Assessment of studies and researches on warehousing - High-level and intermediate-level-long-lived radioactive wastes - December 2012

International Nuclear Information System (INIS)

2013-01-01

This large report first presents the approach adopted for the study and research on the warehousing of high-level and intermediate-level-long-lived radioactive wastes. It outlines how reversible storage and warehousing are complementary, discusses the lessons learned from researches performed by the CEA on long duration warehousing, presents the framework of studies and researches performed since 2006, and presents the scientific and technical content of studies and researches (warehousing need analysis, search for technical options providing complementarity with storage, extension or creation of warehousing installations). The second part addresses high-level and intermediate-level-long-lived radioactive waste parcels, indicates their origins and quantities. The third part proposes an analysis of warehousing capacities: existing capacities, French industrial experience in waste parcel warehousing, foreign experience in waste warehousing. The fourth part addresses reversible storage in deep geological formation: storage safety functions, storage reversibility, storage parcels, storage architecture, chronicle draft. The fifth part proposes an inventory of warehousing needs in terms of additional capacities for the both types of wastes (high-level, and intermediate-level-long-lived), and discusses warehousing functionalities and safety objectives. The sixth and seventh parts propose a detailed overview of design options for warehousing installations, respectively for high-level and for intermediate-level-long-lived waste parcels: main technical issues, feasibility studies of different concepts or architecture shapes, results of previous studies and introduction to studies performed since 2011, possible evolutions of the HA1, HA2 and MAVL concepts. The eighth chapter reports a phenomenological analysis of warehousing and the optimisation of material selection and construction arrangements. The last part discusses the application of researches to the extension of the

Proceedings of the public debate on the general options of management of high and intermediate activity and long-lived radioactive wastes

International Nuclear Information System (INIS)

2006-01-01

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprised 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is a summary of the main questions tackled during this debate from its preparation to its closing meeting and dealing with: the acceptation of the debate, the progress of the debate, the socio-technical problem of gathering the different points to be debated with respect to the different areas in concern, the general questions about the overall nuclear wastes and materials (radioactivity, health, radioprotection, management, reprocessing, control, actors organization, knowledge sharing, perenniality of the financing), the specific questions about long-lived wastes (inventory, separation-transmutation feasibility, nuclear energy and energy policy, management solutions, storage and geologic disposal feasibility, impact of debates on the 2006 law, long-lived waste territories), the conclusions for the 2006 law: mastering the overall nuclear wastes and materials and step-by-step building up of a solution for long-lived wastes (difficulties, lessons learnt from foreign experience, first draft of the 2006 law). Some opinions expressed by some participants about these proposals conclude

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

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.)

LA-ICP-MS for Trace Analysis of Long-Lived Radionuclides in Solid Non-conducting Radioactive Waste Samples

International Nuclear Information System (INIS)

Becker, J.S.; Gastel, M.; Tenzler, D.; Dietze, H.J.

1999-01-01

The characterization of radioactive waste materials from nuclear reactors for recycling and final storage requires fast, sensitive and precise analytical methods, which are able to determine long-lived radionuclidic ultra traces in a short time. For the determination of long-lived α and β ray-emitting nuclides besides the classical radiochemical methods which are mostly include time-consuming radiochemical separation procedures, to an increasing extent inductively coupled plasma mass spectrometry (ICP-MS) has been used successfully as a powerful trace, ultra trace and isotopic analytical method for the determination of long-lived radionuclides in aqueous solutions [1-3

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.)

Long-lived radioactive waste, the French management policy

International Nuclear Information System (INIS)

Barber, P.

1994-01-01

An overwhelming majority of both chambers of the French Parliament voted in favor of Public Law 91-1381 on December 30, 1991, the Waste Act which outlines the research program to be conducted for disposal of long-lived waste. The program focuses on three main research objectives, which are briefly discussed in this presentation: reduction of waste volume and toxicity (advanced partitioning and transmutation); assessment of the waste isolation properties of deep geologic formations; and development of solidification processes and storage techniques for long-term interim storage in near surface facilities. Annual reports on this research will be reviewed by a national commission and submitted to Parliament. Within 15 years, the government will prepare a comprehensive report and may enact new legislation authorizing the creation of a repository. The Waste Act also establishes the conditions for underground geologic research laboratories; site selection, public information and monitoring procedures; and economic incentives related to these facilities, which represent major financial investments that will benefit communities in the involved regions

Long-lived radioactive waste, the French management policy

International Nuclear Information System (INIS)

Barber, P.

1994-01-01

An overwhelming majority of both chambers of the French Parliament voted in favor of Public Law 91-1381 on December 30, 1991, which outlines the research program to be conducted for disposal of long-lived waste. The program focuses on three main research objectives: reduction of waste volumes and toxicity (advanced partitioning and transmutation); assessment of the waste isolation properties of deep geologic formations; and development of solidification processes and storage techniques for long-term interim storage in near-surface facilities. Annual reports on this research will be reviewed by a national commission and submitted to Parliament. Within 15 years, the government will prepare a comprehensive report and may enact new legislation authorizing the creation of a repository. The Waste Act also establishes the conditions for siting underground geologic research laboratories; site selection, public information and monitoring procedures; and economic incentives related to these facilities, which represent major financial investments that will benefit communities in the involved regions

Social scientist on board in long-term management of high level and/or long-lived radioactive waste in Belgium

International Nuclear Information System (INIS)

Parotte, C.

2013-01-01

In Belgium, the long-term management of radioactive waste is under the exclusive competence of the Belgian Agency for Radioactive Waste and Enriched Fissile Materials (knew as ONDRAF/NIRAS). Unlike low-level waste, no institutional policy has yet been formally approved for the long-term management of high level and/or long-lived radioactive waste (knew as B and C waste). In this context, ONDRAF/NIRAS considers the public and stakeholders' participation as an essential factor in the formulation of an effective and legitimate policy. This is why it has decided to integrate them in different ways during the elaboration of the Waste Plan (ONDRAF/NIRAS-document containing guidelines to make a principled policy decision about nuclear waste management). To do so, social scientists have been regularly mobilized either as external evaluators, follow-up committee members, or participatory observants. Hence, the Waste Plan is only the first step in a long decision-making process. For a PhD student under contract with ONDRAF/NIRAS, this mandate consists of thinking out a way to construct an inter-organizational innovative communication system that would be participative, transparent and embedded in a long-term perspective, thus integrating all the further legal steps to take throughout the decision-making process. In this regard, two paradoxical constraints must be taken into account: on the one hand, my own influence on the legal decision-making process should remain limited, because of a series of constraints, lock-ins and previous decisions which have to be respected; on the other hand, ONDRAF/NIRAS expects the research conclusions to be policy relevant and useful. In this paper, the purpose is twofold. Firstly, the issues raised by this policy mandate is an opportunity to question the per-formative dimensions of the social scientist in the decision-making process and, more specifically, to have a reflexive view on our position as PhD Student. Secondly, assuming the

Social scientist on board in long-term management of high level and/or long-lived radioactive waste in Belgium

Energy Technology Data Exchange (ETDEWEB)

Parotte, C. [Spiral Research Center, Department of Political Sciences, Faculty of Law, University of Liege (Belgium)

2013-07-01

In Belgium, the long-term management of radioactive waste is under the exclusive competence of the Belgian Agency for Radioactive Waste and Enriched Fissile Materials (knew as ONDRAF/NIRAS). Unlike low-level waste, no institutional policy has yet been formally approved for the long-term management of high level and/or long-lived radioactive waste (knew as B and C waste). In this context, ONDRAF/NIRAS considers the public and stakeholders' participation as an essential factor in the formulation of an effective and legitimate policy. This is why it has decided to integrate them in different ways during the elaboration of the Waste Plan (ONDRAF/NIRAS-document containing guidelines to make a principled policy decision about nuclear waste management). To do so, social scientists have been regularly mobilized either as external evaluators, follow-up committee members, or participatory observants. Hence, the Waste Plan is only the first step in a long decision-making process. For a PhD student under contract with ONDRAF/NIRAS, this mandate consists of thinking out a way to construct an inter-organizational innovative communication system that would be participative, transparent and embedded in a long-term perspective, thus integrating all the further legal steps to take throughout the decision-making process. In this regard, two paradoxical constraints must be taken into account: on the one hand, my own influence on the legal decision-making process should remain limited, because of a series of constraints, lock-ins and previous decisions which have to be respected; on the other hand, ONDRAF/NIRAS expects the research conclusions to be policy relevant and useful. In this paper, the purpose is twofold. Firstly, the issues raised by this policy mandate is an opportunity to question the per-formative dimensions of the social scientist in the decision-making process and, more specifically, to have a reflexive view on our position as PhD Student. Secondly, assuming the

Public debate on the general options relative to the management of high-medium activity and long-lived radioactive wastes

International Nuclear Information System (INIS)

2005-09-01

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. This document presents the organizational aspects of the debate: origin, organization committee (mission, members, commitments), framework (the December 31, 1991 law, technical enlargement, society aspects), topics (summary of the debate in ten questions), organization modalities (4 main steps, schedule, venues), objectives and perspectives (sharing information, decision making processes to be implemented by 2006). (J.S.)

The high level and long lived radioactive wastes; Les dechets radioactifs a haute activite et a vie longue

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

This report presents the main conclusions of 15 years of researches managed by the CEA. This report is the preliminary version of the 2005 final report. It presents the main conclusions of the actions on the axis 1 and 3 of the law of the 30 December 1991. The synthesis report on the axis 1 concerns results obtained on the long lived radionuclides separation and transmutation in high level and long lived radioactive wastes. the synthesis report on the axis 3 presents results obtained by the processes of conditioning and of ground and underground long term storage. (A.L.B.)

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)

What ethics should apply to the management of long-lived radioactive waste?

International Nuclear Information System (INIS)

Strohl, P.

2002-01-01

Taking action now in the name of a responsible attitude towards humanity in the future: management of the long-term risk posed by certain types of radioactive waste may give rise to a kind of metamoral revolution which goes beyond its specific nature - as long as it remains in the province of reality, rather than the imagination. Following the decisions made by the French Government in December 1998 concerning the creation of two underground laboratories, and the recent granting of permission to build the laboratory at Bure in the Meuse, it is perhaps time to discuss the ethical questions raised by the management of radioactive waste, because the responses usually put forward remain too superficial. Furthermore, it is all too often accepted that they should be made subordinate to the debates on the future of the nuclear industry within the framework of energy policy, whereas the waste that the industry has generated already exists. The safety of this waste must therefore be guaranteed, both in the immediate future and in the long term, so that mankind and the environment are not exposed to levels of irradiation or contamination which exceed those permitted by the radiological protection standards - and this must be done until the danger disappears through radioactive decay, whatever the fate of the nuclear industry. However, we can be certain that any weakening in nuclear technology would adversely affect management of the downstream portion of the fuel cycle

Amount, disposal and relative toxicity of long-lived fission products and actinides in the radioactive wastes of the nuclear fuel cycles

International Nuclear Information System (INIS)

Haug, H.O.

1975-11-01

A review is presented on the magnitude of the long-term problems of radioactive wastes from the nuclear power industry of the FRG (and Western Europe). The production of long-lived fission products and actinides has been calculated for several fuel types of the uranium-plutonium and thorium-uranium fuel cycles and related to a prediction of the development and share of LWR, FBR and HTGR. The quantities and concentrations of actinides, the radioactivity and relative toxicity index of the wastes of reprocessing (and fuel refabrication) and their changes by radioactive decay are presented. The radiotoxicity of the nuclide inventory of the solidified high-level wastes have been compared with naturally occuring uranium ores. On the long term (>10 3 years) the radiotoxicity level of the total area of the final repository in deep geological formation does not result in a significantly higher radiotoxicity level than an uranium ore deposit of low uranium content. Also discussed have been the chemical separation of the actinides from high-level wastes and recycling in fission reactors. (orig.) [de

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

2005 dossier. ANDRA's researches on the geological disposal of high-level and long-lived radioactive wastes. Results and perspectives

International Nuclear Information System (INIS)

2005-06-01

This document makes a status of the researches carried out by the French national agency of radioactive wastes (ANDRA) about the geologic disposal of high-level and long-lived radioactive wastes in deep geologic formations (argilites and granites). Content: 1 - Research on deep disposal of radioactive waste: general interest task: Legislative framework, ANDRA scientific objectives, Inspections and assessments; 2 - Designing a safe and reversible disposal system: Repository safety, Reversibility: an essential requirement; 3 - Clay Research on a repository in a clay formation, A long research programme, Dossier 2005 Argile; 4 - Meuse/Haute-Marne site clay: Expected properties of the rock formation, Choice of argillite, Meuse/Haute-Marne site, Conclusions from 10 years of research at the Meuse/Haute-Marne site; 5 - Repository installations: Safe and reversible architecture, Disposal of B waste, Disposal of C waste, Possible disposal of spent fuel (CU); 6 - The disposal facility in operation: From waste packages reception to their disposal in cells, Stages of the progressive closure of engineered structures; 7 - Reversible management: Freedom of choice for future generations, Various closure stages; 8 - Long-term evolution of the repository: Apprehending the repository complexity Main evolutions expected, Slow and limited release of radioactive substances; 9 - Repository safety and impact on man: Several evolution scenarios, Normal evolution, Altered evolution; 10 - Granite Research on a repository in a granite formation: A global approach, Scientific co-operations, Dossier 2005 Granite; 11 - Characteristics of French granite formations: What properties are required for a repository?, Different types of granite formations; 12 - Repository installations: Repository design adapted to granite fractures, Clay seals to prevent water flows, Waste disposal packages ensuring long-term leak-tightness, Physical and chemical environment favourable for waste packages, Architecture

Deep disposal of long-lived radioactive waste in France: The volunteering approach in site selection

International Nuclear Information System (INIS)

Raynal, M.; Barber, P.

1995-01-01

The French Waste Act of December 1991 set up important dispositions among which the deep disposal of long-lived waste should be evaluated before 2006. ANDRA, the French National Agency for Radioactive Waste Management, is particularly responsible for the siting, the construction and the operation of underground laboratories designed to study potential geologic host-formations for deep disposal. An open decision-making process started up in 1992, specially to restore the public confidence after strong contest in the early 1990. The mission of negotiation conducted in 1993 all over the country by the appointed Member of Parliament, Mr. Bataille, allowed volunteer candidates for the siting surveyed by ANDRA in 1994 and 1995. Four areas are presently under characterization investigations, proceeding with the first phase of the underground laboratory program with the objective of choosing two sites for two underground laboratories. France is now entering a new and very important phase on the long path towards the creation of an underground repository where public's understanding and acceptance is an important part of the overall process as it is shown in this paper

Long-Term Safety Analysis of Baldone Radioactive Waste Repository and Updating of Waste Acceptance Criteria

International Nuclear Information System (INIS)

2001-12-01

The main objective of the project was to provide advice to the Latvian authorities on the safety enhancements and waste acceptance criteria for near surface radioactive waste disposal facilities of the Baldone repository. The project included the following main activities: Analysis of the current status of the management of radioactive waste in Latvia in general and, at the Baldone repository in particular Development of the short and long-term safety analysis of the Baldone repository, including: the planned increasing of capacity for disposal and long term storage, the radiological analysis for the post-closure period Development of the Environment Impact Statement, for the new foreseen installations, considering the non radiological components Proposal of recommendations for future updating of radioactive waste acceptance criteria Proposal of recommendations for safety upgrades to the facility. The work programme has been developed in phases and main tasks as follows. Phase 0: Project inception, Phase 1: Establishment of current status, plans and practices (Legislation, regulation and standards, Radioactive waste management, Waste acceptance criteria), Phase 2: Development of future strategies for long-term safety management and recommendations for safety enhancements. The project team found the general approach use at the installation, the basic design and the operating practices appropriate to international standards. Nevertheless, a number of items subject to potential improvements were also identified. These upgrading recommendations deal with general aspects of the management (mainly storage versus disposal of long-lived sources), site and environmental surveillance, packaging (qualification of containers, waste characterization requirements), the design of an engineered cap and strategies for capping. (author)

Radioactive waste: show time? - 16309

International Nuclear Information System (INIS)

Codee, Hans; Verhoef, Ewoud

2009-01-01

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

Radioactive 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

A report of the symposium on 'comprehensive research on the management of long-lived radioactive wastes' in the Research Center for Nuclear Science and Technology, University of Tokyo

International Nuclear Information System (INIS)

Sekiguchi, Akira; Naito, Keiji; Suzuki, Susumu; Furuya, Hirotaka; Sato, Masatomo.

1983-01-01

In the Research Center for Nuclear Science and Technology, University of Tokyo, the special research project ''Comprehensive Research on the Management of Long-lived Radioactive WasΩtes'' is carried out in the three-year period from fiscal 1982 to 1984. In this connection, a symposium has been held on January 25, 1983. Seven lectures given by the respective speakers are summarized individually: (1) the research of transuranic elements in educational institutions, (2) an outline of the actinoid research facilities planned in Tohoku University, (3) the radiation damage and leachability of glass solids, (4) the situation and trend in Japan and abroad of the disposal of long-lived nuclide wastes, (5) practical site tests concerning the geologic-formation disposal of low-level wastes, (6) the trend in the research of geologic formations for the disposal of high-level wastes, (7) the safety in the management of long-lived radioactive wastes. (Mori, K.)

A contribution to the physical and chemical model of long-lived radioactive wastes by clayey materials

International Nuclear Information System (INIS)

Gorgeon, L.

