires facility; monitoring the Manche disposal facility, the CSM, France's first above-ground disposal facility for low- and intermediate-level waste, which is now closed; studying and designing disposal facilities for waste as yet without a special facility, that is: Low-level, long-lived waste (LLW-LL), High-level and intermediate-level long-lived waste (HLW, ILW-LL) - the Cigeo project; taking in radioactive waste from hospitals, research laboratories, universities and radioactive objects owned by private individuals (old luminous clocks and watches, health care equipment containing radium, natural laboratory salts, certain minerals, etc.); at the request of the owner or the authorities, cleaning up sites polluted by radioactivity; surveying and listing French radioactive waste and issuing the National Inventory of Radioactive Materials and Waste every three years; informing all members of the public by means of documents, exhibitions, visits to its facilities, etc.; preserving the memory of its centers; promoting and disseminating its know-how outside France. Contents: 1 - Andra, its role, its activities, its funding; 2

The methods of conversion of radioactive waste: a look at the past

International Nuclear Information System (INIS)

Rezchikov, D.

2000-01-01

In 1948, the Government of the USSR made provisions to establish an industrial complex to produce Pu-239 in the Chelyabinsk region. PA 'MAYAK' was part of this complex. It is now addressing radioactive waste disposition in peacetime. Making Pu-239 in metal form led to the formation of large quantities of liquid radioactive waste. Since it was impossible to clean the water at that time, radioactive waste was put in the Techa River until 1951. The liquid waste contained a mixture of radioactive Sr, Cs, Nb, Ru and other elements. Sr-90 and Cs-137 accounted for about a quarte of the radioactivity. Many people lived near the Techa and received large doses of radiation. About 2.7 million Curies was put into the river before this practice stopped arid waste was then put into Lake Karachay. High-activity waste was placed in concrete and steel for protection. The volume was cooled with water. When cooling was stopped, the dry mixture heated to 300-350 degrees and exploded. According to official information, the reason for the incident was because the system's control temperature and level of the waste were exceeded. Repair was impossible because radiation fields were high. Contents of the volume were released in the plume and spread into the atmosphere. Around 90 percent of the radioactivity fell near the place of the burst. The rest of the 2 million curies was spread by wind and appeared as the West Ural Trace. It was very important to utilize solid waste (SW). Around 200 special places were made for storage of SW. High-activity SW was kept in reinforced-concrete containers. Middle-activity waste was put in a trench. The total activity of SW is approximately 2 million Curies. (authors)

Low-level radioactive biomedical wastes

International Nuclear Information System (INIS)

Casarett, G.W.

A summary of the management and hazards of low-level radioactive biomedical wastes is presented. The volume, disposal methods, current problems, regulatory agencies, and possible solutions to disposal problems are discussed. The benefits derived from using radioactivity in medicine are briefly described. Potential health risks are discussed. The radioactivity in most of the radioactive biomedical waste is a small fraction of that contained naturally in the human body or in the natural environment. Benefit-risk-cost considerations are presented. The cost of managing these wastes is getting so high that a new perspective for comparison of radioactivity (facts, risks, costs, benefits and trade-offs) and alternate approaches to minimize the risk and cost and maximize the benefits is suggested

The IAEA's activities in the field of radioactive waste management

International Nuclear Information System (INIS)

Semenov, B.A.

1984-01-01

The IAEA has been concerned with radioactive waste management since its inception. Its programme in this area was expanded in the mid 1970s as questions related to the management and disposal of radioactive wastes came into focus in conjunction with the further industrial development of nuclear power. The objectives of the Agency's waste management programme are to assist its Member States in the safe and effective management of wastes by organizing the exchange and dissemination of information, providing guidance and technical assistance and supporting research. The current programme addresses all aspects of the industrial use of nuclear power under the aspects (a) technology of handling and treatment of wastes, (b) underground disposal of wastes, (c) environmental aspects of nuclear energy, including sea disposal of radioactive wastes. Systematic reviews have been made and publications issued concerning the technology of handling, treating, conditioning, and storing various categories of wastes, including liquid and gaseous wastes, wastes from nuclear power plants, spent fuel reprocessing and mining and milling of uranium ores, as well as wastes from decommissioning of nuclear facilities. As waste disposal is the current issue of highest interest, an Agency programme was set up in 1977 to develop a set of guidelines on the safe underground disposal of low-, intermediate- and high-level wastes in shallow ground, rock cavities or deep geological repositories. This programme will continue until 1990. Eleven Safety Series and Technical Documents and Reports have been published under this programme so far, which also addresses safety and other criteria for waste disposal. The environmental part of the waste management programme is concerned with the assessment of radiological and non-radiological consequences of discharges from nuclear facilities, including de minimis concepts in waste disposal and environmental models and data for radionuclide releases

Grading of Requirements for Radioactive Waste Activities in Nuclear Research Reactors: Radioisotope Production Facilities

International Nuclear Information System (INIS)

Tawfik, Y.E.