1994-01-01

This work deals with the high-level and long-lived radioactive wastes confinement which come from the irradiated fuels reprocessing. These wastes are generally coated in a deep geological structure confinement matrix. The radiation protection of a such storage requires that the coating matrix, the technological barriers which separate the storage and the geological medium and the reception rock does not let the radioactive wastes pass. The materials used in this work for the confinement studies are clayey minerals and the retention mechanisms studies are realized on cesium 135, neptunium 237, americium 241 and uranium 233. The first part of this thesis concerns the clayey minerals retention properties towards ions in aqueous solutions. More particularly the relations between these properties and the chemical structure of these solids are investigated. In the second part are presented the experimental works which have allowed to specify the intrinsic characteristics of the studied minerals. Indeed the knowledge of these parameters is essential to quantitatively explain the results of the radionuclides retention. The adsorption mechanisms are described in a third part. (O.L.). 112 refs., 59 figs., 51 tabs

Current status of radioactive waste disposal in Japan and foreign countries

International Nuclear Information System (INIS)

Yamamoto, Masahumi; Inagaki, Yusuke; Kurata, Mitsuyuki; Tanabe, Hiromi

2002-01-01

Various kinds of wastes are generated from operation and decommissioning of nuclear facilities such as a nuclear power plant, a reprocessing plant and so on. These wastes contain radionuclides and are called 'Radioactive Waste'. The radionuclides in the wastes vary considerably in amount from small to large and their half-lives differ in length from short-lived to long-lived. The safety principle for radioactive waste management is to prevent human beings and the environment from receiving radiation exposure over the level which the safety authority in each country approve based on the recommendations by international organizations such as the International Commission on Radiation Protection (ICRP). To assure the conformity to this safety principle, each country has examined the safety measures to dispose of radioactive wastes on the basis of their own condition. For example, high-level radioactive waste (H LW) from reprocessing plant or spent fuel designated as waste and intermediate-and low-level long-lived radioactive wastes, which contain large quantity of long-lived radionuclides, will be disposed of into a deep stable geological formation. The intermediate-and low-level short-lived radioactive wastes, which mainly contain short-lived radionuclides with limited quantity of long-lived radionuclides, have been disposed of in a controlled surface disposal facility or in a rock cavern in the depth of 50-100 m. Clearance level has been considered to be applied for the wastes, which contain very small amount of radionuclides and those wastes bellow clearance level will cause negligible hazards only even without taking any radiation control measures. Such wastes could be reused, recycled or disposed of in the same manner as general wastes from the industries, etc. (author)

Status of the public debate on the general options of management of high and intermediate activity and long-lived radioactive wastes

International Nuclear Information System (INIS)

2006-01-01

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprised 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is a status of the general organisation and progress of the debate from its preparing to its end in mid-January 2006. It shows the challenges the CNDP had to take up to treat the scientifical and technical questions in an accessible way, allowing the participation and the hearing of the large public. A status is made of the deception and satisfaction of the public. A lack of confidence in public authorities and scientists has been expressed several times. No pro-nuclear/anti-nuclear shock has occurred and the debate has revealed a remarkable richness in its content. One contribution of the debate to the future project of law is its enlargement to the overall nuclear wastes and valorizable materials and not only to the high/intermediate-level and long-lived wastes. (J.S.)

Impact of long-lived radionuclides on waste classification for fusion

International Nuclear Information System (INIS)

Maninger, R.C.

1985-01-01

A major goal for commercial applications of fusion reactors is to minimize radioactive wastes and to dispose of them by near-surface burial. There currently are no regulations specifically applicable to fusion wastes but those in force for fission wastes furnish a framework for expected fusion regulations. This paper recommends that all nuclides with half-lives greater than five years be assigned concentration limits as done in 10CFR61 for fission wastes. The paper gives approximate limits for all the significant long half-life sources of gamma radiation in the currently known periodic table. In the absence of working fusion reactors, computer models must be used to estimate the expected actual concentrations of radioactive nuclides. These estimates are needed to guide design parameters to achieve minimum radioactivity in fusion reactors. It is believed that the computer models and nuclear reaction libraries must be much more comprehensive than ordinarily used today to do activation calculations

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

Conceptual design and cost inputs associated with co-disposal of the spent fuel and long lived radioactive wastes in the deep geologic disposal facility

International Nuclear Information System (INIS)

Fako, R.; Sociu, F.; Nicolae, R.; Barariu, G

2013-01-01

The paper aims to be an integrated approach for the containment and isolation of spent fuel and / or long lived radioactive wastes in a Deep Geologic Repository in Romania. Several scenarios could be defined for the management of spent fuel and long lived radioactive waste in Romania considering many specific constraints in Romania (political, geological, economic, demographic, etc.). This paper intends to be an upgrade of several Research, Development and Demonstration (RD&D) works performed by SITON specialists on this subject, taking into account also the conclusions of the Workshop ôCost estimation on spent nuclear fuel disposal in Romaniaö organized by IAEA in cooperation with ANDR at the beginning of this year in Romania.This paper is, also, addressed to decision makers with target on to adopt the best strategy for construction of Deep Geologic Repository in Romania. (authors)

1. round table - Nuclear wastes and radioactive materials. 2. round table - risks linked with nuclear wastes and materials. 3. round table - the problem of long-term management of medium-high activity and long lived wastes. The process defined by the 1991 law

International Nuclear Information System (INIS)

2005-01-01

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprises 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the synthesis of the debates of the first round table of Paris about the problems raised by nuclear wastes in the case of the geologic disposal option. Four families of questions have been tackled: 1 - the exhaustiveness of ANDRA's inventory, the solutions foreseen for the different types of wastes; 2 - the high-medium activity wastes and their processing; 3 - the management of non-reprocessed spent MOX fuels; 4 - the safety and security standards used and their establishment. Four presentations are attached to these proceedings and deal with: the measured and estimated inventory of all radioactive wastes; the inventory and management of radioactive wastes and the place of citizens; the point of view of the nuclear safety authority; conditioning and storage. (J.S.)

Concerted action on the retrievability of long lived radioactive waste in deep underground repositories - progress to date

International Nuclear Information System (INIS)

Dodd, D.H.

2000-01-01

Within the EURATOM Framework Programme: Nuclear Fission Safety, a Concerted Action on the retrievability of long lived radioactive waste in deep underground repositories is being carried out. This Concerted Action commenced on the 1st of January 1998 and involves experts from nine different European countries. The Concerted Action will be completed by the 31st of December 1999. This paper gives a brief overview of the objectives of the Concerted Action, the work programme that has been defined to meet these objectives, the work performed to date, and the remaining work programme. (author)

Waste inventory record keeping systems (WIRKS) for the management and disposal of radioactive waste

International Nuclear Information System (INIS)

2001-06-01

This report is intended to serve Member States planning to develop or implement radioactive waste disposal programmes and to discuss possible ways for compiling and managing information about the inventories in their radioactive waste repositories, which includes low and intermediate level waste (short lived and long lived) and high level radioactive waste. This report identifies generic information that may be recorded in a Waste Inventory Record Keeping System (WIRKS), as identified by consultants and based on their collective expertise in radioactive waste management. The report provides examples of WIRKS implementation in some countries

Public debate on radioactive wastes

International Nuclear Information System (INIS)

2005-01-01

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

Alternative solutions for the disposal of radioactive wastes

International Nuclear Information System (INIS)

Ramsey, R.W. Jr.

1976-01-01

Besides outlining the possibility of dispatching concentrated highly radioactive waste by rockets into space, or of transmuting long-lived isotopes by nuclear reactions into short-lived ones, the author discusses further alternatives for the disposal of radioactive wastes, especially the storage in geologic formations. (HR/LN) [de

Intrinsically secure fast reactors for long-lived waste free and proliferation resistant nuclear power

International Nuclear Information System (INIS)

Slessarev, Igor

2008-01-01

This paper provides description of a nuclear reactor concept aimed towards a radical safety enhancement, an increased proliferation resistance, as well as a realisation of a 'long-lived waste free' NP development. It emphasizes the achievement of considerable reduction ('by design') of residual actinides in the waste streams and of the most hazardous long-lived fission products. It allows to implement only small volume of repositories for the radioactive waste (mostly fission products) and to postpone the technically arduous problems of a large scale disposal of the long-lived wastes until the next millennium, i.e. up to the exhaustion of the fertile natural resources and/or the emergence of more effective technologies of nuclide separation/transmutation. A thorough incineration/transmutation of the wastes (residual actinides in the mixture with lanthanides as well as of the most hazardous fission products) under reactor neutron flux is proposed for their mass reduction. A gradual growth of NP park is necessary for increasing the NP park capacity for waste irradiation. This 'constraint' is not really limiting because it coincides with the permanently growing demands in energy production. The potential of long-lived waste reduction depends on the total fertile fuel resources and on NP growth rate. It was shown that the accumulated actinide long-lived radioactive masses will be reduced significantly: by factor in the range of 10 4 -10 8 in magnitude (compared with LWR once-through cycle) and by 10 2 -10 6 (compared with the ordinary fast reactor park). Thus, the total long-lived waste toxicity pollution source might be comparable with the 'burnt away' toxicity of the natural fertile feed stream. This is quite realistic taking into account the large fertile fuel (U/Th) world-wide resources which provide the NP growth for a sustained time. Along side with the radical intrinsic safety improvement, a further enhancement of core physics ('neutronics') is one of the

Safety and optimization aspects of radioactive waste long-term storage at the ''Vector'' site

International Nuclear Information System (INIS)

Tokarevs'kij, O.V.; Kondrat'jev, S.M.; Aleksjejeva, Z.M.; Ribalka, N.V.

2015-01-01

The paper analyzes links between the final disposal option and needs for long-term storage of radioactive waste taking into proposals on possible changes in radwaste classification as regards disposal. It considers the conceptual approach to design facilities for long-term storage of long-lived radioactive waste at the Vector site and approaches to apply requirements of regulatory documents, radiation safety principles and criteria for long-term storage of radwaste and safety assessment.

The UK system for regulating the long-term safety of radioactive waste disposal

International Nuclear Information System (INIS)

Duncan, A.

1997-01-01

The general system is described for regulation of disposal of solid, long-lived radioactive wastes. The relevant Government policy is outlined, and the framework of legislation and arrangements for implementation, the associated guidance produced by regulatory bodies and the approach to assessment by regulators of a safety case for radioactive waste disposal are reported. Also, for the purposes of discussion in the Workshop, some of the practical issues are considered which are still in development in the UK in regard to regulatory methodology. (author)

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

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)

Long-lived radioactive waste and nuclear plant decommissioning a legacy to future generations

International Nuclear Information System (INIS)

McAulay, I.R.

1996-01-01

Radioactive waste is an inevitable by-product of all uses of radioactive substances. This is the case of natural radioactivity as well as for artificially produced radioactive isotopes, and it is easy to overlook the significance of the waste problem in the case of technologically enhanced natural radioactivity. Several options are available for the disposal of radioactive waste and the paper considers these in detail from the point of view of the possible future impact of radiation doses to individuals or populations. Particular consideration is given to the use of deep disposal at stable geological sites as a means of dealing with large amounts of radioactive waste. It should not be forgotten that some of what we term waste today need not necessarily always be so. Indeed, there is a good case to make for the recycling of low activity materials rather than the uneconomic expedient of burying them. The paper will consider the possible recycling of valuable materials following suitable reprocessing and dilution and mention the dose implications of examples of such re-utilisation of radioactive materials

Long-lived radioactive waste and nuclear plant decommissioning a legacy to future generations

Energy Technology Data Exchange (ETDEWEB)

McAulay, I R [Trinity Coll., Dublin (Ireland). Physical Lab.

1996-10-01

Radioactive waste is an inevitable by-product of all uses of radioactive substances. This is the case of natural radioactivity as well as for artificially produced radioactive isotopes, and it is easy to overlook the significance of the waste problem in the case of technologically enhanced natural radioactivity. Several options are available for the disposal of radioactive waste and the paper considers these in detail from the point of view of the possible future impact of radiation doses to individuals or populations. Particular consideration is given to the use of deep disposal at stable geological sites as a means of dealing with large amounts of radioactive waste. It should not be forgotten that some of what we term waste today need not necessarily always be so. Indeed, there is a good case to make for the recycling of low activity materials rather than the uneconomic expedient of burying them. The paper will consider the possible recycling of valuable materials following suitable reprocessing and dilution and mention the dose implications of examples of such re-utilisation of radioactive materials.

Radioactive waste management and disposal in Australia

International Nuclear Information System (INIS)

Harries, J.R.

1997-01-01

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

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

Interpretation of optimisation in the context of a disposal facility for long-lived radioactive waste

International Nuclear Information System (INIS)

1999-01-01

project P3-033 contained in the following output: R and D Technical Report P259 - Interpretation of Optimisation in the Context of a disposal Facility for Long-Lived Radioactive Waste. (author)

Development plan. High activity-long living wastes project. Abstract; Plan de developpement. Projet HAVL. Resume

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

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.)

ICRP PUBLICATION 122: radiological protection in geological disposal of long-lived solid radioactive waste.

Science.gov (United States)

Weiss, W; Larsson, C-M; McKenney, C; Minon, J-P; Mobbs, S; Schneider, T; Umeki, H; Hilden, W; Pescatore, C; Vesterlind, M

2013-06-01

This report updates and consolidates previous recommendations of the International Commission on Radiological Protection (ICRP) related to solid waste disposal (ICRP, 1985, 1997b, 1998). The recommendations given apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the ICRP system of radiological protection described in Publication 103 (ICRP, 2007) can be applied in the context of the geological disposal of long-lived solid radioactive waste. Although the report is written as a standalone document, previous ICRP recommendations not dealt with in depth in the report are still valid. The 2007 ICRP system of radiological protection evolves from the previous process-based protection approach relying on the distinction between practices and interventions by moving to an approach based on the distinction between three types of exposure situation: planned, emergency and existing. The Recommendations maintains the Commission's three fundamental principles of radiological protection namely: justification, optimisation of protection and the application of dose limits. They also maintain the current individual dose limits for effective dose and equivalent dose from all regulated sources in planned exposure situations. They re-enforce the principle of optimisation of radiological protection, which applies in a similar way to all exposure situations, subject to restrictions on individual doses: constraints for planned exposure situations, and reference levels for emergency and existing exposure situations. The Recommendations also include an approach for developing a framework to demonstrate radiological protection of the environment. This report describes the different stages in the life time of a geological disposal facility, and addresses the application of relevant radiological protection principles for each stage depending on the various exposure situations that can be encountered. In particular, the crucial factor that

ICRP PUBLICATION 122: Radiological Protection in Geological Disposal of Long-lived Solid Radioactive Waste

International Nuclear Information System (INIS)

Weiss, W.; Larsson, C-M.; McKenney, C.; Minon, J-P.; Mobbs, S.; Schneider, T.; Umeki, H.; Hilden, W.; Pescatore, C.; Vesterlind, M.

2013-01-01

This report updates and consolidates previous recommendations of the International Commission on Radiological Protection (ICRP) related to solid waste disposal (ICRP, 1985, 1997b, 1998). The recommendations given apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the ICRP system of radiological protection described in Publication 103 (ICRP, 2007) can be applied in the context of the geological disposal of long-lived solid radioactive waste. Although the report is written as a standalone document, previous ICRP recommendations not dealt with in depth in the report are still valid. The 2007 ICRP system of radiological protection evolves from the previous process-based protection approach relying on the distinction between practices and interventions by moving to an approach based on the distinction between three types of exposure situation: planned, emergency and existing. The Recommendations maintains the Commission’s three fundamental principles of radiological protection namely: justification, optimisation of protection and the application of dose limits. They also maintain the current individual dose limits for effective dose and equivalent dose from all regulated sources in planned exposure situations. They re-enforce the principle of optimisation of radiological protection, which applies in a similar way to all exposure situations, subject to restrictions on individual doses: constraints for planned exposure situations, and reference levels for emergency and existing exposure situations. The Recommendations also include an approach for developing a framework to demonstrate radiological protection of the environment. This report describes the different stages in the life time of a geological disposal facility, and addresses the application of relevant radiological protection principles for each stage depending on the various exposure situations that can be encountered. In particular, the crucial factor that

Shallow land disposal of radioactive waste

International Nuclear Information System (INIS)

1987-01-01

The application of basic radiation protection concepts and objectives to the disposal of radioactive wastes requires the development of specific reference levels or criteria for the radiological acceptance of each type of waste in each disposal option. This report suggests a methodology for the establishment of acceptance criteria for the disposal of low-level radioactive waste containing long-lived radionuclides in shallow land burial facilities

Geological repository layout for radioactive high level long lived waste in argillite

International Nuclear Information System (INIS)

Gaussen, JL

2006-01-01

In the framework of the 1991 French radioactive waste act, ANDRA has studied the feasibility of a geological repository in the argillite layer of the Bure site for high level long lived waste. This presentation is focussed on the underground facilities which constitute the specific component of this project. The preliminary underground layout which has been elaborated is based on four categories of data: - the waste characteristics and inventory; - the geological properties of the host argillite; - the long term performance objectives of the repository; - the specifications in terms of operation and reversibility. The underground facilities consist of two types of works: the access works (shafts and drifts) and the disposal cells. The function of the access works is to permit the implementation of two concurrent activities: the nuclear operations (transfer and emplacement of the disposal packages into the disposal cells) and the construction of the next disposal cells. The design of the drifts network which matches up to this function is also influenced by two other specifications: the minimization of the drift dimensions in order to limit their influence on the integrity of the geological formation and the necessity of a safe ventilation in case of fire. The resulting layout is a network of 4 parallel drifts (2 of them being dedicated to the operation, the other two being dedicated to the construction activities). The average diameter of these access drifts is 7 meters. The link between the surface and the underground is ensured by 4 shafts. The most important function of the disposal cells is to contribute to the long term performance of the repository. In this regard, the thermal and geotechnical considerations play an important role. The B wastes (intermediate level wastes) are not (or not very) exothermic. Consequently, the design of their disposal cells result mainly from geotechnical considerations. The disposal packages (made of concrete) are piled up in

Radioactive waste management and disposal

International Nuclear Information System (INIS)

Kaluzny, Y.

1994-01-01

The public has demonstrated interest and even concern for radioactive waste. A fully demonstrated industrial solution already exists for 90% of the waste generated by the nuclear industry. Several solutions are currently under development for long-term management of long-lived waste. They could be implemented on an industrial scale within twenty years. The low volumes of this type of waste mean there is plenty of time to adopt a solution. (author). 5 photos

Sub-seabed disposal of radioactive wastes

International Nuclear Information System (INIS)

Sivintsaev, Yu.V.

1990-01-01

The first stage of investigations of possibility of sub-seabed disposal of long-living intermediate-level radioactive wastes carried out by NIREX (UK) is described. Advantages and disadvantages of sub-seabed disposal of radioactive wastes are considered; regions suitable for disposal, transport means for marine disposal are described. Three types of sub-seabed burials are characterized

The radioactive wastes: an easy and realistic approach

International Nuclear Information System (INIS)

Pradel, J.

2000-01-01

The question of radioactive waste storage is developed in this feature article. The two categories discussed are the low level and short lived radioactive wastes (period inferior to 30 years) and the long lived and high level radioactive wastes. The technical part about the storage is detailed, then, a study about unexpected troubles that could occur is made and their consequences studied. The last but not the least part is the development about the reasons that alarm the population and the solutions to bring about it. (N.C.)

Fiscal 1982 progress report of 'comprehensive research on the management of long-lived radioactive wastes' in the Research Center for Nuclear Science and Technology, University of Tokyo

International Nuclear Information System (INIS)

Sekiguchi, Akira; Kosako, Toshiso

1983-01-01

In the Research Center for Nuclear Science and Technology, University of Tokyo, the special research project ''Comprehensive Research on the Management of Long-lived Radioactive Wastes'' is carried out in the three-year period from fiscal 1982 to 1984. The works performed in the fiscal year 1982 are described individually, each short description on research purposes and contents, results, future plans, etc. the research works in the three fields of material science, biology and process technology are buffer materials in land disposal, canisters, corrosion of waste-container materials, thermal analysis of high-level wastes, effects of tritium on cells and marine life, biological effect of long-lived nuclides, separation of tritium wastes, actinoids and krypton-iodine, environmental migration of radionuclides, and accident analysis. (Mori, K.)