2017-01-01

A graded approach is applicable in all stages of the life time of a research reactor. During the life time of a research reactor, any grading performed should not, in any manner, affect safety functions and operational limits and conditions are preserved, so that there are no undue radiological hazards to workers, public or environment. The grading of activities should be based on safety analyses, and regulatory requirements. Other elements to be considered in grading are the complexity and the maturity of the technology, operating experience associated with the activities and the stage in the life time of the facility. In order to ensure that proper and a de quate provision is made for the safety implications associated with the management and disposal of radioactive waste, the waste is characterized and classified. The general scheme for classifying radioactive waste as presented in the current study is based on considerations of long term safety, and thus, by implication, disposal of the waste. This classification provides a starting point for the grading of activities associated with the packaging and disposal of radioactive waste

Vitrification of Three Low-Activity Radioactive Waste Streams from Hanford

International Nuclear Information System (INIS)

Ferrara, D.M.; Crawford, C.L.; Ha, B.C.; Bibler, N.E.

1998-09-01

As part of a demonstration for British Nuclear Fuels Limited, Incorporated (BNFL), the Immobilization Technology Section (ITS) of the Savannah River Technology Center (SRTC) has produced and characterized three low-activity waste (LAW) glasses from Hanford radioactive waste samples. The three LAW glasses were produced from radioactive supernate samples that had been treated by the Waste Processing Technology Section (WPTS) at SRTC to remove most of the radionuclides. These three glasses were produced by mixing the waste streams with between four and nine glass-forming chemicals in platinum/gold crucibles and heating the mixture to between 1120 and 1150 degrees C. Compositions of the resulting glass waste forms were close to the target compositions. Low concentrations of radionuclides in the LAW feed streams and, therefore, in the glass waste forms supported WPTS conclusions that pretreatment had been successful. No crystals were detected in the LAW glasses. In addition, all glass waste forms passed the leach tests that were performed. These included a 20 degrees C Product Consistency Test (PCT) and a modified version of the United States Environmental Protection Agency Toxicity Characteristic Leaching Procedure (TCLP)

High level radioactive waste management facility design criteria

International Nuclear Information System (INIS)

Sheikh, N.A.; Salaymeh, S.R.

1993-01-01

This paper discusses the engineering systems for the structural design of the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS). At the DWPF, high level radioactive liquids will be mixed with glass particles and heated in a melter. This molten glass will then be poured into stainless steel canisters where it will harden. This process will transform the high level waste into a more stable, manageable substance. This paper discuss the structural design requirements for this unique one of a kind facility. A special emphasis will be concentrated on the design criteria pertaining to earthquake, wind and tornado, and flooding

Separation processes for high-level radioactive waste treatment

International Nuclear Information System (INIS)

Sutherland, D.G.

1992-11-01

During World War II, production of nuclear materials in the United States for national defense, high-level waste (HLW) was generated as a byproduct. Since that time, further quantities of HLW radionuclides have been generated by continued nuclear materials production, research, and the commercial nuclear power program. In this paper HLW is defined as the highly radioactive material resulting from the processing of spent nuclear fuel. The HLW is the liquid waste generated during the recovery of uranium and plutonium in a fuel processing plant that generally contains more than 99% of the nonvolatile fission products produced during reactor operation. Since this paper deals with waste separation processes, spent reactor fuel elements that have not been dissolved and further processed are excluded

The treatment of radioactive waste in Institute of Nuclear Physics of Uzbekistan

International Nuclear Information System (INIS)

Radyuk, R.I.

2001-01-01

Full text: The main purpose of radioactive waste treatment is security of humanity and environment for future. The formation of radioactive waste in Institute of Nuclear Physics connects with scientific and research works on reactor and cyclotron. There are works in the field of radiochemistry, activation analysis, research of material. It is connected with some different materials used in practical work: mountain rock, food-stuffs, biological materials and other. The Institute of Nuclear Physics has enterprise, making radioactive isotopes. In consequence of this work radioactive wastes form. Average annual volume of liquid radioactive waste is 2000 m 3 in year. During normal work of nuclear reactor and enterprise of radioactive isotope small part of radionuclides with gaseous waste gets in environment. The content of inert gas does not exceed 2% of permissible level . Value of radionuclides fall out in area from 0.5 Km to 10 Km does not differ global fall out and changes from 1.1.10 6 Bq/km 2 to 1.6.10 7 Bq/km 2 month (permissible doze - 5.6.10 8 Bq/km 2 .month). The solid radioactive waste of medium and low activity are burying on Republic point of radioactive waste storage. Annual volume of solid radioactive waste is 60 m 3 in year and total radioactivity is 10 11 Bk. The solid radioactive waste of high activity are going to of Chelyabinsk. The liquid radioactive waste belong to second and third group of radioactive waste (classification of IAEA). The decontamination of liquid radioactive waste are made on the station of liquid radioactive waste treatment by method of sedimentation and distillation. The productivity of this plant is 15m 3 in day. Before treatment liquid radioactive waste is analyzed to determine chemical and radiochemical composition. It is solution with content of salt from 0.8 g/l to 15 g/l, salt Ca 2+ and Mg 2+ - 20 mg-eqv/l, oxygen - 100 mg O 2 /l , activity from 10 2 Bq/l to 10 4 Bq/l. The radionuclides composition of liquid radioactive

Argentine project for the final disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Palacios, E.; Ciallella, N.R.; Petraitis, E.J.

1989-01-01

From 1980 Argentina is carrying out a research program on the final disposal of high level radioactive wastes. The quantity of wastes produced will be significant in next century. However, it was decided to start with the studies well in advance in order to demonstrate that the high level wastes could be disposed in a safety way. The option of the direct disposal of irradiated fuel elements was discarded, not only by the energetic value of the plutonium, but also for ecological reasons. In fact, the presence of a total inventory of actinides in the non-processed fuel would imply a more important radiological impact than that caused if the plutonium is recycled to produce energy. The decision to solve the technological aspects connected with the elimination of high-level radioactive wastes well in advance, was made to avoid transfering the problem to future generations. This decision is based not only on technical evaluations but also on ethic premises. (Author)

Radioactive and mixed waste management plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

1995-01-01

This Radioactive and Mixed Waste Management Plan for the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory is written to meet the requirements for an annual report of radioactive and mixed waste management activities outlined in DOE Order 5820.2A. Radioactive and mixed waste management activities during FY 1994 listed here include principal regulatory and environmental issues and the degree to which planned activities were accomplished

Cosmic disposal of radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Inoue, Y; Morisawa, S [Kyoto Univ. (Japan). Faculty of Engineering

1975-03-01

The technical and economical possibility and safety of the disposal of highly radioactive waste into cosmos are reviewed. The disposal of highly radioactive waste is serious problem to be solved in the near future, because it is produced in large amounts by the reprocessing of spent fuel. The promising methods proposed are (i) underground disposal, (ii) ocean disposal, (iii) cosmic disposal and (iv) extinguishing disposal. The final disposal method is not yet decided internationally. The radioactive waste contains very long life nuclides, for example transuranic elements and actinide elements. The author thinks the most perfect and safe disposal method for these very long life nuclides is the disposal into cosmos. The space vehicle carrying radioactive waste will be launched safely into outer space with recent space technology. The selection of orbit for vehicles (earth satellite or orbit around planets) or escape from solar system, selection of launching rocket type pretreatment of waste, launching weight, and the cost of cosmic disposal were investigated roughly and quantitatively. Safety problem of cosmic disposal should be examined from the reliable safety study data in the future.

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.

Radioactive wastes and their disposal

International Nuclear Information System (INIS)

Neumann, L.

1984-01-01

The classification of radioactive wastes is given and the achievements evaluated in the disposal of radioactive wastes from nuclear power plants. An experimental pilot unit was installed at the Jaslovske Bohunice nuclear power plant for the bituminization of liquid radioactive wastes. UJV has developed a mobile automated high-output unit for cementation. In 1985 the unit will be tested at the Jaslovske Bohunice and the Dukovany nuclear power plants. A prototype press for processing solid wastes was manufactured which is in operation at the Jaslovske Bohunice plant. A solidification process for atypical wastes from long-term storage of spent fuel elements has been developed to be used for the period of nuclear power plant decommissioning. (E.S.)

The disposal of high level radioactive wastes. Proposed solutions and uses in Brazil

International Nuclear Information System (INIS)

Toledo, J.F.A.

1992-06-01

The characteristics of high level radioactive waste produced in nuclear plants similar to that used in Brazil is presented. Subsequently it is described the international experience, and the way to apply such knowledge to the Brazilian situation, defining the magnitude of the problem, applying a methodology to select sites, and choosing areas for the location of a repository. Once such areas are defined, it is presented the behaviour of rock mass, similar to those found in the brazilian territory, based on the requirements for a high radioactive waste repository site. Finally, two Projects are presented for countries with lithologies similar to that of Brazil. The first one is choosing sites for a high radioactive waste repository program, and the second is an investigation of rock mass responses program. (author)

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)

MANAGEMENT OF RADIOACTIVE WASTES IN CHINA

Institute of Scientific and Technical Information of China (English)

潘自强

1994-01-01

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

Radioactive Bench-scale Steam Reformer Demonstration of a Monolithic Steam Reformed Mineralized Waste Form for Hanford Waste Treatment Plant Secondary Waste - 12306

Energy Technology Data Exchange (ETDEWEB)

Evans, Brent; Olson, Arlin; Mason, J. Bradley; Ryan, Kevin [THOR Treatment Technologies, LLC - 106 Newberry St. SW, Aiken, SC 29801 (United States); Jantzen, Carol; Crawford, Charles [Savannah River Nuclear Solutions (SRNL), LLC, Aiken, SC 29808 (United States)

2012-07-01

Hanford currently has 212,000 m{sup 3} (56 million gallons) of highly radioactive mixed waste stored in the Hanford tank farm. This waste will be processed to produce both high-level and low-level activity fractions, both of which are to be vitrified. Supplemental treatment options have been under evaluation for treating portions of the low-activity waste, as well as the liquid secondary waste from the low-activity waste vitrification process. One technology under consideration has been the THOR{sup R} fluidized bed steam reforming process offered by THOR Treatment Technologies, LLC (TTT). As a follow-on effort to TTT's 2008 pilot plant FBSR non-radioactive demonstration for treating low-activity waste and waste treatment plant secondary waste, TTT, in conjunction with Savannah River National Laboratory, has completed a bench scale evaluation of this same technology on a chemically adjusted radioactive surrogate of Hanford's waste treatment plant secondary waste stream. This test generated a granular product that was subsequently formed into monoliths, using a geo-polymer as the binding agent, that were subjected to compressibility testing, the Product Consistency Test and other leachability tests, and chemical composition analyses. This testing has demonstrated that the mineralized waste form, produced by co-processing waste with kaolin clay using the TTT process, is as durable as low-activity waste glass. Testing has shown the resulting monolith waste form is durable, leach resistant, and chemically stable, and has the added benefit of capturing and retaining the majority of Tc-99, I-129, and other target species at high levels. (authors)

Radioactive waste sea disposal practices and the need for international regulations

International Nuclear Information System (INIS)

Reyners, P.