Disposal options for radioactive waste

International Nuclear Information System (INIS)

Olivier, J.P.

1991-01-01

On the basis of the radionuclide composition and the relative toxicity of radioactive wastes, a range of different options are available for their disposal. Practically all disposal options rely on confinement of radioactive materials and isolation from the biosphere. Dilution and dispersion into the environment are only used for slightly contaminated gaseous and liquid effluents produced during the routine operation of nuclear facilities, such as power plants. For the bulk of solid radioactive waste, whatever the contamination level and decay of radiotoxicity with time are, isolation from the biosphere is the objective of waste disposal policies. The paper describes disposal approaches and the various techniques used in this respect, such as shallow land burial with minimum engineered barriers, engineered facilities built at/near the surface, rock cavities at great depth and finally deep geologic repositories for long-lived waste. The concept of disposing long-lived waste into seabed sediment layers is also discussed, as well as more remote possibilities, such as disposal in outer space or transmutation. For each of these disposal methods, the measures to be adopted at institutional level to reinforce technical isolation concepts are described. To the extent possible, some comments are made with regard to the applicability of such disposal methods to other hazardous wastes. (au)

Taking into account the long term dimension associated with radioactive waste management

International Nuclear Information System (INIS)

Schieber, C.; Schneider, T.; Lavelle, S.

2008-01-01

Radioactive waste introduces a new time dimension in the field of risk management. This is why, for more than 10 years, there have been reflections on the societal and organisational mechanisms allowing a responsible management over the long term of the risk associated with radioactive waste. These reflections lead one to ask questions regarding interactions between what is at stake for societal and radiation protection criteria, demanding a multidisciplinary approach to the problem. Within the framework of the European project C.O.W.A.M. 2, dedicated to the improvement of governance of radioactive waste management in Europe, a working group involving experts, authorities, waste managers, locally elected representatives and N.G.O.s, discussed the stakes associated with the long term dimension. This article presents the main results of this working group, organised around four themes: meaning of the long term and what is at stake, the ethical dimension regarding long term issues, continuity and sustainability of the surveillance and control of radioactive waste facilities, effectiveness of financing schemes for the long term management of radioactive waste. (authors)

Ethical aspects of long-lived waste disposal

International Nuclear Information System (INIS)

McCombie, C.

1996-01-01

Independent of the long debate on the use of nuclear power, waste management specialists have a clear, unassailable set of environmental goals aimed at protecting the public and workers from any unjustifiable exposure to radiation. It is recognized that releases to the environment must be minimized, operational doses from waste handling kept low, and storage facilities constructed and operated with very high levels of safety. A philosophy of how to make best use of the available resources is embedded into the established principles of the ICRP, requiring justification of practices, limitation of doses and optimization. The situation is different when we consider the particular case of disposal of long-lived radioactive waste. Properly designed and sited repositories will present only low levels of risk - but these risks are predicted to peak only after many thousands of years. It is obvious, therefore, that this disposal involves the present and immediately following generations investing resources into the protection of far-future individuals. Attention has focused upon this intergeneration issue in recent years, leading to intensified debate on all ethical aspects of waste disposal. In this paper, I will try to provide a short overview of recent relevant work, to indicate the ethical principles agreed upon and to highlight the currently most controversial issues. (author)

Characteristics of medically related low-level radioactive waste

International Nuclear Information System (INIS)

Weir, G.J. Jr.; Teele, B.

1986-07-01

This report describes a survey that identified the current sources of medically generated radioactive wastes. Included are recommendations on how to reduce the volume of medically-related material classified as low-level radioactive wastes, to improve handling techniques for long-lived radioisotopes, and for options for the use of radioactive materials in medical studies. 8 refs., 11 tabs

The long-term management of radioactive waste

International Nuclear Information System (INIS)

Faussat, A.

1988-01-01

After setting out the terms of reference of ANDRA (National agency for the management of radioactive waste), the author describes the current situation and the projects for the surface storage of waste of low and medium activity. He then discusses the work which has started on the construction of an underground laboratory for studying the storage of long life waste [fr

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

Issues for the long term management of radioactive waste

International Nuclear Information System (INIS)

Schneider, T.; Schieber, C.; Lavelle, S.

2006-01-01

High-level radioactive waste are currently managed in interim storage installations, providing an adequate protection of the public and the workers for the short term period. However, the long-term persistence of the radioactivity of the waste gives a new timescale dimension, never experimented by the society for the development of protection systems. In the framework of the European Commission research project 'COWAM-2' (COmmunity WAste Management) dedicated to the governance of radioactive waste management, the issues of 'long term governance' have been addressed by exploring the elements which can contribute to a better integration of the technical and societal time dimensions, taking into account technical, ethical, economic and organizational considerations. The originality of this project is to address the various issues within working groups involving stakeholders from different origins and European countries together with a research team. After a discussion on the time dimensions to be taken into account from the technical and societal perspective, this paper presents, mainly based on the findings of the COWAM-2 project, a brief analysis of the ethical criteria to be considered when future generations are concerned as well as some performance criteria regarding long term governance. Finally, it proposes a discussion on the interest for the radiation protection experts to engage a process with stakeholders concerned by radioactive waste management in order to favour the emergence of a sustainable management responding to the issues at stake and including radiation protection considerations for long term periods. (authors)

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)

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.

Issues for the long term management of radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Schneider, T.; Schieber, C. [CEPN, 92 - Fontenay-aux-Roses (France); Lavelle, S. [ICAM, 59 - Lille (France)

2006-07-01

High-level radioactive waste are currently managed in interim storage installations, providing an adequate protection of the public and the workers for the short term period. However, the long-term persistence of the radioactivity of the waste gives a new timescale dimension, never experimented by the society for the development of protection systems. In the framework of the European Commission research project 'COWAM-2' (COmmunity WAste Management) dedicated to the governance of radioactive waste management, the issues of 'long term governance' have been addressed by exploring the elements which can contribute to a better integration of the technical and societal time dimensions, taking into account technical, ethical, economic and organizational considerations. The originality of this project is to address the various issues within working groups involving stakeholders from different origins and European countries together with a research team. After a discussion on the time dimensions to be taken into account from the technical and societal perspective, this paper presents, mainly based on the findings of the COWAM-2 project, a brief analysis of the ethical criteria to be considered when future generations are concerned as well as some performance criteria regarding long term governance. Finally, it proposes a discussion on the interest for the radiation protection experts to engage a process with stakeholders concerned by radioactive waste management in order to favour the emergence of a sustainable management responding to the issues at stake and including radiation protection considerations for long term periods. (authors)

The concept of responsibility to future generations for the management and storage of radioactive waste

International Nuclear Information System (INIS)

Vial, E.

2004-01-01

Recognition of the concept of responsibility to future generations seems, to imply the need to assume responsibility today for radioactive waste legacy of the past as well as for the waste that is currently being generated. However, this view of things, or more precisely this interpretation, is clouded by the lack of a clear definition of the concept of responsibility towards future generations. The concept has been used mainly in connection with long-lived radioactive wastes, which pose the greatest management problem as it so so far exceeds any human scale of reference. Consideration for future generations has to be a factor in the management of all types of radioactive waste, be it short, medium or long-lived waste or very low, low, intermediate or highly radioactive waste. As a general rule the concept of responsibility has made focus on long lived waste, whatever its level of radioactivity. The current alternatives for the management of radioactive waste may be: interim storage, final disposal, incineration, transmutation, to lower the radioactivity of the wastes. These different alternatives are discussed because they are not all genuine solutions and need to be deepened. (N.C.)

Management of disused long lived sealed radioactive sources (LLSRS)

International Nuclear Information System (INIS)

2003-06-01

The document provides advice the sealed source users and the national waste management organizations with the technical know-how on the management of disused and spent long lived sealed radioactive sources (LLSRS) and with the particular guidelines required for handling, conditioning for storage, and storage of these sources. The guidance is intended to assist in establishing compliance with the present standards, requirements, and adopted practices. It also provides background material for any possible technical assistance to developing countries and serves as a reference for technical staff involved with IAEA programmes on the subject. Because of the historic nature of many of the sources under this category and the lack of well developed technical procedures recognized on the international level, this publication can serve as a basis for establishing future handling and conditioning procedures. The LLSRS addressed in this publication are primarily those containing radionuclides having half-lives greater than 30 years. These sources may contain long lived alpha-emitters, mainly 238 Pu, 239 Pu, 237 Np, 241 Am, 226 Ra; beta-emitters: 14 C, and 63 Ni and could be neutron sources such as PuBe, RaBe and AmBe

The national plan of radioactive materials and wastes management. ASN's notice about the choice of the sites to be investigated in view of the setting up of a disposal facility for low activity/long living wastes

International Nuclear Information System (INIS)

2009-07-01

This short presentation, given by the national safety authority (ASN) at the meeting of July 1, 2009 of the high committee for the nuclear safety transparency and information (HCTISN), presents, first, the second French national plan of radioactive materials and wastes management (PNGMDR) with its main priorities, and then, the choice of the sites to survey in view of the setting up of a disposal facility for low level/long living wastes. The ASN expresses its opinion about the criteria retained by the ANDRA (the national agency of radioactive waste management) to select the most suitable sites. (J.S.)

Log live high activity radioactive wastes / Researches and results law of the 30 December 1991. Separation and transmutation of long lived radionuclides; Les dechets radioactifs a haute activite et a vie longue / recherches et resultats Loi du 30 decembre 1991. Separation et transmutation des radionucleides a vie longue

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-12-15

The law of the 30 December 1991 on the high activity long lived radioactive wastes reached the end. This synthesis final document presents the scientific and technological results, obtained still the end of 2005, on the separation and the transmutation of long lived radionuclides of high activity long lived radioactive wastes. It is organized in five chapters: a presentation of the context and the historical aspects, the researches, the objectives and the strategy of the axis 1, the researches results on the advanced separation, the researches results on the transmutation, the scenario of separation-transmutation and their environmental, technical and economical impacts. (A.L.B.)

ICRP guidance on radioactive waste disposal

International Nuclear Information System (INIS)

Cooper, J.R.

2002-01-01

The International Commission on Radiological Protection (ICRP) issued recommendations for a system of radiological protection in 1991 as the 1990 Recommendations. Guidance on the application of these recommendations in the general area of waste disposal was issued in 1997 as Publication 77 and guidance specific to disposal of solid long-lived radioactive waste was issued as Publication 81. This paper summarises ICRP guidance in radiological protection requirements for waste disposal concentrating on the ones of relevance to the geological disposal of solid radioactive waste. Suggestions are made for areas where further work is required to apply the ICRP guidance. (author)

Management of radioactive materials and wastes: status, stakes and perspectives

International Nuclear Information System (INIS)

Champion, Didier; Devin, Patrick; Tanguy, Loic; Bernard, Herve; Minon, Jean-Paul; Leclaire, Arnaud; Gilli, Ludivine; Lheureux, Yves; Pescatore, Claudio; Barbey, Pierre; Schneider, Thierry; Gay, Didier; Forest, Isabelle; Hemidy, Pierre-Yves; Baglan, Nicolas; Desnoyers, Bruno; Pieraccini, Michel; Poncet, Philippe; Seguin, Bertille; Calvez, Marianne; Leclerc, Elisabeth; Bancelin, Estelle; Fillion, Eric; Segura, Yannick; Vernaz, Etienne; Granier, Guy; De Preter, Peter; Petitfrere, Michael; Laye, Frederic; Nakamura, Takashi; Gin, Stephane; Lebaron-Jacobs, Laurence; Dinant, Sophie; Vacquier, Blandine; Crochon, Philippe; Griffault, Lise; Smith, Graham

2013-10-01

These technical days were organized by the Environment section of the French Society of Radiation Protection (SFRP). Time was given to some exchange about the societal aspects of radioactive waste management as well as about the legal context but the most part of the debates delt with the actual management modalities of the different types of wastes, both in France and in foreign countries, and with the related stakes, in particular in terms of impact. This document brings together the presentations (slides) of the following talks: - Contributions of radiation protection to the long-term safety management of radioactive wastes (Jean-Paul MINON - ONDRAF); - The national inventory of radioactive materials and wastes (Arnaud LECLAIRE - ANDRA); - The high activity, medium activity-long living wastes in debate - a co-building approach (ANCCLI/Clis of Bure/IRSN) to share stakes, enlighten, and develop thought (Ludivine GILLI - IRSN, Yves LHEUREUX - ANCCLI); - Social aspects of Radioactive Waste Management - The International Learning (Claudio PESCATORE - AEN/OCDE); - Citizens involvement and ACRO's point of view on radioactive wastes management (Pierre BARBEY - ACRO); - New CIPR recommendations about the geologic disposal of long-living radioactive wastes (Thierry SCHNEIDER - CEPN); - Overview of processes under the views of radiation protection principles (Didier GAY - IRSN); - The national plan of radioactive materials and wastes management (Loic TANGUY - ASN); - Joint convention on spent fuel management safety and on radioactive waste management safety - status and main stakes (Isabelle FOREST - ASN); - Transport of radioactive wastes (Bruno DESNOYERS - AREVA); - Optimisation and limitation of the environmental impacts of very-low level wastes - valorisation and processes selection (Michel PIERACCINI - EDF), Philippe PONCET - AREVA); - Management of hospital wastes - Example of Montpellier's University Regional Hospital (Bertille SEGUIN - CHRU de Montpellier); - Waste

Development of low-alkaline cement using pozzolans for geological disposal of long-lived radioactive waste

International Nuclear Information System (INIS)

Mihara, Morihiro; Iriya, Keishiro; Torii, Kazuyuki

2008-01-01

To reduce uncertainties in the safety assessment of the disposal system for long-lived radioactive waste, cement was developed which generates leachates with a lower pH than that of ordinary cement paste. This cement is termed 'low-alkaline cement'. Large amounts of pozzolans were used to produce the low-alkaline cement with ordinary Portland cement. Silica fume was found to be an effective pozzolans to reduce pH, but the needed large amount of silica fume reduced the workability of fresh concrete. Therefore, the authors also used fly ash with silica fume, to develop more workable low-alkaline cement, termed high-volume fly ash silica fume cement (HFSC). Two types of HFSC developed showed high compressive strength, smaller drying shrinkage and lower temperature rise than that of ordinary Portland cement. It was confirmed that HFSC could be used as self-compacting concrete. Therefore they can be applied as either structural or backfilling concrete in the disposal system. (author)

An integrated approach to the management of radioactive waste in Australia

International Nuclear Information System (INIS)

Woollett, S.M.

2002-01-01

This paper draws attention to the practices and progress in radioactive waste management in Australia. A National Repository for the disposal of low-level and short-lived intermediate- level radioactive waste and a National Store for the storage of long-lived intermediate-level radioactive waste are presently being established. This has necessitated considerable activity in addressing emerging issues in the management of radioactive waste. The Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) has a major role in developing an integrated approach to manage radioactive waste in Australia. This approach begins with the development of a radioactive waste management policy and identification of the issues in radioactive waste management requiring attention. ARPANSA is developing national standards and guidance documents for the safe and responsible management of waste prior to its acceptance at the National Repository or National Store. This contributes to the Agency's promotion of uniformity of radiation protection and nuclear safety policy and practices across Australia's Commonwealth, State and Territory jurisdictions. (author)

Nuclear incineration method for long life radioactive wastes

International Nuclear Information System (INIS)

Matsumoto, Takaaki; Uematsu, Kunihiko.

1987-01-01

Nuclear incineration method is the method of converting the long life radioactive nuclides in wastes to short life or stable nuclides by utilizing the nuclear reaction caused by radiation, unlike usual chemical incineration. By the nuclear incineration, the radioactivity of wastes increases in a short period, but the problems at the time of the disposal are reduced because of the decrease of long life radioactive nuclides. As the radiation used for the nuclear incineration, the neutron beam from fission and fusion reactors and accelerators, the proton beam and gamma ray from accelerators have been studied. The object of the nuclear incineration is actinide, Sr-90, Cs-137, I-129 and Tc-99. In particular, waste actinide emits alpha ray, and is strongly toxic, accordingly, the motive of attempting the nuclear incineration is strong. In Japan, about 24t of waste actinide will accumulate by 2000. The principle of the nuclear incineration, and the nuclear incineration using nuclear fission and fusion reactors and accelerators are described. The nuclear incineration using fission reactors was examined for the first time in 1972 in USA. It is most promising because it is feasible by the present technology without particular research and development. (Kako, I.)

Management of radioactive wastes

International Nuclear Information System (INIS)

2005-01-01

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

Disposal of radioactive waste: can long-term safety be evaluated

International Nuclear Information System (INIS)

1991-01-01

The long-term safety of any hazardous waste disposal system must be convincingly shown prior to its implementation. For radioactive wastes, safety assessments over timescales far beyond the normal horizon of social and technical planning have already been conducted in many countries. These assessments provide the principal means to investigate, quantify, and explain long-term safety of each selected disposal concept and site for the appropriate authorities and the public. Such assessments are based on four main elements: definition of the disposal system and its environment, identification of possible processes and events that may affect the integrity of the disposal system, quantification of the radiological impact by predictive modelling, and description of associated uncertainties. The NEA Radioactive Waste Management Committee and the IAEA International Radioactive Waste Management Advisory Committee have carefully examined the current scientific methods for safety assessments of radioactive waste disposal systems, as briefly summarized in this report. The Committees have also reviewed the experience now available from using safety assessment methods in many countries, for different disposal concepts and formations, and in the framework of both nationally and internationally conducted studies, as referenced in this report [fr

Strategy and programs of the research on high-level and long-living radioactive wastes (by right of article L542 of the environment code from December 30, 1991 law). Conjuncture document

International Nuclear Information System (INIS)

2003-01-01

This document gives, in a first part, a brief insight on the main results of the researches carried out in 2002 on the management of high-level and long-living radioactive wastes according to the three research ways defined by the December 30, 1991 law: separation-transmutation, disposal in deep geologic underground, wastes conditioning and storage. The second part of the document is an executive summary of the 2003 edition of the document 'strategy and programs of the researches on the management of high-level and long-living radioactive wastes - SPR 2003'. It presents the content of the different chapters: 1 - researches methodology and implementation of coordinated studies; 2 - researches status 10 years after the enforcement of the law; 3 - the main goals and steps to reach before the 2006 date-line; 4 - the description and analysis of the programs under consideration; 5 - the coordination between French programs; 6 - the international cooperation. (J.S.)