1975-01-01

Radioactive waste is mainly disposed of as liquid releases in coastal waters or as solid wastes dumped in the high seas. The Geneva Convention on the high seas which lays down that Contracting States should not, by unilateral measures, pollute the seas by dumping radioactive wastes, and Article 37 of the Euratom Treaty on the Commission's control over radioactive waste disposal plans by Member States constitute the principal legal basis for such activities at international level. The competent international organisations, IAEA and the OECD Nuclear Energy Agency (NEA), have both made detailed studies on the scientific, technical and legal aspects of sea disposal of radioactive wastes. Following consideration of the possibilities of waste dumping in the Atlantic and the related hazard assessment, at its Member State's request, NEA in 1967 undertook an initial experimental packaged waste disposal operation in the high seas. This operation's technical success encouraged Member States to undertake further operations in subsequent years under NEA international control. At present, in view of the entry into force of the London Convention on prevention of marine pollution by dumping of wastes, it seems desirable that the international character of such operations be preserved and all countries concerned be encouraged to adopt an international code of practice for sea disposal of radioactive wastes [fr

Radioactive waste processing method and device

International Nuclear Information System (INIS)

Ozaki, Shigeru; Tateyama, Shinji.

1998-01-01

A powdery activated carbon is charged to radioactive liquid wastes to form a mixed slurry. The slurry is subjected to solid/liquid separation, and a high-molecular water absorbent is charged to the separated activated carbon sludge wastes to process them while stirring. The high-molecular water absorbent comprises a graft polymer of starch and acrylonitrile or a cross-linked polymer of sodium acrylate and a cross-linking agent. The high-molecular water absorbing agent is previously charged to a vessel for containing the wasted active carbon sludges. The device of the present invention comprises a filtration device for solid/liquid separation of the mixed slurry, a sludge-containing vessel, a device for charging the high-molecular water absorbent and a sludge stirring device. The device of charging the high-molecular water absorbent comprises a plurality of weighing devices for weighing the change of the weight of the charged products and a conveyor for transferring the sludge-containing vessels. With such a constitution, stable sludge can be obtained, and activated carbon sludge wastes can be burnt without crushing them. (T.M.)

Derivation of activity limits for the disposal of radioactive waste in near surface disposal facilities

International Nuclear Information System (INIS)

2003-12-01

criteria for disposal of radioactive wastes to near surface facilities. These criteria are qualitative in nature and, for example, they do not address limitations on radionuclide content of waste, waste packages or the facility as a whole. This publication is to present an approach for establishing radiological waste acceptance criteria using a safety assessment methodology and to illustrate its application in establishing limits on the total activity and the activity concentrations of radioactive waste to be disposed in near surface disposal facilities. The approach makes use of accepted methods and computational schemes currently used in assessing the safety of near surface disposal facilities both during the operational and post-closure periods. The scope of this publication covers the use of safety assessment methodology to calculate total and specific activities limits for radioactive waste in near surface disposal facilities. It is used to evaluate the potential operational and post-closure radiological impact of solid and solidified radioactive waste in near surface facilities. The radioactive waste types used to illustrate the approach range from waste containing radionuclides used for medical, industrial and research purposes to waste arising from nuclear fuel cycle activities. They also include waste arising from the decommissioning of nuclear facilities. The focus of the publication is on using of safety assessment methodology in derivation of quantitative radioactivity limits. This report deals with the role of activity limits in disposal system safety (Section 2), the relevant radiation protection criteria (Section 3), the approach to derive activity limits (Section 4), illustrations of the application of this approach (Section 5), and guidance on the use of the approach (Section 6)

Small-scale demonstration of high-level radioactive waste processing and solidification using actual SRP waste

International Nuclear Information System (INIS)

Okeson, J.K.; Galloway, R.M.; Wilhite, E.L.; Woolsey, G.B.; Ferguson, R.B.

1980-01-01

A small-scale demonstration of the high-level radioactive waste solidification process by vitrification in borosilicate glass is being conducted using 5-6 liter batches of actual waste. Equipment performance and processing characteristics of the various unit operations in the process are reported and, where appropriate, are compared to large-scale results obtained with synthetic waste

Vitrification of hazardous and radioactive wastes

International Nuclear Information System (INIS)

Bickford, D.F.; Schumacher, R.

1995-01-01

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

Treatment of radioactive wastes by incineration; Tratamiento de desechos radiactivos por incineracion

Energy Technology Data Exchange (ETDEWEB)

Priego C, E., E-mail: emmanuel.priego@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

2013-10-15

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

Processing method for radioactive liquid waste

International Nuclear Information System (INIS)

Yasumura, Keijiro

1991-01-01

Drainages, such as water after used for washing operators' clothes and water used for washing hands and for showers have such features that the radioactive concentration is extremely low and detergent ingredients and insoluble ingredients such as waste threads, hairs and dirts are contained. At present, waste threads are removed by a strainer. Then, after measuring the radioactivity and determining that the radioactivity is less than a predetermined concentration, they are released to circumstances. However, various organic ingredients such as detergents and dirts in the liquid wastes are released as they are and it is not preferred in respect of environmental protection. Then, in the present invention, activated carbon is filled in a container orderly so that the diameter of the particles of the activated carbon is increased in the upper layer and decreased in the lower layer, and radioactive liquid wastes are passed through the container. With such a constitution. Both of soluble substances and insoluble substances can be removed efficiently without causing cloggings. (T.M.)

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.)

Radioactive waste management perspectives in Malaysian Nuclear Agency

International Nuclear Information System (INIS)

Nurul Wahida Ahmad Khairuddin; Nik Marzukee Nik Ibrahim; Mat Bakar Mahusin; Mohamad Hakiman Mohamad Yusoff; Muhammad Zahid Azrmi

2009-01-01

Waste Technology Development Centre (WasTeC) has been mandated to carry out radioactive waste management activities since 1984. The main objective of WasTeC is to deal with radioactive waste in a manner that protects health and the environment now and in the future, without imposing undue burdens on the future generations. This centre provides services for waste generators within Nuclear Malaysia and also for external waste generators. Services provided include transportation of radioactive waste, decontamination, treatment and storage. This paper will discuss on procedure for applying for services, responsibility of waste generator, responsibility of waste operator, need to comply with waste acceptance criteria and regulations related to management of radioactive waste. (Author)

Storing solid radioactive wastes at the Savannah River Plant

International Nuclear Information System (INIS)

Horton, J.H.; Corey, J.C.

1976-06-01

The facilities and the operation of solid radioactive waste storage at the Savannah River Plant (SRP) are discussed in the report. The procedures used to segregate and the methods used to store radioactive waste materials are described, and the monitoring results obtained from studies of the movement of radionuclides from buried wastes at SRP are summarized. The solid radioactive waste storage site, centrally located on the 192,000-acre SRP reservation, was established in 1952 to 1953, before any radioactivity was generated onsite. The site is used for storage and burial of solid radioactive waste, for storage of contaminated equipment, and for miscellaneous other operations. The solid radioactive waste storage site is divided into sections for burying waste materials of specified types and radioactivity levels, such as transuranium (TRU) alpha waste, low-level waste (primarily beta-gamma), and high-level waste (primarily beta-gamma). Detailed records are kept of the burial location of each shipment of waste. With the attention currently given to monitoring and controlling migration, the solid wastes can remain safely in their present location for as long as is necessary for a national policy to be established for their eventual disposal. Migration of transuranium, activation product, and fission product nuclides from the buried wastes has been negligible. However, monitoring data indicate that tritium is migrating from the solid waste emplacements. Because of the low movement rate of ground water, the dose-to-man projection is less than 0.02 man-rem for the inventory of tritium in the burial trenches. Limits are placed on the amounts of beta-gamma waste that can be stored so that the site will require minimum surveillance and control. The major portion (approximately 98 percent) of the transuranium alpha radioactivity in the waste is stored in durable containers, which are amenable to recovery for processing and restorage should national policy so dictate

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

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.

High-level radioactive waste glass and storage canister design

International Nuclear Information System (INIS)

Slate, S.C.; Ross, W.A.

1979-01-01

Management of high-level radioactive wastes is a primary concern in nuclear operations today. The main objective in managing these wastes is to convert them into a solid, durable form which is then isolated from man. A description is given of the design and evaluation of this waste form. The waste form has two main components: the solidified waste and the storage canister. The solid waste form discussed in this study is glass. Waste glasses have been designed to be inert to water attack, physically rugged, low in volatility, and stable over time. Two glass-making processes are under development at PNL. The storage canister is being designed to provide high-integrity containment for solidified wastes from processing to terminal storage. An outline is given of the steps in canister design: material selection, stress and thermal analyses, quality verification, and postfill processing. Examples are given of results obtained from actual nonradioactive demonstration tests. 14 refs

Managing the nation's high-level radioactive waste: key issues and recommendations

International Nuclear Information System (INIS)

1981-07-01

To date, no unified national plan has been adopted to develop and implement a comprehensive system of management and disposal of high-level radioactive waste in the United States. Growing public concern about this problem has resulted in a number of recent efforts to develop a national high-level waste management policy. The 96th Congress strove to resolve the central issues, but ultimately failed to pass legislation, partly because of disagreements about the appropriate role of states in the siting of repositories for military waste. Outside government, a number of organizations convened representatives of diverse groups concerned with national high-level radioactive waste management to seek agreement on the major elements of national policy. One such organization was RESOLVE, Center for Environmental Conflict Resolution, which in May 1981 was merged into The Conservation Foundation. RESOLVE convened Forum II, a series of discussions among representatives of environmental, industrial, governmental, and citizen interest groups, in 1981 specifically to address the issues blocking Congressional agreement on high-level waste policy. This report contains the recommendations which resulted from these deliberations. Reprocessing, interim storage, respository development, and licensing requirements are addressed. Federal, state, and public participation in decision making are also discussed

Institutional arrangements for radioactive waste management

International Nuclear Information System (INIS)

Willrich, M.