Long term governance for radioactive waste management. Final report of Cowan2 - work package 4

International Nuclear Information System (INIS)

Schneider, Th.; Schieber, C.; Lavele, S.

2006-12-01

This report aims at identifying key features for the long term governance of radioactive waste. It is proposed by the COWAN2 Work Package 4 the purpose of which was to identify, discuss and analyse the institutional, ethical, economic and legal considerations raised by long term radioactive waste storage or disposal on the three interrelated issues of: responsibility and ownership of radioactive waste on the long term, continuity of local dialogue between stakeholders and monitoring of radioactive waste management facilities, and compensation and sustainable development. The aim is also to propose guidelines in order to better address long term issues in decision-making processes and start long term governance

Long term governance for radioactive waste management. Final report of Cowan2 - work package 4

Energy Technology Data Exchange (ETDEWEB)

Schneider, Th.; Schieber, C.; Lavele, S.

2006-12-15

This report aims at identifying key features for the long term governance of radioactive waste. It is proposed by the COWAN2 Work Package 4 the purpose of which was to identify, discuss and analyse the institutional, ethical, economic and legal considerations raised by long term radioactive waste storage or disposal on the three interrelated issues of: responsibility and ownership of radioactive waste on the long term, continuity of local dialogue between stakeholders and monitoring of radioactive waste management facilities, and compensation and sustainable development. The aim is also to propose guidelines in order to better address long term issues in decision-making processes and start long term governance

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

Radioactive waste management for a radiologically contaminated hospitalized patient

International Nuclear Information System (INIS)

Pina Jomir, G.; Michel, X.; Lecompte, Y.; Chianea, N.; Cazoulat, A.

2015-01-01

Radioactive waste management in the post-accidental phase following caring for a radiologically contaminated patient in a hospital decontamination facility must be anticipated at a local level to be truly efficient, as the volume of waste could be substantial. This management must comply with the principles set out for radioactive as well as medical waste. The first step involves identification of radiologically contaminated waste based on radioactivity measurement for volume reduction. Then, the management depends on the longest radioactive half-life of contaminative radionuclides. For a half-life inferior to 100 days, wastes are stored for their radioactivity to decay for at least 10 periods before disposal like conventional medical waste. Long-lived radioactive waste management implies treatment of liquid waste and special handling for sorting and packaging before final elimination at the French National Agency for Radioactive Waste Management (ANDRA). Following this, highly specialized waste management skills, financial responsibility issues and detention of non-medical radioactive sources are questions raised by hospital radioactive waste management in the post-accidental phase. (authors)

Properties and long-term behaviour of bitumen and radioactive waste-bitumen mixtures

International Nuclear Information System (INIS)

Eschrich, H.

1980-10-01

Part I represents a survey of the properties and the long-term behaviour of pure bitumens and mixtures of bitumens with radioactive reactor and reprocessing wastes. This survey includes information on the origin, amounts, and composition of the various wastes considered for bituminization and the different waste bituminization techniques used. The influence of various factors on the quality of waste-bitumen products and on the radiological safety during transport, short- and long-term storage of the final products is described. Special consideration is given to the most important safety relevant factors associated to the use of bitumen as matrix material for radioactive wastes, such as leach-resistance, radiolysis, chemical and mechanical stability, combustibility, and microbial attack. Part II consists of a comprehensive bibliography on the bituminization of radioactive wastes, giving about 300 references to literature published from the beginning of the use of bitumen in radioactive waste management in 1960 until the beginning of 1979. Methods for the quality control of bituminous materials and some useful data are given in an annex. (author)

Treatment of short-lived radioactive wastes

International Nuclear Information System (INIS)

Yamaguchi, Chiri

1976-01-01

Recently short life nuclides have come to be utilized increasingly as diagnostic radioisotopes, and Tc-99m (half-life; 6.05 hours) and Ga-67 (half-life 7.79 hours) are replacing the most nuclides fomerly used in vivo test. Such development of radioactive products inevitably causes the rapid increase of their wastes. At present, the radioactive wastes produced by hospitals and university laboratories in Japan are collected by the Japan Radioisotope Association, and treated by the Japan Atomic Energy Research Institute. These wastes are divided into combustibles and incombustibles to store in the store house in the Japan Atomic Energy Research Institute. The present law in Japan contains the contradiction which treats the matter with one several millionth of radioactivity after decay same as the original radioactive matter. Thus solid must be stored permanently, while gas and liquid can be discharged after dilution. (Kobatake, H.)

Storage of long lived solid waste

International Nuclear Information System (INIS)

Ozarde, P.D.; Agarwal, K.; Gupta, R.K.; Gandhi, K.G.

2009-01-01

Long lived solid waste, generated during the fuel cycle mainly includes high level vitrified waste product, high level cladding hulls and low and intermediate level alpha wastes. These wastes require storage in specially designed engineered facilities before final disposal into deep geological repository. Since high-level vitrified waste contain heat generating radionuclides, the facility for their storage is designed for continuous cooling. High level cladding hulls undergo volume reduction by compaction and will be subsequently stored. (author)

No 2906. Proposal of law with the aim of organizing the durable management of radioactive wastes

International Nuclear Information System (INIS)

2006-02-01

This proposal of law is the result of a long thinking enriched by 15 years of reports preparation, workshops and exchange with foreign organizations in charge of radioactive waste management, mainly carried out in the framework of the December 30, 1991 law. This proposal of law deals with the following points: general conditions of the management of radioactive wastes, rules relative to the reprocessing of foreign wastes, national plan for the management of radioactive wastes, creation of a national commission of evaluation of the research work on the management of high-activity and long-lived radioactive wastes, creation of a funds for the financing of the research and the industrial management of radioactive wastes, the three complementary methods of waste management for the high-activity and long-lived wastes, date lines for the implementation of a first experimental reactor for transmutation, for a long duration surface or sub-surface storage facility and for a reversible disposal center, concerting obligation with people's representatives and creation of a public interest group, financial contribution allocated to territory authorities, radioactive wastes proprietorship, creation of a local information and follow-up committee for radioactive waste facilities, and eventual charge compensations relative to the implementation of this law. (J.S.)

Research on long-lived radioactive waste management: focus on environmental issues

International Nuclear Information System (INIS)

Andre Jehan, R.

1994-01-01

Studies are in progress on deep geologic media to examine their potential for retrievable or non retrievable nuclear waste disposal. The primary objective of site investigations and experiments for the coming years will be the development of underground laboratories (observation of host rocks and fluids). Geologic research programs are designed to investigate the potential for deep construction and the ability of the underground media to isolate radioelements from the biosphere. Researches covered the following topics: understanding the media likely to be found in underground laboratories using 3-D geologic modelling; predicting the materials behaviour under various mechanical, thermal and radiation loadings; describing fluid transfers through the geosphere and assessing radioactive materials transport and/or blockage by understanding the multiple geochemical mechanisms involved. The geologic and climatic long term behaviours are also taken into account. (author). 13 figs

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

Regulatory issues related to long-term storage and disposal of radioactive wastes in Kazakhstan

International Nuclear Information System (INIS)

Kim, A.; Romanenko, O.; Tazhibayeva, I.; Zhunussova, T.

2012-01-01

Full text: Reported material is a result of activity accomplished in the framework of cooperation program between Kazakhstan and Norway within 2009-2012. This work was divided into three distinctive parts, as follows: 1. Analysis of existing threats associated with radioactive wastes in the Republic of Kazakhstan. The objective of this part of the work was to reveal the most important threats in the sphere of radioactive waste management in the Republic of Kazakhstan, which require an increased regulatory attention. Threat assessment needed to identify: main radiological threats both for people who work with radioactive wastes and for population living near the radioactive waste storage places now and in the long term which require an increased regulatory attention; problems that need urgent and detailed analysis; and main problems in the realization of regulatory process in Kazakhstan including weakness in the regulatory and legal framework. Threat assessment analysis showed that in order to reduce the level of threats it was necessary to begin developing a national policy and strategy for radioactive waste management which need to be approved by the Government, to develop proposals for Radioactive Wastes new classification, including identification of relevant categories of Radioactive Wastes, as well as criteria for their disposal in accordance with IAEA recommendations and experience from other countries. 2. Development of new classification system for radioactive wastes in Kazakhstan. Following the results of threat assessment performed within the first stage, the objective of the second part of work was to develop a proposal to adopt a new Radioactive Wastes classification in Kazakhstan in accordance with the IAEA recommendations, including implementation of new categories, taking into account international experience and current situation in Kazakhstan. The result of this stage of work was a proposal for a new Radioactive Wastes classification and

Economic analysis of radioactive waste storage and disposal projects

International Nuclear Information System (INIS)

Kleinen, P.J.; Starnes, R.B.

1995-01-01

Radioactive waste storage and disposal efforts present challenging issues for cost and economic analyses. In particular, legal requirements for states and compact areas to develop radioactive waste disposal sites, combined with closure of some sites, have placed urgency on planning, locating, and constructing storage and disposal sites. Cost analyses of potential projects are important to the decision processes. Principal objectives for cost analyses for projects are to identify all activities, covering the entire project life cycle, and to develop costs for those activities using methods that allow direct comparisons between competing project alternatives. For radioactive waste projects, long project lives ranging from tens of years to 100 or more years must be considered. Alternative, and competing, technologies, designs, and operating plans must be evaluated. Thorough base cost estimates must be made for all project phases: planning, development, licensing/permitting, construction, operations, and maintenance, closure, and post-closure/institutional care. Economic analysis procedures need to accommodate the specific features of each project alternative and facilitate cost comparisons between differing alternatives. Economic analysis assumptions must be developed to address the unusually long project lives involved in radioactive waste projects

Moving Forward with Lessons Learned About Long-term Radioactive Waste Management

Energy Technology Data Exchange (ETDEWEB)

Atherton, Elizabeth; Dalton, John [UK Nirex Ltd., Harwell (United Kingdom)

2006-09-15

A range of lessons have been identified from previous attempts to implement long term radioactive waste management policy in the UK and internationally. Many of these relate to the way the decision-making process is undertaken and the fact that there needs to be an open, transparent process that enables continuous stakeholder involvement. Nirex believes that using the SEA and EIA frameworks will help to incorporate the lessons learned into the future decision-making process relating to long-term radioactive waste management.

Moving Forward with Lessons Learned About Long-term Radioactive Waste Management

International Nuclear Information System (INIS)

Atherton, Elizabeth; Dalton, John

2006-01-01

A range of lessons have been identified from previous attempts to implement long term radioactive waste management policy in the UK and internationally. Many of these relate to the way the decision-making process is undertaken and the fact that there needs to be an open, transparent process that enables continuous stakeholder involvement. Nirex believes that using the SEA and EIA frameworks will help to incorporate the lessons learned into the future decision-making process relating to long-term radioactive waste management

National radioactive waste repository draft EIS. 2 volumes

International Nuclear Information System (INIS)

2002-01-01

Most Australians benefit either directly or indirectly from the medical, industrial and scientific use of radioactive materials. This use produces a small amount of radioactive waste, including low level and short-lived intermediate level radioactive waste such as lightly contaminated soil, plastic, paper, laboratory equipment, smoke detectors, exit signs and gauges.This waste is temporarily stored at more than 100 urban and rural locations around Australia, much of it in buildings that were neither designed nor located for the long-term storage of radioactive material and that are nearing or have reached capacity. Storage locations include hospitals, research institutions, and industry and government stores. Storing such waste in many locations in non-purpose built facilities potentially poses greater risk to the environment and people than disposing of the material in a national, purpose-built repository where the material can be safely managed and monitored. The objectives of the national repository are to: 1. strengthen Australia's radioactive waste management arrangements by promoting the safe and environmentally sound management of low level and short-lived intermediate level radioactive waste 2. provide safe containment of these wastes until the radioactivity has decayed to background levels. To meet these objectives, it is proposed to construct a national near-surface repository at either the preferred site on the Woomera Prohibited Area (WPA) or either of the two nearby alternative sites. The facility is not intended for the disposal of radioactive ores from mining. A national store for long-lived intermediate level waste will not be co-located with the national repository, and would be subject to a separate environmental assessment process.One preferred and two alternative sites have been selected for the national repository, following an extensive site selection process. All three sites are located in northern South Australia in a region known as central

Experimental studies on behaviour of long-lived radionuclides in relation to deep-ocean disposal of nuclear waste

International Nuclear Information System (INIS)

Aston, S.R.; Fowler, S.W.

1984-01-01

Laboratory experiments have been carried out to investigate the interactions of long-lived radionuclides with sediments from present or potential deep-ocean radioactive waste disposal sites. The studies have been concerned with both geochemical aspects and sediment/animal radioecology. Examples drawn from the comparative behaviour of technetium and three transuranium nuclides (neptunium, plutonium and americium) are presented in relation to their uptake from sea water by deep-ocean sediments, ease of desorption and transfer from contaminated sediments to benthic invertebrates. The results provide information for the prediction of the behaviour of long-lived radionuclides in the deep-sea water/sediment boundary after their release from wastes. (author)

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

Fusion reactor radioactive waste management

International Nuclear Information System (INIS)

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

1976-01-01

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

Waste Disposal: Long-term Performance Studies for Radioactive Waste Disposal and Hydrogeological Modelling

Energy Technology Data Exchange (ETDEWEB)

Marivoet, J

2000-07-01

The main objectives of SCK-CEN's R and D programme on long-term performance studies are: (1) to develop a methodology and associated tools for assessing the long-term safety of geological disposal of all types of radioactive waste in clay formations and of the shallow-land burial of low-level waste; (2) to assess the performance and to identify the most influential elements of integrated repository systems for the disposal of radioactive waste; (3) to collect geological, piezometric and hydraulic data required for studying the hydrogeological system in north-eastern Belgium; (4) to develop a regional aquifer model for north-easter Belgium and to apply it in the performance assessments for the Mol site; (5) to test, verify and improve computer codes used in the performance assessment calculations of waste disposal concepts and contaminated sites (the computer codes simulate water flow and transport of radionuclides in engineered barriers, aquifers and contaminated sites). The scientific programme and achievements in 1999 are described.

Regulatory decision making in the presence of uncertainty in the context of the disposal of long lived radioactive wastes. Third report of the Working group on principles and criteria for radioactive waste disposal

International Nuclear Information System (INIS)

1997-10-01

Plans for disposing of radioactive wastes have raised a number of unique and mostly philosophical problems, mainly due to the very long time-scales which have to be considered. While there is general agreement on disposal concepts and on many aspects of a safety philosophy, consensus on a number of issues remains to be achieved. The IAEA established a subgroup under the International Radioactive Waste Management Advisory Committee (INWAC). The subgroup started its work in 1991 as the ''INWAC Subgroup on Principles and Criteria for Radioactive Waste Disposal''. With the reorganization in 1995 of IAEA senior advisory committees in the nuclear safety area, the title of the group was changed to ''Working Group on Principles and Criteria for Radioactive Waste Disposal''. The working group is intended to provide an open forum for: (1) the discussion and resolution of contentious issues, especially those with an international component, in the area of principles and criteria for safe disposal of waste; (2) the review and analysis of new ideas and concepts in the subject area; (3) establishing areas of consensus; (4) the consideration of issues related to safety principles and criteria in the IAEA's Radioactive Waste Safety Standards (RADWASS) programme; (5) the exchange of information on national safety criteria and policies for radioactive waste disposal. This is the third report of the working group and it deals with the subject of regulatory decision making under conditions of uncertainty which is a matter of concern with respect to disposal of radioactive wastes underground. 14 refs

Studies on separation, conversion and transmutation of long-living radionuclides. A contribution to advanced disposal of high-level radioactive wastes

International Nuclear Information System (INIS)

Modolo, Giuseppe

2014-01-01

The future role and acceptance of nuclear energy will be decisively determined by the safe operation of existing and future facilities and by convincing solutions for nuclear waste management. With respect to the long half-lives of some radionuclides (actinides and fission products) and the related question as to whether the release of radionuclides from a repository can be prevented over very long periods of time, alternatives to the direct disposal of spent nuclear fuels are discussed internationally. As a potential complementary solution, the technological option with partitioning and transmutation (P and T) is considered. This method separates and converts the long-lived radionuclides into stable, short-lived nuclides via neutron reactions in dedicated facilities. Against this background, the first main chapter of the present work looks at the chemical separation of actinides from high-level reprocessing wastes. In order to achieve a better understanding of the processes at the molecular level, basic investigations were also performed on separating actinides(III) via liquid-liquid or liquid-solid extraction. At the same time, reversible processes were developed and tested on the laboratory scale with the aid of mixer-settlers and centrifugal extractors. The subsequent chapter focuses on separating the long-lived fission product iodine-129 from radioactive wastes as well as from process effluents arising from reprocessing. As part of this work, different simple chemical and physical techniques were developed for complete recovery with respect to transmutation or conditioning in host matrices that are sufficiently stable for final storage. Its high mobility and radiological properties make iodine-129 relevant for the long-term safety assessment of final repositories. In addition, transmutation experiments on iodine-127/129 targets were performed using high-energy protons (145-2600 MeV). Due to the expected low cross sections (<100 mb), transmutation with protons

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.)

Complex containment design for long-term encapsulation of radioactive waste

International Nuclear Information System (INIS)

Sungaila, M.A.; San, E.K.W.; Palmeter, T.

2011-01-01

The Port Granby Project is part of the larger Port Hope Area Initiative (PHAI), a community-based program for the development and implementation of a safe, local, long-term management solution for historic low-level radioactive waste in the Municipalities of Port Hope and Clarington. The Port Granby Project includes the construction of a long-term low-level radioactive waste management facility, the transfer of the contaminated material to the new facility from existing storage, construction and operation of a new waste water treatment facility, and monitoring and maintenance of the facility for a period of several hundred years. A key component of the new long-term facility is a highly-engineered containment mound incorporating a composite base liner, a leachate collection system, and a multi-layer final cover system. Issues of interest include the details of the design, the evolution of the design, as well as the field quality assurance measures that will be specified to ensure that the design is correctly implemented. (author)

Final disposal of high-level radioactive waste and/or long-living nuclear waste in a clay formation in the Belgian-Dutch border region; Definitieve berging van hoogradioactief en/of langlevend kernafval in een kleiformatie in de Belgisch-Nederlandse grensstreek

Energy Technology Data Exchange (ETDEWEB)

Weyns, W.