1976-01-01

The existing organizational structure and regulations for management of high-level and TRU wastes are likely to become ineffective if left unchanged. Recommendations for institutional reforms include the establishment of a National Radioactive Waste Authority in the U.S. and of an International Radioactive Waste Commission under IAEA

High-Level Radioactive Waste: Safe Storage and Ultimate Disposal.

Science.gov (United States)

Dukert, Joseph M.

Described are problems and techniques for safe disposal of radioactive waste. Degrees of radioactivity, temporary storage, and long-term permanent storage are discussed. Included are diagrams of estimated waste volumes to the year 2000 and of an artist's conception of a permanent underground disposal facility. (SL)

Chemical decontamination method for radioactive metal waste

International Nuclear Information System (INIS)

Onuma, Tsutomu; Akimoto, Hidetoshi

1991-01-01

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

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.)

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)

Low-level radioactive waste management at the Nevada Test Site - Current status

International Nuclear Information System (INIS)

Becker, B.D.; Crowe, B.M.; Gertz, C.P.; Clayton, W.A.

1999-01-01

The performance objectives of the Department of Energy's Low-Level Radioactive Waste (LLW) disposal facilities located at the Nevada Test Site transcend those of any other radioactive waste disposal site in the US. Situated at the southern end of the Great Basin, 800 feet above the water table, the Area 5 Radioactive Waste Management Site (RWMS) has utilized a combination of engineered shallow land disposal cells and deep augured shafts to dispose a variety of waste streams. These include high volume low-activity wastes, classified materials, and high-specific-activity special case wastes. Twenty miles north of Area 5 is the Area 3 RWMS. Here bulk LLW disposal takes place in subsidence craters formed from underground testing of nuclear weapons. Earliest records indicate that documented LLW disposal activities have occurred at the Area 5 and Area 3 RWMS's since 1961 and 1968, respectively. However, these activities have only been managed under a formal program since 1978. This paper describes the technical attributes of the facilities, present and future capacities and capabilities, and provides a description of the process from waste approval to final disposition. The paper also summarizes the current status of the waste disposal operations

Radioactive liquid waste processing system

International Nuclear Information System (INIS)

Noda, Tetsuya; Kuramitsu, Kiminori; Ishii, Tomoharu.

1997-01-01

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

Proposed goals for radioactive waste management

International Nuclear Information System (INIS)

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

1977-04-01

Goals are proposed for the national radioactive waste management program to establish a policy basis for the guidance and coordination of 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 analyses of selected primary literature and interviews of personnel concerned with waste management. Public concerns are identified, their relevance assessed, and a conceptual framework is developed that facilitates understanding of the dimensions and demands of the radioactive waste management problem. The nature and scope of the study are described along with the approach used to arrive at a set of goals appropriately focused on waste management

Studies on site characterization methodologies for high level radioactive waste disposal

International Nuclear Information System (INIS)

Wang Ju; Guo Yonghai; Chen Weiming

2008-01-01

This paper presents the final achievement of the project 'Studies of Site-specific Geological Environment for High Level Waste Disposal and Performance Assessment Methodology, Part Ⅰ: Studies on Site Characterization Methodologies for High Level Radioactive Waste Disposal', which is a 'Key Scientific and Technological Pre-Research Project for National Defense' during 2001-2005. The study area is Beishan area, Gansu Province, NW China--the most potential site for China's underground research laboratory and high level radioactive waste repository. The boreholes BS01, BS2, BS03 and BS04 drilled in fractured granite media in Beishan are used to conduct comprehensive studies on site characterization methodologies, including: bore hole drilling method, in situ measurement methods of hydrogeological parameters, underground water sampling technology, hydrogeochemical logging method, geo-stress measurement method, acoustic borehole televiewer measurement method, borehole radar measurement method, fault stability evaluation methods and rock joint evaluation method. The execution of the project has resulted in the establishment of an 'Integrated Methodological System for Site Characterization in Granite Site for High Level Radioactive Waste Repository' and the 8 key methodologies for site characterization: bore hole drilling method with minimum disturbance to rock mass, measurement method for hydrogeological parameters of fracture granite mass, in situ groundwater sampling methods from bore holes in fractured granite mass, fracture measurement methods by borehole televiewer and bore radar system, hydrogeochemical logging, low permeability measurement methods, geophysical methods for rock mass evaluation, modeling methods for rock joints. Those methods are comprehensive, advanced, innovative, practical, reliable and of high accuracy. The comprehensive utilization of those methods in granite mass will help to obtain systematic parameters of

Method for processing radioactive wastes containing sodium

International Nuclear Information System (INIS)

Kubota, Takeshi.

1975-01-01

Object: To bake, solidify and process even radioactive wastes highly containing sodium. Structure: H and or NH 4 zeolites of more than 90g per chemical equivalent of sodium present in the waste is added to and left in radioactive wastes containing sodium, after which they are fed to a baker such as rotary cylindrical baker, spray baker and the like to bake and solidify the wastes at 350 to 800 0 C. Thereby, it is possible to bake and solidify even radioactive wastes highly containing sodium, which has been impossible to do so previously. (Kamimura, M.)

Development of very low-level radioactive waste sequestration process criteria

Energy Technology Data Exchange (ETDEWEB)

Chan, N.; Wong, P., E-mail: nicholas.chan@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

2015-12-15

Segregating radioactive waste at the source and reclassifying radioactive waste to lower waste classes are the key activities to reduce the environmental footprint and long-term liability. In the Canadian Standards Association's radioactive waste classification system, there are 2 sub-classes within low-level radioactive waste: very short-lived radioactive waste and very low-level radioactive waste (VLLW). VLLW has a low hazard potential but is above the Canadian unconditional clearance criteria as set out in Schedule 2 of Nuclear Substances and Devices Regulations. Long-term waste management facilities for VLLW do not require a high degree of containment and isolation. In general, a relatively low-cost near-surface facility with limited regulatory control is suitable for VLLW. At Canadian Nuclear Laboratories' Chalk River Laboratories site an initiative, VLLW Sequestration, was implemented in 2013 to set aside potential VLLW for temporary storage and to be later dispositioned in the planned VLLW facility. As of May 2015, a total of 236m{sup 3} resulting in approximately $1.1 million in total savings have been sequestered. One of the main hurdles in implementing VLLW Sequestration is the development of process criteria. Waste Acceptance Criteria (WAC) are used as a guide or as requirements for determining whether waste is accepted by the waste management facility. Establishment of the process criteria ensures that segregated waste materials have a high likelihood to meet the VLLW WAC and be accepted into the planned VLLW facility. This paper outlines the challenges and various factors which were considered in the development of interim process criteria. (author)

2. plan of R and D: methodological technological, instrumental and numerical developments for radioactive wastes management

International Nuclear Information System (INIS)

1995-10-01

The second meeting of R and D in radioactive waste management was organized by ENRESA on June 1995 in Madrid. The main objective was to disseminate the most relevant works within the R and D plan, and to establish an adequate form involved for discussion R and D radioactive waste management. The meeting was articulated in the followings sessions: I.- Low and medium radioactive wastes II.- High level radioactive wastes: activities of ENRESA III.- High level radioactive wastes: near field IV.- Biosphere, radiological protection, behaviour evaluation V.-Dismantling and decommissioning nuclear facilities VI.- Geosphere (Author)

Non-fuel cycle radioactive waste policy in Turkey

International Nuclear Information System (INIS)

Izmir, A.I.; Uslu, I.

2001-01-01

be difficult to trace. The fundamental issue for which protection is required, is the prevention of over exposure of individuals or groups throughout the entire life cycle of sealed sources, lkitelli Accident in Istanbul (in 08.01.1999) shows the importance of life cycle of sealed source. Disused sealed sources which potentially represent medium and high radiological risks in Turkey are mainly Am-241, Ra-226, Kr-85, Co-60, lr-192 and Cs-137. According to 'The Radiation Protection Regulation' all spent sources have to be sent to the manufacturer. However, the spent sources which the manufacturer stopped its source related activities or the sources which were imported before the issue of the Regulation, are stored in Radioactive Waste Processing and Storage Facility (CWPSF) of Cekmece Nuclear Research and Training Center (CNRTC). Main radionuclides in the inventory of the Facility are Co-60, Cs-137, Am-240, Sr-90, Kr-85, Fe-55 respectively. Conclusion. Waste prevention and minimisation is an essential element of any radioactive waste management strategy. The objective of waste minimisation is to reduce the activity and the volume of wastes for storage, treatment and disposal. The environmental impact will also be reduced, as well as the costs associated with contaminated material management. Due to increasing number of radiation and nuclear related activities, the waste facility of CNRTC 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 the best place for the final storage of processed radioactive wastes. Research and development studies in TAEA will continue in radioactive waste management with the aim of improving data, models, and concepts related to long-term safety of disposal of radioactive waste. (author)

Reduction of Radioactive Waste Through the Reuse and Recycle Policy of the Sealed Radioactive Sources Management

Directory of Open Access Journals (Sweden)

T. Marpaung

2012-08-01

Full Text Available In the past few years, the utilization of sealed source for medical, industrial and research purposes has shown an accelerating increase. This situation will lead to increases in the amount of sealed radioactive. During its use, a sealed radioactive waste will eventually become either a spent sealed source or disused sealed radioactive source (DSRS, due to certain factors. The reduction of the amount of radioactive waste can be executed through the application of reuse and recycle of sealed source. The reuse and recycle policy for spent and disused sealed sources are not already specified yet. The reuse of spent sealed sources can be applied only for the sources which had been used in the medical field for radiotherapy, namely the reuse of a teletherapy Co-60 source in a calibration facility. The recycle of a spent sealed source can be performed for radioactive sources with relatively high activities and long half-lives; however, the recycling activity may only be performed by the manufacturer. To avoid legal conflicts, in the amendment to the Government Regulation No.27 Year 2002 on Management of Radioactive Waste, there will be a recommendation for a new scheme in the management of radioactive waste to facilitate the application of the principles of reduce, reuse, and recycle

Reduction of Radioactive Waste Through the Reuse and Recycle Policy of the Sealed Radioactive Sources Management

International Nuclear Information System (INIS)

Marpaung, T.