2010-10-15

Recently, the Belgian organization NIRAS presented its 'Draft Waste Plan'. In this plan NIRAS chooses clay as the reference option for final geological disposal of high-level radioactive and/or long-living nuclear waste (b and C waste). The author presents an overview of the current state of affairs in scientific research on underground storage of radioactive waste in Belgian clay layers. [Dutch] Recent presenteerde het Belgische NIRAS het 'Ontwerp Afvalplan'. In dit plan kiest NIRAS als referentieoptie voor definitieve geologische berging van hoogradioactief en/of langlevend kernafval (B- en C-afval) in klei. De auteur geeft een overzicht van de stand van zaken van wetenschappelijk onderzoek naar ondergrondse opslag van radioactief afval in Belgische kleilagen.

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

Research of the multibarrier system for an underground deposition of radioactive wastes

Directory of Open Access Journals (Sweden)

Marian Šofranko

2007-01-01

Full Text Available The paper deals in brief with research problems of multiple protection barrier systems for an underground storage of highly radioactive waste in connection with the problem of resolving a definite liquidation of this waste. This problem has a worlwide importance and is comprehensively investigated, evaluated and resolved in many well accepted research centers. Present the experts agree, that the most suitable way of the long-lived radioactive wastes liquidation is their storage into suitable underground geological formations. The core insulation of radioactive wastes from the biosphere for an extremly long time can be achieved by using a technical isolation barrier in combination with an appropriate rock mass.

A consideration of retrievability in geologic disposal of radioactive wastes

International Nuclear Information System (INIS)

Sasaki, Noriaki

2001-12-01

Geologic disposal cannot be implemented based only on the consensus of the engaged technical community, and needs the wide social agreement and confidence for it. This is now a common understanding in many countries. Under this kind of recognition, the concept of retrievability in geologic disposal of radioactive wastes has been rapidly interested in recent years and has being discussed in several European countries. For example, EC has cooperated the concerted action on the retrievability of long-lived radioactive waste with the joining of nine countries, and the expert group on disposal concepts for radioactive waste (EKRA) set up by the Swiss government has presented its findings on the new concept of the long-lived radioactive waste management considering the retrievability. The OECD/NEA has also discussed on this issue and published the documents. There are some countries where the legislation requires the retrievability. This paper briefly summarizes the important findings and recommendations on the concept of retrievability, as the results of review of some interesting documents from European countries, for the purpose of reflecting to the research and development of geologic disposal in Japan. (author)

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

International Nuclear Information System (INIS)

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

2016-01-01

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

Radioactive waste management in France

International Nuclear Information System (INIS)

Faussat, A.

1988-01-01

Solutions for radioactive waste management are already in existence and applied on an industrial scale for short-lived wastes. France has acquired an aknowledged expertise on the international level and several foreign contemporaries are interested in the relevant techniques developed. An intensive international cooperation has allowed to define bases for an underground deep repository for long-lived wastes. It is therefore important to choose a site which meets the expected storage conditions. This development work has been started in several countries in a similar way and which should be completed by the beginning of the next century. An 'open channel' with the public about this emotional topic can smooth the way for solutions by which mankind can master its technological challenges

Radioactive waste and the back part of fuel cycle of nuclear installations in Slovakia

International Nuclear Information System (INIS)

Koprda, V.

2004-01-01

This article is devoted to radioactive waste (RAW) management, an integrated system starting with collection and sorting of RAW through its storage, treatment, conditioning, handling and transport up to its disposal. Some notes will touch also the near surface depository of low level and intermediate level radioactive waste in Mochovce, and the long-term storage of waste improper for such type of disposal, and also some words will be addressed to the development and research of a deep geological depository for disposal spent fuel from nuclear power plant and long-lived radioactive waste. (author)

The radioactive waste management in France

International Nuclear Information System (INIS)

Lacoste, A.C.; Bodenez, Ph.; Jacq, F.; Grevoz, A.; Bataille, Ch.; Birraux, C.; Vicent, C.; Locufier, A.; Bodenez, Ph.; Dupraz, B.; Leroy, D.; Granger, S.; Taniguchi, T.; Louvat, D.; Sene, M.; Sene, R.; Bonnemains, J.

2005-01-01

The actors involved in research will report on fourteen years work in their respective fields: ANDRA on its research on deep geological formation repositories and the Cea on its research into partitioning and transmutation, and packaging and long term storage, will submit their preliminary reports in June 2005. The debate surrounding high-level long-lived waste must not draw a veil over the existence of the other types of radioactive waste whose levels are much lower but representing volumes which are much greater. It is the reason why A.S.N. oversees the drafting of the National Plan for Radioactive Waste Management and recoverable Materials initiated two years ago by the Ministry for ecology and sustainable development following a request from O.P.E.C.S.T. (Parliament Office for Scientific and Technology Choices Assessment). The parliament has to decide on the matter within the deadline of 2006. (N.C.)

Maintenance of records for radioactive waste disposal

International Nuclear Information System (INIS)

1999-07-01

The safety of the radioactive waste disposal concepts does not rely on long term institutional arrangements. However, future generations may need information related to repositories and the wastes confined in them. The potentially needed information therefore has to be identified and collected. A suitable system for the preservation of that information needs to be created as a part of the disposal concept beginning with the planning phase. The IAEA has prepared this technical report to respond to the needs of Member States having repositories or involved in or considering the development of repositories. In many countries policies and systems for record keeping and maintenance of information related to disposal are the subjects of current interest. This report describes the requirements for presenting information about repositories for radioactive waste including long lived and transuranic waste and spent fuel if it is declared as a waste. The report discussed topics of identification, transfer and long term retention of high level information pertaining to the repository in a records management system (RMS) for retrieval if it becomes necessary in the future

Stepwise approach to decision making for long-term radioactive waste management. Experience, issues and guiding principles

International Nuclear Information System (INIS)

2004-01-01

Radioactive waste exists as a result of both past and current practices. One of the most challenging tasks is the management of long-lived waste that must be isolated from the human environment for many thousands, or even hundreds of thousands, of years. Although significant technical progress has been made in developing management schemes that, according to technical experts, would ensure long-term safety (e.g. engineered geologic disposal), the rate of progress towards implementing such solutions has been slower than expected. The contrast between expected and observed rates may be partly attributable to an earlier technical optimism. More significant, however, are the setbacks, which have arisen mainly from an underestimation of the societal and political dimensions. In long-term radioactive waste management, consideration is increasingly being given to concepts such as stepwise decision making and adaptive staging in which the public, and especially the local public, are to be meaningfully involved in the review and planning of developments. The key feature of these concepts is development by steps or stages that are reversible, within the limits of practicability. This is designed to provide reassurance that decisions can be reversed if experience shows them to have adverse or unwanted effects. A stepwise approach to decision making has thus come to the fore as being of value in advancing long-term radioactive waste management solutions in a societally acceptable manner. Despite its early identification within the radioactive waste management community as an important means for reaching solutions and decisions in which there is broad-based confidence, the bases for and application of stepwise decision making has not been widely reviewed. Guiding principles of any such process are still being formulated, its roots in empirical social science research have not been fully reviewed, nor the difficulties of its implementation analysed. The report reviews current

PNGMDR - Characterisation of intermediate-level long-lived wastes

International Nuclear Information System (INIS)

2014-12-01

This document presents the status of the characterization of intermediate-level long-lived wastes which are warehoused on exploited EDF sites or which will be produced during the deconstruction of first-generation reactors. It addresses aspects related to characterisation and packaging of wastes produced before 2015. More specifically, it addresses aspects related to contamination and to activation. Contamination is assessed by measurements whereas activation assessment is based on numerical simulations associated with measurements performed during parcel production. After having mentioned the concerned reactors, the document presents the methodology adopted for these assessments, and reports the progress status of the characterization process for these intermediate-level long-lived wastes

Technological demonstrators. Researches and studies on the storage and disposal of long living intermediate level and high level radioactive wastes; Les demonstrateurs technologiques. Recherches et etudes sur le stockage et l'entreposage des dechets de haute activite et de moyenne activite a vie longue

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

This brochure presents the technological demonstrators made by the French national agency of radioactive wastes (ANDRA) and exhibited at Limay (Yvelines, France). These demonstrators, built at scale 1, have been an essential support to the establishment of the 'Dossier 2005' which demonstrates the feasibility of a reversible disposal of long living-intermediate level and high level radioactive wastes in the Callovo-Oxfordian argillite of Meuse-Haute Marne. Two type of demonstrators were built: demonstrators of storage containers for long living-intermediate level wastes and for spent fuels, and dynamic demonstrators for containers handling. This brochure presents these different demonstrators, their characteristics and the results of their tests. (J.S.)

Radioactive waste generated from JAERI partitioning-transmutation cycle system

Energy Technology Data Exchange (ETDEWEB)

Shinichi, Nakayama; Yasuji, Morita; Kenji, Nishihara [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

2001-07-01

Production of lower-level radioactive wastes, as well as the reduction in radioactivity of HLW, is an important performance indicator in assessing the viability of a partitioning-transmutation system. We have begun to identify the chemical compositions and to quantify the amounts of radioactive wastes that may be generated by JAERI processes. Long-lived radionuclides such as {sup 14}C and {sup 59}Ni and spallation products of Pb-Bi coolants are added to the existing inventory of these nuclides that are generated in the current fuel cycle. Spent salts of KCl-LiCl, which is not generated from the current fuel cycle, will be introduced as a waste. (author)

Radioactive Wastes Generated From JAERI Partitioning-Transmutation Fuel Cycle

International Nuclear Information System (INIS)

Nakayama, Shinichi; Morita, Yasuji; Nishihara, Kenji

2003-01-01

Production of lower-level radioactive wastes, as well as the reduction in radioactivity of HLW, is an important performance indicator in assessing the viability of a partitioning-transmutation system. We have begun to identify the chemical compositions and to quantify the amounts of radioactive wastes that may be generated by JAERI's processes. Long-lived radionuclides such as 14 C and 59 Ni and spallation products of Pb-Bi coolants are added to the existing inventory of these nuclides that are generated in the current fuel cycle. Spent salts of KCl-LiCl, which is not generated from the current fuel cycle, will be introduced as a waste. (authors)

Safety Aspects in Radioactive Waste Management

Directory of Open Access Journals (Sweden)

Peter W. Brennecke

2007-01-01

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

The regulatory function in radioactive waste management

International Nuclear Information System (INIS)

Duncan, A.; Pescatore, C.

2008-01-01

Allan Duncan, expert to NEA and former Chief Inspector for Pollution (United Kingdom), elaborated on the regulatory function in the domain of radioactive waste management. The preparation of a document and a brochure on the subject has been one of the main tasks of the Regulators' Forum since its creation in 2001. He stressed that management of NORM waste was generally subject to different standards than similar radioactive waste from a nuclear source, for no obvious reason than that of public perception. He also pointed out the large number of 'regulatory bodies' involved in the regulation of radioactive waste management facilities and particularly geological disposal facilities, and their links to the Government. He gave the example of the United Kingdom. He stressed the fact that, since there will not be continuous control, licensing of geological disposal is an act of trust in the regulatory system. A. Duncan gave the position of two Commissions in England on deep geological disposal. The UK Sustainable Development Commission says, 'it is impossible to guarantee safety over long-term disposal of (nuclear) waste' which implies that nuclear fission power should be shut down; CoRWM, the Committee on Radioactive Waste Management, recommends instead geological disposal for existing wastes as a broadly acceptable solution. As a concluding remark A. Duncan focused the attention on the general question of what current society needs to do in order to meet its obligations to future generations with respect to disposal of long-lived wastes. (authors)

The disposal of radioactive waste

International Nuclear Information System (INIS)

Ormai, P.

2006-01-01

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

Long-term storage of radioactive waste: IAEA perspectives on safety and sustainability

International Nuclear Information System (INIS)

Rowat, J.H.; Louvat, D.; Metcalf, P.E.

2006-01-01

As the amounts of radioactive waste in surface storage have increased, concern has grown over the safety and sustainability of storage in the long term. In response to increasing concerns, the International Atomic Energy Agency (IAEA) has included an action to address the safety implications of the long-term storage (LTS) of radioactive waste in its action plan for waste safety; the action plan was endorsed by the IAEA's Member States in 2001. In 2003, the IAEA published a position paper on the safety and sustainability of LTS as part fulfilment of the action in question. A key theme of the position paper is the contrast of safety and sustainability implications of LTS with those of disposal. The present paper provides a summary of the position paper, describes current IAEA activities that deal with the subject of LTS, and discusses findings from the 2004 Cordoba symposium on disposal of low activity radioactive waste that pertain to LTS. (author)

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)

Public debate on radioactive wastes; Le debat public sur les dechets radioactifs

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

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

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

Development of characterization methods applied to radioactive wastes and waste packages

International Nuclear Information System (INIS)

Guy, C.; Bienvenu, Ph.; Comte, J.; Excoffier, E.; Dodi, A.; Gal, O.; Gmar, M.; Jeanneau, F.; Poumarede, B.; Tola, F.; Moulin, V.; Jallu, F.; Lyoussi, A.; Ma, J.L.; Oriol, L.; Passard, Ch.; Perot, B.; Pettier, J.L.; Raoux, A.C.; Thierry, R.

2004-01-01

This document is a compilation of R and D studies carried out in the framework of the axis 3 of the December 1991 law about the conditioning and storage of high-level and long lived radioactive wastes and waste packages, and relative to the methods of characterization of these wastes. This R and D work has permitted to implement and qualify new methods (characterization of long-lived radioelements, high energy imaging..) and also to improve the existing methods by lowering detection limits and reducing uncertainties of measured data. This document is the result of the scientific production of several CEA laboratories that use complementary techniques: destructive methods and radiochemical analyses, photo-fission and active photonic interrogation, high energy imaging systems, neutron interrogation, gamma spectroscopy and active and passive imaging techniques. (J.S.)

Long lived isotopes in the Chernobyl radioactive cloud at Cracow

International Nuclear Information System (INIS)

Mietelski, J.W.; Broda, R.; Sieniawski, J.

1988-01-01

The analysis of the residual gamma radioactivity in the air filters exposed during the passage of the Chernobyl radioactive cloud over Cracow area gave data on variation in time of the relative contribution of long lived radioisotopes. Conclusions on transport properties of some elements are deduced from the obtained results. 10 refs., 5 figs. (author)

Expertise on the provision of evidence with respect to Nagra's disposal concept for spent fuel assemblies, vitrified high-level radioactive waste as well as for long-living intermediate-level wastes (Opalinus clay project)

International Nuclear Information System (INIS)

2005-08-01

Mankind has been living in a field of natural radiation; in Switzerland, the natural dose is around 3 mSv per year. It can be assumed that an artificial dose smaller than the natural one is harmless and can therefore be tolerated. However, nuclear power plants, medicine, industry and research produce radioactive wastes whose radioactivity is mostly higher than the natural level. These wastes must therefore be concentrated and enclosed until the decay reduces the dose rate to a harmless level. For this, it is foreseen that the radioactive wastes will be disposed of in deep-lying geological strata. The enclosure must be guarantied in such a way that, at any time, the radiation suffered by mankind and environment due to the radioactive wastes stays under the statutory limit of 1 mSv/a. The judgement of the quality of the deep underground repository is divided into 3 chapters: a) based on the geological and hydro-geological properties of the host rock, the proof of safety shows that the chosen repository site is safe for the long term; b) the proof of site guaranties that the repository needed can be built in the chosen host rock; c) the proof of implementation demonstrates that the repository can be built with the actual technical means proposed. The forecast for the development of the safety of the repository in the long term is fairly inaccurate, the most difficult factor being the developments in mankind's way of life. Therefore, conservative assumptions must be taken into account to cover even the most unlikely cases. The former project 'Gewaehr' presented by the National Co-operative for the Disposal of Nuclear Wastes (NAGRA) in 1978 was based on crystalline rock; it was rejected because it was not possible to find a sufficiently large area without geologic faults for the repository. In new investigations, NAGRA found a suitable layer of Opalinus clay in Zurich's Weinland. In the neighbourhood of the layer discovered, there are neither noticeable beds of other

The management of radioactive waste, as practised and planned

International Nuclear Information System (INIS)

Bjurstroem, Sten

1991-01-01

The development of radioactive waste management has recently been evaluated and discussed by an expert group organized by the Uranium Institute. The report of the group describes the knowledge obtained through research and development, and the technical and administrative systems in operation or planned for the various kinds of waste within the nuclear fuel cycle. It also demonstrates the wide international concensus that methods are presently available to design and site repositories for long-term safe disposal of long-lived wastes and to evaluate the radiological impacts of waste disposal. (author)

α and long-lived βγ waste source term. A first generation model for a deep cemented waste repository

International Nuclear Information System (INIS)

Lovera, P.; Mangin, J.P.; Jorda, M.; Lewi, J.

1987-01-01

According to the normal scenario of radioactivity release to the biosphere, only long-lived nuclides are able to migrate significantly to the surface. A first generation model, concerning a cemented waste of hulls and ends deeply disposed of in a granitic medium is in progress at CEA. Two nuclides have been selected: 237-Neptunium (as a reference of α emitters) and 135-Cesium (as a reference of long-lived β emitters). Attributing the long term activity to these both nuclides leads to a model which is conservative beyond ca. 150000 years. Principal difficulties arise from physico-chemical behaviour of Neptunium in aqueous phase, and from non-linear Cesium adsorption on various media. Condiment code (versions 2 and 3), which is developed parallely to the present model is conceived to take account for these phenomena

Progress on the national low level radioactive waste repository and national intermediate level waste store

International Nuclear Information System (INIS)

Perkins, C.

2001-01-01

Over the last few years, significant progress has been made towards siting national, purpose-built facilities for Australian radioactive waste. In 2001, after an eight year search, a preferred site and two alternatives were identified in central-north South Australia for a near-surface repository for Australian low level (low level and short-lived intermediate level) radioactive waste. Site 52a at Everts Field West on the Woomera Prohibited Area was selected as the preferred site as it performs best against the selection criteria, particularly with respect to geology, ground water, transport and security. Two alternative sites, Site 45a and Site 40a, east of the Woomera-Roxby Downs Road, were also found to be highly suitable for the siting of the national repository. A project has commenced to site a national store for intermediate (long-lived intermediate level) radioactive waste on Commonwealth land for waste produced by Commonwealth agencies. Public input has been sought on relevant selection criteria

Regulatory approaches in the United States of America for safe management and disposal of long-lived radionuclides

International Nuclear Information System (INIS)

Greeves, J.T.; Bell, M.J.; Nelson, R.A.

1998-01-01

Regulation of the safe management and disposal of commercial, man-made, long-lived radioactive wastes in the United States is the responsibility of the US Nuclear Regulatory Commission (NRC). In some instances, state regulatory authorities have entered into agreements with the NRC to exercise regulatory authority over management and disposal of low-level radioactive wastes and uranium mill tailings within their borders. The legal and regulatory framework employed to achieve safe management and disposal of long-lived radioactive wastes in the US regulatory system is quite detailed, and in many cases the requirements are considerably prescriptive. The NRC has undertaken an initiative to move in the direction of adopting risk-informed, performance-based and risk-informed, less-prescriptive regulations. The current status and future direction of the legal and regulatory framework for management and disposal of commercial long-lived radioactive waste in the US is described. (author)

Low-level radioactive waste management handbook series: Low-level radioactive waste management in medical and biomedical research institutions

International Nuclear Information System (INIS)

1987-03-01

Development of this handbook began in 1982 at the request of the Radhealth Branch of the California Department of Health Services. California Assembly Bill 1513 directed the DHS to ''evaluate the technical and economic feasibility of (1) reducing the volume, reactivity, and chemical and radioactive hazard of (low-level radioactive) waste and (2) substituting nonradioactive or short-lived radioactive materials for those radionuclides which require long-term isolation from the environment. A contract awarded to the University of California at Irvine-UCI (California Std. Agreement 79902), to develop a document focusing on methods for decreasing low-level radioactive waste (LLW) generation in institutions was a result of that directive. In early 1985, the US Department of Energy, through EG and G Idaho, Inc., contracted with UCI to expand, update, and revise the California text for national release

Reversibility and retrievability in geologic disposal of radioactive waste. A new Nea report

International Nuclear Information System (INIS)

Brown, P.A.; Pascatore, C.; Sumerling, T.

2001-01-01

Radioactive waste needs to be managed responsibly to ensure public safety and the protection of the environment, as well as security from unauthorized interference, now and in the future. One of the most challenging tasks is the management of long-lived radioactive waste that must be isolated from the human environment for many thousands, or even hundreds of thousands, of years. There is a consensus among the engaged technical community that engineered geologic disposal provides a safe and ethical method for the long term management of such waste. This method is also cited in the national policies of several countries as either a promising or appropriate method for dealing with long-lived radioactive waste. Engineered geologic disposal means emplacement of waste in repositories constructed deep underground in suitable geologic media. Thus the waste is contained, and safety assured by passive barriers with multiple safety functions, so that there is no need for any further actions by future generations. Primary principles of the engineered geologic disposal concept are that waste will only be emplaced in a repository when there is high confidence in the ultimate long-term safety, and that the long-term safety must not rely on actions following the closure of the repository. This does not mean, however, that actions cannot be taken. Most repository development programmes include the possibility of post-closure activities for security and monitoring purposes. (authors)

Proceedings of the public debate on the general options of management of high and intermediate activity and long-lived radioactive wastes; Compte-rendu du debat public sur les options generales en matiere de gestion des dechets radioactifs de haute activite et de moyenne activite a vie longue

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-01-15

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprised 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is a summary of the main questions tackled during this debate from its preparation to its closing meeting and dealing with: the acceptation of the debate, the progress of the debate, the socio-technical problem of gathering the different points to be debated with respect to the different areas in concern, the general questions about the overall nuclear wastes and materials (radioactivity, health, radioprotection, management, reprocessing, control, actors organization, knowledge sharing, perenniality of the financing), the specific questions about long-lived wastes (inventory, separation-transmutation feasibility, nuclear energy and energy policy, management solutions, storage and geologic disposal feasibility, impact of debates on the 2006 law, long-lived waste territories), the conclusions for the 2006 law: mastering the overall nuclear wastes and materials and step-by-step building up of a solution for long-lived wastes (difficulties, lessons learnt from foreign experience, first draft of the 2006 law). Some opinions expressed by some participants about these proposals conclude

Disposal of high level and long lived radioactive waste in deep geological formation

International Nuclear Information System (INIS)

Niezborala, J.M.; Hoorelbeke, J.M.

2000-01-01

The status of ANDRA's research program on high level and long lived waste corresponds to the start of construction of the Meuse/Haute-Marne Underground Research Laboratory in an argillite layer, as well as to the selection in 1999 of preliminary disposal concepts corresponding to this layer. The paper describes the preliminary concepts dealing with transuranic waste, high level vitrified waste and potentially disposed spent fuel. Provision is made for a high level of flexibility, in particular with regard to options of reversibility of the disposal process, and to potential evolutions of the waste inventory. These concepts were selected for research purpose to assess by the year 2006 the feasibility of a potential repository, with.respect in particular to safety rules. The paper mentions the research targets of the program aiming at answering major scientific and technological questions raised by the concepts. The program includes the fitting and validation of the modelling, on the basis in particular of the experimental work to be carried out in the Underground Research Laboratory, making it possible to dimension the disposal concepts and to assess their safety. (authors)

Radioactive waste management and regulation

International Nuclear Information System (INIS)

Willrich, M.

1976-12-01

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

Planning and Design Considerations for Geological Repository Programmes of Radioactive Waste

International Nuclear Information System (INIS)

2014-11-01

Disposal in a geological repository is the generally accepted solution for the long term management of high level and/or long lived radioactive wastes, in line with the general principles defined in the IAEA Safety Fundamentals. This publication presents practical information on the way a geological repository programme for radioactive waste could be defined and planned, with special attention to all aspects having an impact on the timing. Country specific examples for repository development phases are provided, based on actual experiences from Member States

Safety analysis of geologic containment of long life radioactive wastes. Critical assessment of existing methods and proposition of prospective approach

International Nuclear Information System (INIS)

Masure, P.; Gedefroy, P.; Imauven, C.

1983-01-01

Existing methods of risk analysis applied to disposal of long-lived radioactive waste in geologic formations are rewieved. A prospective analysis method for containment performances is proposed, deduced in the burial system from the combination of interaction between wastes, repository, host rock, surrounding geosphere, of natural evolution of each component of the system, sudden or chance events that could break waste containment. The method is based on the elaboration of four basic schemes graded in difficulties to facilitate comparisons

Perspectives concerning radioactive waste management

International Nuclear Information System (INIS)

Noynaert, L.

2013-01-01

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

Feasibility of space disposal of radioactive nuclear waste. 2: Technical summary

Science.gov (United States)

1974-01-01

The feasibility of transporting radioactive waste produced in the process of generating electricity in nuclear powerplants into space for ultimate disposal was investigated at the request of the AEC as a NASA in-house effort. The investigation is part of a broad AEC study of methods for long-term storage or disposal of radioactive waste. The results of the study indicate that transporting specific radioactive wastes, particularly the actinides with very long half-lives, into space using the space shuttle/tug as the launch system, appears feasible from the engineering and safety viewpoints. The space transportation costs for ejecting the actinides out of the solar system would represent less than a 5-percent increase in the average consumer's electric bill.

Integrated system for long-term radioactive waste management in the UK

International Nuclear Information System (INIS)

Dalton, J.; Wisbey, S.

2003-01-01

Since the failure of Nirex application to build a Rock Characterisation Facility near Sellafield in 1997, Nirex has been applying lessons learnt from that failure. Some of the issues involved are generic and relate to the process by which legitimate authority can be gained for government policy development, the structure of the nuclear industry and the behaviour of institutions. Transparency must be central to the culture of organisations attempting to win public acceptance. In the UK, the Department for Environment, Food and Rural Affairs (DEFRA) have started a consultation process - stage one completed in March 2002 - to consult about the safe management of radioactive waste. Nirex has modified its approach to long-term waste management, using a concept of phased (stepwise and reversible) geological disposal. Nirex also provides waste producers with advice on, and endorsement of, the packaging and transport of wastes. Through these examples, this paper will demonstrate how Nirex is providing an integrated approach to the long-term management of radioactive wastes in the UK. (orig.)

Geological aspects of the deep disposal of radioactive waste

International Nuclear Information System (INIS)

McEwen, T.J.

1998-01-01

Various environments have been selected throughout the world for the potential deep disposal of long-lived radioactive waste. The selection of these environments has been carried out using a variety of methods, some of them more logical and defensible than others. The 'raison d'etre' for their selection also varies from country to country. Important lessons have been learnt from the site selection programmes, the site characterisation activities and the accompanying performance assessments that have been carried out concerning the suitability of geological environments for the disposal of long-lived waste. These lessons are the subject of this paper. 24 refs

Radioactive waste management

International Nuclear Information System (INIS)

1984-07-01

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

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)

Disposal of radioactive waste from nuclear research facilities

CERN Document Server

Maxeiner, H; Kolbe, E

2003-01-01

Swiss radioactive wastes originate from nuclear power plants (NPP) and from medicine (e.g. radiation sources), industry (e.g. fire detectors) and research (e.g. CERN, PSI). Their conditioning, characterisation and documentation has to meet the demands given by the Swiss regulatory authorities including all information needed for a safe disposal in future repositories. For NPP wastes, arisings as well as the processes responsible for the buildup of short and long lived radionuclides are well known, and the conditioning procedures are established. The radiological inventories are determined on a routinely basis using a combined system of measurements and calculational programs. For waste from research, the situation is more complicated. The wide spectrum of different installations combined with a poorly known history of primary and secondary radiation results in heterogeneous waste sorts with radiological inventories quite different from NPP waste and difficult to measure long lived radionuclides. In order to c...

Transmutation of long-lived nuclear waste

International Nuclear Information System (INIS)

Abrahams, K.

1992-10-01

Nuclear waste disposal in geologically stable repositories is considered to be safe and effective, and the assumptions, which lead to very long term predictions seem to be satisfied. As possibilities to perturb repositories, can never be entirely excluded, it could be an attractive option to reduce the toxicity of waste by supplementing the uranium-plutonium cycle with minor actinide burning cycles. In this option the amount of mining waste is limited at the same time because uranium is used economically. If requests for reduction of long-lived actinide waste would result in much higher costs for nuclear energy, the innovative thorium-uranium cycle might become competitive. It is of vital interest that efforts are now being internationalized in networks to make proper use of experience from past civil and military programs. Visions for almost pollution-free energy production could arise if well prepared minds are concentrated on this issue. (author). 5 refs., 2 figs., 1 tab

1. round table - Nuclear wastes and radioactive materials. 2. round table - risks linked with nuclear wastes and materials. 3. round table - the problem of long-term management of medium-high activity and long lived wastes. The process defined by the 1991 law; 1. table ronde - dechets nucleaires et matieres radioactives. 2. table ronde - Les risques des dechets et matieres nucleaires. 3. table ronde - Le probleme de la gestion a long terme des dechets a MA/HAVL. Le processus defini par la loi de 1991

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprises 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the synthesis of the debates of the first round table of Paris about the problems raised by nuclear wastes in the case of the geologic disposal option. Four families of questions have been tackled: 1 - the exhaustiveness of ANDRA's inventory, the solutions foreseen for the different types of wastes; 2 - the high-medium activity wastes and their processing; 3 - the management of non-reprocessed spent MOX fuels; 4 - the safety and security standards used and their establishment. Four presentations are attached to these proceedings and deal with: the measured and estimated inventory of all radioactive wastes; the inventory and management of radioactive wastes and the place of citizens; the point of view of the nuclear safety authority; conditioning and storage. (J.S.)

Greater confinement disposal of radioactive wastes

International Nuclear Information System (INIS)

Trevorrow, L.E.; Gilbert, T.L.; Luner, C.; Merry-Libby, P.A.; Meshkov, N.K.; Yu, C.

1985-01-01

Low-level radioactive waste (LLW) includes a broad spectrum of different radionuclide concentrations, half-lives, and hazards. Standard shallow-land burial practice can provide adequate protection of public health and safety for most LLW. A small volume fraction (approx. 1%) containing most of the activity inventory (approx. 90%) requires specific measures known as greater-confinement disposal (GCD). Different site characteristics and different waste characteristics - such as high radionuclide concentrations, long radionuclide half-lives, high radionuclide mobility, and physical or chemical characteristics that present exceptional hazards - lead to different GCD facility design requirements. Facility design alternatives considered for GCD include the augered shaft, deep trench, engineered structure, hydrofracture, improved waste form, and high-integrity container. Selection of an appropriate design must also consider the interplay between basic risk limits for protection of public health and safety, performance characteristics and objectives, costs, waste-acceptance criteria, waste characteristics, and site characteristics

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.)

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)

Context of the long-term management of low-level short-lived waste

International Nuclear Information System (INIS)

Hooft, E.

2004-01-01

Until the international moratorium of 1983, Belgium relied on sea disposal for its low-level waste. Since then, ONDRAF/NIRAS, the Belgian radioactive waste management agency, has launched studies to look for land-based solutions. These studies, which are still going on, have gone through various phases. The sometimes harsh reactions in public opinion and the recommendations of independent experts, however, progressively led ONDRAF/NIRAS to question its work methodology. On 16 January 1998 was a milestone in Belgian's nuclear waste management. On that day, the Belgian federal government opted for a final, or potentially final, solution for the long-term management of short-lived, low-level radioactive waste, a solution that also had to be progressive, flexible, and reversible. At the same time, the government entrusted new missions to ONDRAF/NIRAS in particular that of developing methods to enable the integration of final repository project proposals at a local level and restricted the number of potential sites for final disposal to the four existing nuclear sites in Belgium and to possibly interested local districts. The government's decision of 16 January 1998 forced ONDRAF/NIRAS to change its strategy. The agency set up a new work programme and worked out an innovative methodology. This new methodology aims to generate, at the level of the interested towns and villages, draft projects for a final repository supported by a wide public consensus. (author)

Studies for the storage of high level and long living radioactive wastes

International Nuclear Information System (INIS)

2001-01-01

This synthesis presents the studies and main results of the year 1999 obtained in the framework of the second axis of the 1991 law about the feasibility study of deep underground radioactive waste repositories. It precises also the French and international context in which researches are carried out, in particular with the development of scientific partnerships. (J.S.)

Aube storage center for very-low-level radioactive wastes. Annual report 2010

International Nuclear Information System (INIS)

2011-09-01

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. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2010 activity report of the center for very-low-level radioactive wastes. It presents a review of the activities of the center: presentation of the installations, safety, security and radiation protection, environmental monitoring and effluents, public information and communication

The Cigeo project: an industrial storage site for radioactive wastes in deep underground

International Nuclear Information System (INIS)

Krieguer, Jean-Marie

2017-01-01

In 2006, France has decided to store its high-level and long-lived radioactive wastes, mostly issued from the nuclear industry, in a deep geological underground disposal site. This document presents the Cigeo project, a deep underground disposal site (located in the East of France) for such radioactive wastes, which construction is to be started in 2021 (subject to authorization in 2018). After a brief historical review of the project, started 20 years ago, the document presents the radioactive waste disposal context, the ethical choice of underground storage (in France and elsewhere) for these types of radioactive wastes, the disposal site safety and financing aspects, the progressive development of the underground facilities and, of most importance, its reversibility. In a second part, the various works around the site are presented (transport, buildings, water and power supply, etc.) together with a description of the various radioactive wastes (high and intermediate level and long-lived wastes and their packaging) that will be disposed in the site. The different steps of the project are then reviewed (the initial design and initial construction phases, the pilot industrial phase (expected in 2030), the operating phase, and the ultimate phases that will consist in the definitive closure of the site and its monitoring), followed by an extensive description of the various installations of surface and underground facilities, their architecture and their equipment

Treatment and disposal of radioactive wastes from the viewpoint of the NUCLEX 78

Energy Technology Data Exchange (ETDEWEB)

Koerner, W [Staatliches Amt fuer Atomsicherheit und Strahlenschutz, Berlin (German Democratic Republic)

1980-02-01

The results and consequences of the NUCLEX 78 are considered in form of a progress report on treatment and disposal of radioactive wastes from the nuclear fuel cycle. Investigations performed in the USA, Western Europe, and Japan are concerned with rationalization of the treatment processes for low-level and intermediate-level radioactive wastes and with the development of industrial methods of high-level waste solidification. In the field of ultimate storage, utilization of stable rock layers in the deep underground - especially of salt rocks - is evaluated to be the only available method of long-term isolation of high-level radioactive wastes and wastes containing long-lived alpha emitters. After technical and economical as well as safety works will have been concluded, commissioning of repositories in the underground is to be expected in the mid nineties.

Management of radioactive wastes. Closing meeting

International Nuclear Information System (INIS)

2006-01-01

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. The debate comprised 4 public hearings (September 2005: Bar-le-Duc, Saint-Dizier, Pont-du-Gard, Cherbourg), 12 round-tables (October and November 2005: Paris, Joinville, Caen, Nancy, Marseille), a synthesis meeting (December 2005, Dunkerque) and a closing meeting (January 2006, Lyon). This document is the proceedings of this closing meeting. The aim of this meeting is to make a status of the different public hearings and round-tables and to stress on some particular points of the nuclear waste management debate. Some points concern the social and democratic dimension of this debate which can be summarized in few words like: public information, decision making, secrecy, confidence, transparency, acceptability, ethics. Some other points concern the scientific and technical dimensions of nuclear waste management and refer to the advantages and drawbacks of the different options of the 1991 law (transmutation, deep geologic disposal, and subsurface storage). (J.S.)

Radioactive waste in Federal Germany

International Nuclear Information System (INIS)

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

1988-01-01

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

Predisposal Radioactive Waste Management

International Nuclear Information System (INIS)

2014-01-01

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

Coupled thermo–hydro–mechanical processes for the Dutch radioactive waste repository

NARCIS (Netherlands)

Buragohain, P.; Vardon, P.J.; Hicks, M.A.; Vardon, P.J.; Bykov, D.

2016-01-01

Disposal of spent nuclear fuel and long lived radioactive waste in deep clay geological formations is one of the promising options worldwide. In this concept of the geological disposal system, the Boom Clay is considered as a potential host rock when designing a generic waste repository in the

International perspective on regulation and radioactive waste management

International Nuclear Information System (INIS)

Brennecke, P.W.

2001-01-01

In recent years, within the framework of national as well as international programmes, notable advances and considerable experience have been reached, in particular in the areas of minimisation of the production of radioactive waste, conditioning and disposal of short-lived low and intermediate level waste, vitrification of fission product solution on an industrial scale and engineered storage of long-lived high level waste, i.e. vitrified waste and spent fuel. Based on such results near-surface repositories have successfully been operated in many countries. Furthermore, geological repository development programmes are now being pursued, addressing the development and application of appropriate methods for site-specific safety assessments, too. In addition to scientific-technical areas, issues regarding economical, environmental, ethical and political aspects have been considered increasingly during the last years. Hence, there is a need for the examination of such issues in more detail and, if appropriate, for introducing respective results in further radioactive waste management and disposal options and/or planning work. Taking differences in national approaches, practices and constraints into account, it is to be recognised that future developments and decisions will have to be extended in order to include further important aspects and, finally, to enhance acceptance and confidence in safety-related planning work as well as proposed radioactive waste management and disposal solutions. In particular, international expertise and peer reviews are to be integrated. (author)

Development of transmutation technologies of radioactive waste by actinoid hydride

International Nuclear Information System (INIS)

Konashi, Kenji; Matsui, Hideki; Yamawaki, Michio

2001-01-01

Two waste treatment methods, geological disposal and transmutation, have been studied. The transmutation method changes long-lived radioactive nuclides to short-lived one or stabilizes them by nuclear transformation. The transmutation by actinoid hydride is exactly alike that transformation method from actinoid disposal waste to Pu fuel. For this object, OMEGA project is processing now. The transmutation is difficult by two causes such as large amount of long-lived radioactive nuclides and not enough development of control technologies of nuclear reaction except atomic reactor. The transmutation using actinoid hydride has merits that the amount of actinoid charged in the target increases and the effect of thermal neutrons on fuel decreases depending on homogeneous transmutation velocity in the target. Development of stable actinoid hydride under the conditions of reactor temperature and irradiation environment is important. The experimental results of U-ZrH 1.6 are shown in this paper. The irradiation experiment using Th hydride has been proceeding. (S.Y.)