2012-01-01

In the past few years, the utilization of sealed source for medical, industrial and research purposes has shown an accelerating increase. This situation will lead to increases in the amount of sealed radioactive. During its use, a sealed radioactive waste will eventually become either a spent sealed source or disused sealed radioactive source (DSRS), due to certain factors. The reduction of the amount of radioactive waste can be executed through the application of reuse and recycle of sealed source. The reuse and recycle policy for spent and disused sealed sources are not already specified yet. The reuse of spent sealed sources can be applied only for the sources which had been used in the medical field for radiotherapy, namely the reuse of a teletherapy Co-60 source in a calibration facility. The recycle of a spent sealed source can be performed for radioactive sources with relatively high activities and long half-lives; however, the recycling activity may only be performed by the manufacturer. To avoid legal conflicts, in the amendment to the Government Regulation No.27 Year 2002 on Management of Radioactive Waste, there will be a recommendation for a new scheme in the management of radioactive waste to facilitate the application of the principles of reduce, reuse, and recycle (author)

Methods of Disposing Of High-Level Radioactive Waste: A Review

International Nuclear Information System (INIS)

Abumurade, K.

2002-01-01

High level nuclear waste from both commercial reactors and defense industry presents a difficult problem to the scientific community as well as the public. The solutions to this problem is still debatable both technically and ethically. There are few methods proposed for disposing of high level waste. Each method has its own advantages and disadvantages. However, the very deep underground geologic repository is the best choice for disposing of high-level radioactive wastes. The cost benefit equation of nuclear power production and its waste is discussed. However, the public should be educated about this matter to minimize the gap between them and the nuclear power community including scientists industry, and governments. (Author) 15 refs., 4 tabs., 1 fig

Uncertainty quantification applied to the radiological characterization of radioactive waste.

Science.gov (United States)

Zaffora, B; Magistris, M; Saporta, G; Chevalier, J-P

2017-09-01

This paper describes the process adopted at the European Organization for Nuclear Research (CERN) to quantify uncertainties affecting the characterization of very-low-level radioactive waste. Radioactive waste is a by-product of the operation of high-energy particle accelerators. Radioactive waste must be characterized to ensure its safe disposal in final repositories. Characterizing radioactive waste means establishing the list of radionuclides together with their activities. The estimated activity levels are compared to the limits given by the national authority of the waste disposal. The quantification of the uncertainty affecting the concentration of the radionuclides is therefore essential to estimate the acceptability of the waste in the final repository but also to control the sorting, volume reduction and packaging phases of the characterization process. The characterization method consists of estimating the activity of produced radionuclides either by experimental methods or statistical approaches. The uncertainties are estimated using classical statistical methods and uncertainty propagation. A mixed multivariate random vector is built to generate random input parameters for the activity calculations. The random vector is a robust tool to account for the unknown radiological history of legacy waste. This analytical technique is also particularly useful to generate random chemical compositions of materials when the trace element concentrations are not available or cannot be measured. The methodology was validated using a waste population of legacy copper activated at CERN. The methodology introduced here represents a first approach for the uncertainty quantification (UQ) of the characterization process of waste produced at particle accelerators. Copyright © 2017 Elsevier Ltd. All rights reserved.

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

Processing method and device for radioactive waste containing surfactant

International Nuclear Information System (INIS)

Yukita, Atsushi; Yoshikawa, Ryozo; Izumida, Tatsuo; Nishi, Takashi; Hattori, Yasuo.

1997-01-01

Washing liquid wastes generated in washing facilities in a nuclear power plant are collected in a liquid waste collecting tank. A suspension containing a powdery active carbon is supplied to the liquid waste collecting tank. Organic ingredients such as of a surfactant, oil ingredients and radioactive materials in the form of ions contained in the washing liquid wastes are adsorbed to the powdery active carbon. The washing liquid wastes containing the powdery active carbon and granular radioactive materials are led into an active carbon separating and drying device. The powdery active carbon and granular radioactive materials contained in the washing liquid wastes are filtered and separated by a filtering plate, and accumulated as filtered materials on the surface of the filtering plate. The purified washing liquid wastes are discharged to the outside. The filtered materials are dried by hot steams (or hot water) and dried air. The filtered materials are peeled from the filtering plate. The filtered materials, in other word, dried powdery active carbon and granular radioactive materials are transported to and burnt in an incinerator. (I.N.)

Radioactive waste management in West Germany

Energy Technology Data Exchange (ETDEWEB)

Krause, H [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.)

1978-01-01

The technologies developed in West Germany for radioactive waste management are widely reviewed. The first topic in this review paper is the disposal of low- and middle-level radioactive liquid wastes. Almost all these liquid wastes are evaporated, and the typical decontamination factor attained is 10/sup 4/ -- 10/sup 6/. The second topic is the solidification of residuals. Short explanation is given to bituminization and some new processes. The third topic is high-level liquid wastes. Degradation of glass quality due to various radiation is discussed. Embedding of small glass particles containing radioactive wastes into metal is also explained. Disposals of low-level solid wastes and the special wastes produced from reprocessing and mixed oxide fuel fabrication are explained. Final disposal of radioactive wastes in halite is discussed as the last topic. Many photographs are used to illustrate the industrial or experimental use of those management methods.