Setting up a safe deep repository for long-lived HLW and ILW in Russia: Current state of the works

International Nuclear Information System (INIS)

Polyakov, Yu.D.; Porsov, A.Yu.; Beigul, V.P.; Palenov, M.V.

2014-01-01

The concept of RW disposal in Russia in accordance with the Federal Law 'On Radioactive Waste Management and Amendments to Specific Legal Acts of the Russian Federation' No. 190-FL dated 11 July 2011, is oriented at the ultimate disposal of waste, without an intent for their subsequent retrieval. The law 190-FL has it as follows: - A radioactive waste repository is a radioactive waste storage facility intended for disposal of the radioactive wastes without an intent for their subsequent retrieval. - Disposal of solid long-lived high-level waste and solid long-lived intermediate-level waste is carried out in deep repositories for radioactive waste. - Import into the Russian Federation of radioactive waste for the purpose of its storage, processing and disposal, except for spent sealed sources of ionising radiation originating from the Russian Federation, is prohibited. For safe final disposal of long-lived HLW and ILW, it is planned to construct a deep repository for radioactive waste (DRRW) in a low-pervious monolith rock massif in the Krasnoyarsk region in the production territory of the Mining and Chemical Combine (FSUE 'Gorno-khimicheskiy kombinat'). According to the IAEA recommendations and in line with the international experience in feasibility studies for setting up of HLW and SNF underground disposal facilities, the first mandatory step is the construction of an underground research laboratory. An underground laboratory serves the following purposes: - itemised research into the characteristics of enclosing rock mass, with verification of massive material suitability for safe disposal of long-lived HLW and ILW; - research into and verification of the isolating properties of an engineering barrier system; - development of engineering solutions and transportation and process flow schemes for construction and running of a future RW ultimate isolation facility. (authors)

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

International Nuclear Information System (INIS)

Markovic, V.

1964-10-01

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

Implementation of the program law from June 28, 2006 on the sustainable management of radioactive materials and wastes

International Nuclear Information System (INIS)

2009-07-01

This presentation, given by the national agency of radioactive waste management (ANDRA) at the meeting of July 1, 2009 of the high committee for the nuclear safety transparency and information (HCTISN), describes the two projects of the ANDRA in the framework of the program law of June 28, 2006 about the sustainable management of radioactive materials and wastes. The first project is a reversible deep geologic waste disposal facility for high level/long living wastes. The second project is a low depth waste storage facility for low level/long living wastes. For each project, the site selection, the type of waste and its conditioning, and the concept and specifications of the facility are presented. (J.S.)

CEA - Nuclear Energy Division. Report on Sustainable Radioactive Waste Management

International Nuclear Information System (INIS)

2012-12-01

The Sustainable Radioactive Waste Management Act of June 28, 2006, specified clear guidelines for spent nuclear fuel management. It states two complementary principles: - The policy of treating and recycling spent nuclear fuel is valid for reducing the quantity and toxicity of suitably packaged ultimate radioactive waste-forms. - The reference process for high-activity and long-lived ultimate waste is deep geological disposal. The report prepared by the CEA in response to these requirements was completed after several years of work in cooperation with the other French actors in this field (EDF, AREVA) and with contribution of the CNRS and Andra. It addresses the following topics in several volumes: n guidelines for research on 4. generation systems, and a description of the various systems examined; - the results of research coordinated by the CEA on partitioning and transmutation of long-lived radioactive elements; - choices proposed for the Astrid integrated technology demonstrator - a sodium-cooled fast reactor (SFR) - and a reasonable timetable for its construction; - a review of research conducted around the world on 4. generation systems based on fast neutron reactors (FNRs). The principal results and findings compiled by the CEA from these studies are summarized in this document

Aube storage center for short-lived low- and intermediate-level wastes. Annual report 2008

International Nuclear Information System (INIS)

2009-06-01

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. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2008 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, events or incidents, environmental monitoring, wastes management, public information

Management of radioactive wastes; Gestion des dechets radioactifs

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

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

Solid and liquid radioactive wastes

International Nuclear Information System (INIS)

Cluchet, J.; Desroches, J.

1977-01-01

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

Researches on the management of high activity and long-lived radioactive wastes. Axis 1 - separation-transmutation; Recherches sur la gestion des dechets radioactifs a haute activite et a vie longue. Axe 1 - separation-transmutation

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-11-15

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.)

Progress on the national low level radioactive waste repository and national intermediate level waste store

International Nuclear Information System (INIS)

Perkins, C.

2003-01-01

The Australian Government is committed to establishing two purpose-built facilities for the management of Australia's radioactive waste; the national repository for disposal of low level and short-lived intermediate level ('low level') waste, and the national store for storage of long-lived intermediate level ('intermediate level') waste. It is strongly in the interests of public security and safety to secure radioactive waste by disposal or storage in facilities specially designed for this purpose. The current arrangements where waste is stored under ad hoc arrangements at hundreds of sites around Australia does not represent international best practice in radioactive waste management. Environmental approval has been obtained for the national repository to be located at Site 40a, 20 km east of Woomera in South Australia, and licences are currently being sought from the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) to site, construct and operate the facility. The national repository may be operating in 2004 subject to obtaining the required licences. The national store will be located on Australian Government land and house intermediate level waste produced by Australian Government departments and agencies. The national store will not be located in South Australia. Short-listing of potentially suitable sites is expected to be completed soon

The low to intermediate activity and short living waste storage facility. For a controlled management of radioactive wastes

International Nuclear Information System (INIS)

2006-01-01

Sited at about 50 km of Troyes (France), the Aube facility started in 1992 and has taken over the Manche facility for the surface storage of low to intermediate and short living radioactive wastes. The Aube facility (named CSFMA) is the answer to the safe management of these wastes at the industrial scale and for 50 years onward. This brochure presents the facility specifications, the wastes stored at the center, the surface storage concept, the processing and conditioning of waste packages, and the environmental monitoring performed in the vicinity of the site. (J.S.)

Low-level radioactive waste disposal technologies used outside the United States

International Nuclear Information System (INIS)

Templeton, K.J.; Mitchell, S.J.; Molton, P.M.; Leigh, I.W.

1994-01-01

Low-level radioactive waste (LLW) disposal technologies are an integral part of the waste management process. In the United States, commercial LLW disposal is the responsibility of the State or groups of States (compact regions). The United States defines LLW as all radioactive waste that is not classified as spent nuclear fuel, high- level radioactive waste, transuranic waste, or by-product material as defined in Section II(e)(2) of the Atomic Energy Act. LLW may contain some long-lived components in very low concentrations. Countries outside the United States, however, may define LLW differently and may use different disposal technologies. This paper outlines the LLW disposal technologies that are planned or being used in Canada, China, Finland, France, Germany, Japan, Sweden, Taiwan, and the United Kingdom (UK)

Historical perspective, economic analysis, and regulatory analysis of the impacts of waste partitioning-transmutation on the disposal of radioactive wastes

International Nuclear Information System (INIS)

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

1990-10-01

Partitioning-transmutation, sometimes called actinide burning, is an alternative approach to high-level radioactive waste management. It consists of removing long-lived radionuclides from wastes and destroying those radionuclides, thus reducing the long-term hazards of radioactive waste. It was studied in detail in the 1970's. New developments in technology and other factors are resulting in a reexamination of this waste management option. This report consists of three papers which summarize the historical work, update the analysis of the costs of waste disposal, and describe current regulatory requirements which might be impacted by P-T. The papers provide a starting point for future research on P-T. 152 refs., 2 figs., 19 tabs

China's current status and long-term outlook of nuclear power and radioactive waste disposal management

International Nuclear Information System (INIS)

Li, Zhidong

2015-01-01

This study identified the current status and long-term outlook of China's nuclear power development and radioactive waste disposal management after the 3.11 FUKUSHIMA accidents. China strengthened the actions for achieving nuclear power safety and cost efficiency as well as safety management of radioactive waste. It is a hard work to expand the capacity to 58 GW, the governmental target in 2020. The long-term development will strongly depend on the progress in safety management of nuclear power and radioactive waste and economic competitiveness. (author)

Status and prospects of radioactive waste management in France

International Nuclear Information System (INIS)

Gonnot, F.M.

2012-01-01

The chairman of ANDRA (French agency for the management of radioactive waste) presents the activities of the agency in the framework of the 2006 Planning Act that took in principle the decision to dispose of the high-level and the long-lived radioactive waste in a geological repository (Cigeo project). One of the important aspects of the Cigeo project is the requirement by law, to study the reversibility and therefore to demonstrate the capability to retrieve already disposed waste packages. In March 2010 the Government accepted the 30 km 2 area proposed by ANDRA for the location of the future repository. At present, ANDRA teams are fully busy on 2 fronts: first in preparing the license application for Cigeo to be submitted in 2015, and secondly in preparing the industrial phase of the Cigeo project. Low-level and intermediate-level radioactive waste are disposed of in surface facilities. (A.C.)

Radioactive wastes management

International Nuclear Information System (INIS)

Albert, Ph.

1999-01-01

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

Aube storage centre for short-lived low- and intermediate-level wastes. Annual report 2009

International Nuclear Information System (INIS)

2010-06-01

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. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2009 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, events or incidents, environmental monitoring, wastes management, public information, opinion of the Health and safety Committee (CHSCT)

Aube storage center for short-lived low- and intermediate-level wastes. Annual report 2010

International Nuclear Information System (INIS)

2011-06-01

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. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2010 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, events or incidents, environmental monitoring, wastes management, public information, recommendations of the Health and safety Committee (CHSCT)

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)

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

Developing of Radioactive Wastes Management Safety at Baldone Repository Radons

International Nuclear Information System (INIS)

Abramenkovs, A.; Abramenkova, G.; Klavins, M.

2008-01-01

The near surface radioactive wastes repository Radons near the Baldone city was put in operation in 1962. The safety assessment of repository was performed during 2000-2001 under the PHARE project to evaluate the recommended upgrades of repository. The outline design for new vaults and interim storage for long lived radioactive wastes was elaborated during 2003-2004 years. The Environmental Impact Assessment (EIA) for upgrade of Baldone repository was performed during 2004-2005 years. Additional evaluations of radioactive wastes management safety were performed during 2006 year by the experts of ENRESA, Spain. It was shown, that the additional efforts were spent for improving of radioactive wastes cementation in concrete containers. The results of tritium and Cs 137 leaching studies are presented and discussed. It was shown, that additives can significantly reduce the migration of radionuclides in ground water. The leaching coefficients for tritium and Cs 137 were determined to supply with the necessary data the risk assessment calculations for operation of Baldone repository R adons

Proposed partitioning and transmutation of long-lived nuclear wastes

International Nuclear Information System (INIS)

Van Tuyle, G.J.; Rawlins, J.A.

1991-01-01

A means of transmuting key long-lived nuclear wastes, primarily the minor actinides (Np, Am, Cm) and iodine, using a hybrid proton accelerator and sub-critical lattice, is proposed. By partitioning light water reactor (LWR) spent fuel and by transmuting key elements, such as the plutonium, the minor actinides, and a few of the long-lived fission products, some of the most significant challenges in building a waste repository can be substantially reduced. The proposed machine would transmute the minor actinides and the iodine produced by 75 LWRs, and would generate usable electricity (beyond that required to run the large accelerator) of 850 MW e . 14 refs., 10 figs

The Constitution, waste facility performance standards, and radioactive waste classification: Is equal protection possible?

Energy Technology Data Exchange (ETDEWEB)

Eye, R.V. [Kansas Dept. of Health and Environment, Topeka, KS (United States)

1993-03-01

The process for disposal of so-called low-level radioactive waste is deadlocked at present. Supporters of the proposed near-surface facilities assert that their designs will meet minimum legal and regulatory standards currently in effect. Among opponents there is an overarching concern that the proposed waste management facilities will not isolate radiation from the biosphere for an adequate length of time. This clash between legal acceptability and a perceived need to protect the environment and public health by requiring more than the law demand sis one of the underlying reasons why the process is deadlocked. Perhaps the most exhaustive public hearing yet conducted on low-level radioactive waste management has recently concluded in Illinois. The Illinois Low-Level Radioactive Waste Disposal Facility Sitting Commission conducted 71 days of fact-finding hearings on the safety and suitability of a site near Martinsville, Illinois, to serve as a location for disposition of low-level radioactive waste. Ultimately, the siting commission rejected the proposed facility site for several reasons. However, almost all the reasons were related, to the prospect that, as currently conceived, the concrete barrier/shallow-land burial method will not isolate radioactive waste from the biosphere. This paper reviews the relevant legal framework of the radioactive waste classification system and will argue that it is inadequate for long-lived radionuclides. Next, the paper will present a case for altering the classification system based on high-level waste regulatory considerations.

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

Long term governance of radioactive waste - research and guidance on governance methodologies

International Nuclear Information System (INIS)

Meskens, G.

2007-01-01

Our modern society is increasingly faced with challenges and problems that cannot be solved by a purely technical, political or social approach. Radioactive waste disposal site selection and management can be characterised as one of these challenges that require a transdisciplinary approach, integrating social, philosophical and ethical aspects in a 'technical' practice. Along the spirit of this transdisciplinary approach, and in order to ensure the necessary public support for a policy decision regarding this practice, stakeholder involvement is more and more seen as a necessary policy element in the decision making process. The aim is to achieve the broad involvement of individuals from civil society, with significant representation from local communities, elected representatives and NGO's, as well as scientists from outside radioactive waste management organisations, together with established players in the field, such as the implementers of radioactive waste management, public authorities, experts and waste producers. Several initiatives regarding stakeholder involvement in radioactive waste management have been taken already in Europe, as well in the research era as in 'the real world'. Among them was the EC FP6 COWAM2 project ('Community Waste Management 2 - Improving the Governance of Nuclear Waste Management and Disposal in Europe') that run from January 2003 to December 2006. The objective of COWAM 2 was to contribute to the actual improvement of the governance of Radioactive Waste Management (RWM) in order to address the issue of geological waste disposal in Europe, by: Better addressing and understanding societal expectations, needs and concerns as regards radioactive waste decision making processes, notably at local and regional levels, taking advantage of the past and ongoing successful and unsuccessful experiences of RWM in the concerned European countries; Increasing societal awareness of and accountability for RWM at local, national and European

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

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

Systematic analysis method for radioactive wastes generated from nuclear research facilities

International Nuclear Information System (INIS)

Kameo, Yutaka; Ishimori, Ken-ichiro; Haraga, Tomoko; Shimada, Asako; Katayama, Atsushi; Nakashima, Mikio; Takahashi, Kuniaki

2011-01-01

Analytical methods have been developed for the simple and rapid determination of radioactive nuclides, which are selected as important nuclides for the safety assessment of the disposal of wastes generated from research facilities. We advanced the development of a high-efficiency nondestructive measurement technique for γ-ray-emitting nuclides, simple and rapid methods for the pretreatment of hard-to-dissolve samples and subsequent radiochemical separation, and rapid determination methods for long-lived nuclides. In order to establish a system to analyze the important nuclides in various kinds of sample, actual radioactive wastes such as concentrated liquid waste, activated concrete, and metal pipes were analyzed by the present method. The results showed that the present method was well suited for a rapid and simple determination of low-level radioactive wastes generated from research facilities. (author)

Presentation of preliminary studies relative to the long duration disposal of medium level and long lived (MLLL) wastes

International Nuclear Information System (INIS)

Leroy, C.; Moreau, A.; Fayette, L.; Bellon, M.; Templier, J.C.; Macias, R.M.; Porcher, J.B.; Rey, F.; Hollender, F.; Girard, J.P.

2002-01-01

In the contract of objectives signed in 2001 with the government, the French atomic energy commission (CEA) committed itself to supply reports of preliminary studies about long duration disposal concepts for medium level and long lived radioactive wastes. This document makes the synthesis of the preliminary studies carried out in 2001 and 2002 by exploring simultaneously the surface and subsurface disposal concepts. The studies deal with the design of a facility with a long service life. Four hypotheses have been retained for the preliminary studies: a secular lifetime (typically 100 to 300 years), a single and new site for all waste packages (no existing facility available), two confinement barriers, an envelope-type site with specific characteristics (seismicity, climate conditions, airplane crash..). These preliminary studies show the existence of solutions for each option: with and without storage containers in both type (surface and subsurface) of facilities. They outline the necessity of studying more thoroughly some technical points. This instruction will be performed for the concepts retained after a multi-criteria analysis. (J.S.)

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

International Nuclear Information System (INIS)

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

2001-01-01

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

New approaches to solving the management problem of long-lived radionuclides

International Nuclear Information System (INIS)

Egorov, N.N.; Zakharov, M.A.; Lazarev, L.N.; Lyubtsev, R.I.; Nikiforov, A.S.; Strakhov, M.V.; Filippov, E.A.

1991-01-01

During spent fuel reprocessing the most dangerous long-lived radionuclides are present both in off-gases on the stage of cutting and dissolution and mainly in highly radioactive raffinates arising from the first extraction cycle. In the last years the investigators of the Soviet Union are more and more led to the conclusion that the more reasonable combination of routine methods for waste management and new technical approaches could contribute to the profound solution of this problem. Estimations and specific development are focused on the followings; partitioning of long-lived radionuclides; improvement of solidification methods; substantiation of possibilities for transmutation of long-lived radionuclides; evaluation of potentialities for disposal of radioactive wastes into outer space. Many sided elaborations are needed for the realization of such concept; the most necessary developments have been already performed in some research programs. International cooperation in this field is likely to approach solving the settled problem. (M.N.)

Impact of partitioning and transmutation in radioactive waste management

International Nuclear Information System (INIS)

Magill, J.

2006-01-01

Nuclear energy provides a significant contribution to the overall energy supply in Europe. With 148 reactors in 13 of the 25 Member States producing a total power of 125 G We, the resulting energy generation of 850 TWh per year provides 35% of the total electrical energy requirements in the European Union. Worldwide, 441 commercial reactors operate in 31 countries and provide 17% of the electrical requirements. Currently 32 nuclear reactors are being built worldwide mostly in India, China and in neighbouring countries. The used fuel discharged from nuclear power plants constitutes the main contribution to nuclear waste in countries which do not undertake reprocessing. As such, its disposal requires isolation from the biosphere in stable deep geological formations for long periods of time (some hundred thousand years) until its radioactivity decreases through the process of radioactive decay. Ways for significantly reducing the volumes and radio toxicities of the waste and to shorten the very long times for which the waste must be stored safely are being investigated. This is the motivation behind the partitioning and transmutation (P and T) activities worldwide. Most of the hazard from the spent fuel stems from only a few chemical elements, namely plutonium, neptunium, americium, curium, and some long-lived fission products such as iodine, caesium and technetium. At present approximately 2500 t of spent fuel are produced annually in the EU, containing about 25 t of plutonium, and 3.5 t of the minor actinides neptunium, americium and curium, and about 3 t of long-lived fission products. These radioactive by-products, although present in relatively low concentrations in the used fuel, are a hazard to life forms when released into the environment. This paper addresses the potential impact of P and T on the long-term disposal of nuclear waste. In particular, it evaluates how realistic P and T scenarios can lead to a reduction in the time required for the waste to be

National Inventory of radioactive materials and wastes. The 2015 essentials. Synthesis report for 2015. 2015 descriptive catalogue of families. 2015 geographical inventory. The focus on 2015

International Nuclear Information System (INIS)

2015-03-01

This huge publication gathers several reports. He first one (The essentials) presents the stakes and principles of the management of radioactive materials and wastes, the inventory of stocks of radioactive wastes at the end of 2013 and the inventory of stocks of radioactive materials at the same date, discusses projected quantities of radioactive materials and wastes on the basis of industrial scenarios, and proposes prospective inventories. The second one is a synthesis report which addresses radioactive materials and wastes and their management (origins, classification, peculiar cases, general management principles), the general results (for radioactive materials, for radioactive wastes, perspective beyond 2030, warehousing and storages of radioactive materials and wastes), detailed results for different sectors (electronuclear, research, defence, non electronuclear industry, medicine), historical situations (storage centres for conventional wastes, historic on-site storages, storages of high natural radioactivity wastes, mining sites, sites contaminated by radioactivity, submerged wastes). It also proposes 6 thematic files: existing and projected solutions in France for the management of the different types of radioactive wastes on the long term, objectives and techniques of waste processing and packaging, dismantling of nuclear installations and decontamination of sites polluted by radioactivity, management of used radioactive sources, the case of high natural radioactivity wastes, foreign inventory of radioactive wastes. The next report addresses issues of waste classification (origin, management, family sheet of radioactive wastes, presentation of the different families (shapes, packaging, quantities, and so on): high-level, intermediate-level and long-lived, low and intermediate-level and short-lived, low-level and long-lived, very low-level, and others. Appendices notably indicate locations. The next report, after a recall on classification, origin and

Synthesis of long live storage studies surface storage of MA-VL wastes

International Nuclear Information System (INIS)

Hollender, F.; Jourdain, F.; Piault, E.; Blanchet, Y.; Avakian, G.; Goger, F.; Caillaud, J.; Devictor, N.; Bary, B.; Moitier, C.; Breton, E.; Ranc, G.; Gaillard, J.P.; Lagrave, H.

2004-01-01

This document is realized in the framework of the axis 3 of the law of 1991 on the radioactive wastes management. It presents a long time surface storage installation of medium activity long life wastes. The long time of the installation would reach 300 years at the maximum. The feasibility is demonstrated and the design choices are presented and justified. The specific points of the long time storage installation, which are different from a classical industrial storage installation, are also discussed. (A.L.B.)

Risk perception, risk evaluation and human values: cognitive bases of acceptability of a radioactive waste repository

International Nuclear Information System (INIS)

Earle, T.C.; Lindell, M.K.; Rankin, W.L.

1981-07-01

Public acceptance of radioactive waste management alternatives depends in part on public perception of the associated risks. Three aspects of those perceived risks were explored in this study: (1) synthetic measures of risk perception based on judgments of probability and consequences; (2) acceptability of hypothetical radioactive waste policies, and (3) effects of human values on risk perception. Both the work on synthetic measures of risk perception and on the acceptability of hypothetical policies included investigations of three categories of risk: (1) Short-term public risk (affecting persons living when the wastes are created), (2) Long-term public risk (affecting persons living after the time the wastes were created), and (3) Occupational risk (affecting persons working with the radioactive wastes). The human values work related to public risk perception in general, across categories of persons affected

A comparison of radioactive waste from first generation fusion reactors and fast fission reactors with actinide recycling

International Nuclear Information System (INIS)

Koch, M.; Kazimi, M.S.

1991-04-01

Limitations of the fission fuel resources will presumably mandate the replacement of thermal fission reactors by fast fission reactors that operate on a self-sufficient closed fuel cycle. This replacement might take place within the next one hundred years, so the direct competitors of fusion reactors will be fission reactors of the latter rather than the former type. Also, fast fission reactors, in contrast to thermal fission reactors, have the potential for transmuting long-lived actinides into short-lived fission products. The associated reduction of the long-term activation of radioactive waste due to actinides makes the comparison of radioactive waste from fast fission reactors to that from fusion reactors more rewarding than the comparison of radioactive waste from thermal fission reactors to that from fusion reactors. Radioactive waste from an experimental and a commercial fast fission reactor and an experimental and a commercial fusion reactor has been characterized. The fast fission reactors chosen for this study were the Experimental Breeder Reactor 2 and the Integral Fast Reactor. The fusion reactors chosen for this study were the International Thermonuclear Experimental Reactor and a Reduced Activation Ferrite Helium Tokamak. The comparison of radioactive waste parameters shows that radioactive waste from the experimental fast fission reactor may be less hazardous than that from the experimental fusion reactor. Inclusion of the actinides would reverse this conclusion only in the long-term. Radioactive waste from the commercial fusion reactor may always be less hazardous than that from the commercial fast fission reactor, irrespective of the inclusion or exclusion of the actinides. The fusion waste would even be far less hazardous, if advanced structural materials, like silicon carbide or vanadium alloy, were employed

A comparison of radioactive waste from first generation fusion reactors and fast fission reactors with actinide recycling

Energy Technology Data Exchange (ETDEWEB)

Koch, M.; Kazimi, M.S.

1991-04-01

Limitations of the fission fuel resources will presumably mandate the replacement of thermal fission reactors by fast fission reactors that operate on a self-sufficient closed fuel cycle. This replacement might take place within the next one hundred years, so the direct competitors of fusion reactors will be fission reactors of the latter rather than the former type. Also, fast fission reactors, in contrast to thermal fission reactors, have the potential for transmuting long-lived actinides into short-lived fission products. The associated reduction of the long-term activation of radioactive waste due to actinides makes the comparison of radioactive waste from fast fission reactors to that from fusion reactors more rewarding than the comparison of radioactive waste from thermal fission reactors to that from fusion reactors. Radioactive waste from an experimental and a commercial fast fission reactor and an experimental and a commercial fusion reactor has been characterized. The fast fission reactors chosen for this study were the Experimental Breeder Reactor 2 and the Integral Fast Reactor. The fusion reactors chosen for this study were the International Thermonuclear Experimental Reactor and a Reduced Activation Ferrite Helium Tokamak. The comparison of radioactive waste parameters shows that radioactive waste from the experimental fast fission reactor may be less hazardous than that from the experimental fusion reactor. Inclusion of the actinides would reverse this conclusion only in the long-term. Radioactive waste from the commercial fusion reactor may always be less hazardous than that from the commercial fast fission reactor, irrespective of the inclusion or exclusion of the actinides. The fusion waste would even be far less hazardous, if advanced structural materials, like silicon carbide or vanadium alloy, were employed.

The management of radioactive wastes

International Nuclear Information System (INIS)

1998-01-01

This educative booklet describes the role and missions of the ANDRA, the French national agency for the management of radioactive wastes, and the different aspects of the management of radioactive wastes: goal, national inventory, classification, transport (organisation, regulation, safety), drumming, labelling, surface storage of short life wastes, environmental control, management of long life wastes (composition, research, legal aspects) and the underground research laboratories (description, public information, projects, schedules). (J.S.)

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)

Long-lived high and intermediate level radioactive wastes: defining the context, stakes and perspectives; Dechets radioactifs de haute activite et de moyenne activite a vie longue: situer le contexte, les enjeux et les perspectives

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

The French law from December 30, 1991 has defined an ambitious 15 years program of researches in order to explore the different possible paths for the long-term management of long-lived high and intermediate level radioactive wastes. The law foresees also that at the end of the 15 years research program, a project of law will be prepared by the French government and transmitted to the European parliament in 2006. A public debate has been organized and emceed in 2005 in order dialogue with the general public and to gather its questions, remarks and fears. In the framework of their contribution to this debate, the ministries of industry and environment have prepared this document which answers some key questions about radioactive waste management: where do wastes come from, what are the risks, how are they managed today in France and in foreign countries, what are the results of the researches carried out during 15 years, what are the advantages and drawbacks of each waste management solution considered, what is the perspective of application of each solution, what is the position of experts, what will be the decision process. This synthetic document supplies some reference marks to better understand these different points. Some pedagogical files about radioactivity, fuel cycle, and nuclear industry activities are attached to the document. (J.S.)

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

Characterization of long-lived radioactive dust clouds generated in uranium mill operations

International Nuclear Information System (INIS)

Bigu, J.

1987-01-01

The characteristics of long-lived radioactive dust clouds generated in several mechanical and physico-chemical operations in a uranium mill have been investigated. The study consisted of the determination of dust size distribution, and of the radionuclides contained in the particles of each dimension class ranging from <0.1 to 26 μm in diameter. Experiments were conducted using several cascade impactors operating at different sample flow rates. Two different types of cascade impactors were used. Radionuclide identification was done using α-spectrometry and γ-spectrometry. Long-lived and short-lived radionuclides were identified in dust samples. The characteristics of the dust clouds depended on the mill operation. The following operations were studied: crushing (vibrating grizzly, jaw crusher, cone crusher); screening; ore transportation; grinding; acid leaching; counter-current decantation; yellowcake precipitation and drying; and yellowcake packaging. In addition, other dust and radioactivity measurements have been carried out

Regulatory objectives, requirements and guidelines for the disposal of radioactive wastes - long-term aspects

International Nuclear Information System (INIS)

1987-01-01

It is the purpose of this document to present the regulatory basis for judging the long-term acceptability of radioactive waste disposal options, assuming that the operational aspects of waste emplacement and facility closure satisfy the existing regulatory framework of requirements. Basic objectives of radioactive waste disposal are given, as are the regulatory requirements which must be satisfied in order to achieve these objectives. In addition, guidelines are given on the application of the radiological requirements to assist proponents in the preparation of submissions to the Atomic Energy Control Board (AECB). The primary focus of the requirements is on radiation protection, although environmental protection and institutional controls are also addressed in a more general way since these factors stem directly from the overall objectives for radioactive waste disposal

Environmental restoration and management of low-level radioactive and mixed waste at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Kendrick, C.M.

1994-01-01

Management of radioactive waste at Oak Ridge National Laboratory (ORNL) must address several major challenges. First, contaminants from some disposed wastes are leaching into the groundwater and these disposal sites must be remediated. Second, some of these ''legacy'' wastes, as well as currently generated radioactive wastes, are also contaminated with chemicals, including polychlorinated biphenyls (PCBs), solvents, and metals (i.e., mixed waste). Third, wastes containing long-lived radionuclides in concentrations above established limits have been determined unsuited for disposal on the Oak Ridge Reservation. Reflecting these challenges, ORNL's strategy for managing its radioactive wastes continues to evolve with the development of improved technologies and site-specific adaptation of some standard technologies

Radioactive wastes: a proposal to its classification

International Nuclear Information System (INIS)

Domenech N, H.; Garcia L, N.; Hernandez S, A.

1996-01-01

On the basis of the quantities and the characteristics of the stored radioactive wastes in Cuba and the IAEA system of wastes classification, the concentration activities that would be used as limits for those categories are evaluated. This approach suggests a limit of 10 TBq/m 3 for short lived liquid wastes of Low and Intermediate Level (less than 30 years) and 5 TBq/m 3 for long lived liquid wastes (more than 30 years). For solid wastes the suggested limits are ten times lower. Taking into account the small quantities of arising wastes and to make easy its segregation, collection and disposal, a low level waste sub-classification in three new categories, whether or not they may be direct discharged, is suggested. As lower classification limit, while not specific exemption levels are established in the country, the use of an ALI min fraction is emphasized, meanwhile the total discharged activity will be no greater than 10 MBq or 100 MBq when the discharge occurs over the whole year. (authors). 6 refs., 5 tabs

Radioactive waste handling and disposal at King Faisal Specialist Hospital and Research Centre.

Science.gov (United States)

Al-Haj, Abdalla N; Lobriguito, Aida M; Al Anazi, Ibrahim

2012-08-01

King Faisal Specialist Hospital & Research Centre (KFSHRC) is the largest specialized medical center in Saudi Arabia. It performs highly specialized diagnostic imaging procedures with the use of various radionuclides required by sophisticated dual imaging systems. As a leading institution in cancer research, KFSHRC uses both long-lived and short-lived radionuclides. KFSHRC established the first cyclotron facility in the Middle East, which solved the in-house high demand for radionuclides and the difficulty in importing them. As both user and producer of high standard radiopharmaceuticals, KFSHRC generates large volumes of low and high level radioactive wastes. An old and small radioactive facility that was used for storage of radioactive waste was replaced with a bigger warehouse provided with facilities that will reduce radiation exposure of the staff, members of the public, and of the environment in the framework of "as low as reasonably achievable." The experiences and the effectiveness of the radiation protection program on handling and storage of radioactive wastes are presented.

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.

Suitable areas for a long-term radioactive waste storage facility in Portugal

International Nuclear Information System (INIS)

Duarte, P.; Paiva, I.; Trindade, R.; Mateus, A.

2006-01-01

Radioactive wastes in Portugal result mainly from the application of radioactive materials in medicine, research, industry and from U-ores mining and milling activities. Sealed and unsealed sources (including liquid effluents and N.O.R.M.) classified as radioactive wastes have been collected, segregated, conditioned and stored in the Portuguese Radioactive Waste Interim Storage Facility (P.R.W.I.S.F.) since the sixties. The Radiological Protection and Nuclear Safety Department (D.P.R.S.N.) of the Nuclear and Technological Institute (I.T.N.) is responsible for the R.W.I.S.F. management, located nearby Lisbon (S.a.c.a.v. ). Despite recent improvements performed at R.W.I.S.F., the 300 m3 storage capacity will be soon used up if current average store-rate remains unaltered. Being aware of the tendency for radioactive waste production increase in Portugal and of the international rules and recommendations on disposal sites for this kind of wastes, it becomes clear that the P.R.W.I.S.F. must be updated. In this work, a first evaluation of suitable areas to host a long-term radioactive waste storage facility was carried out using a Geographic Information System (G.I.S.) base. Preference and exclusionary criteria were applied, keeping constant the map scale (1:1000000). After processing exclusionary criteria, remaining areas were scored by overlaying three preference criteria. A composite score was determined for each polygon (problem solution) by summing the three preference criteria scores. The highest scores resulted from the combination of these criteria correspond to 4% of the territory, spatially distributed in seven of the eighteen Portuguese mainland administrative districts. Work in progress will use this area as reference for site selection, criss-crossing appropriate criteria for scales ranging from 1:50000 to 1:25000. (authors)

Suitable areas for a long-term radioactive waste storage facility in Portugal

Energy Technology Data Exchange (ETDEWEB)

Duarte, P.; Paiva, I.; Trindade, R. [Instituto Tecnologico e Nuclear, Dept. de Proteccao Radiologica e Seguranca Nuclear, Sacavem (Portugal); Mateus, A. [Lisboa Univ., Dept. de Geologia and Creminer, Faculdade de Ciencias (Portugal)

2006-07-01

Radioactive wastes in Portugal result mainly from the application of radioactive materials in medicine, research, industry and from U-ores mining and milling activities. Sealed and unsealed sources (including liquid effluents and N.O.R.M.) classified as radioactive wastes have been collected, segregated, conditioned and stored in the Portuguese Radioactive Waste Interim Storage Facility (P.R.W.I.S.F.) since the sixties. The Radiological Protection and Nuclear Safety Department (D.P.R.S.N.) of the Nuclear and Technological Institute (I.T.N.) is responsible for the R.W.I.S.F. management, located nearby Lisbon (S.a.c.a.v. ). Despite recent improvements performed at R.W.I.S.F., the 300 m3 storage capacity will be soon used up if current average store-rate remains unaltered. Being aware of the tendency for radioactive waste production increase in Portugal and of the international rules and recommendations on disposal sites for this kind of wastes, it becomes clear that the P.R.W.I.S.F. must be updated. In this work, a first evaluation of suitable areas to host a long-term radioactive waste storage facility was carried out using a Geographic Information System (G.I.S.) base. Preference and exclusionary criteria were applied, keeping constant the map scale (1:1000000). After processing exclusionary criteria, remaining areas were scored by overlaying three preference criteria. A composite score was determined for each polygon (problem solution) by summing the three preference criteria scores. The highest scores resulted from the combination of these criteria correspond to 4% of the territory, spatially distributed in seven of the eighteen Portuguese mainland administrative districts. Work in progress will use this area as reference for site selection, criss-crossing appropriate criteria for scales ranging from 1:50000 to 1:25000. (authors)

Radioactive wastes. Management prospects

International Nuclear Information System (INIS)

Guillaumont, R.

2003-01-01

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

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.)

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)

The strategy and practice of radioactive waste management in the Pacific Basin

International Nuclear Information System (INIS)

Norman, N.; Gray, B.R.

1992-01-01

Radioactive waste management is an integral part of the planning process for the nuclear industry in Pacific Basin countries. This paper reviews areas of common interest and cooperation, sources of waste and current inventories, production rates, and future plans. Each level of radioactive waste requires different methods for handling, storage, and disposal. Definitions may vary In detail from country to country, but generally high level wastes are defined as those deriving from spent fuel and from reprocessing of fuel. These wastes contain transuranic elements and fission products that are highly radioactive, heat-generating and long-lived. Intermediate level and low level wastes may include, respectively, material from fuel fabrication and power generation other than spent fuel, and those wastes produced by research institutions, hospitals, and in other non-power producing Industrial uses of radioisotopes. The energy requirements of most countries are likely to continue to grow, and the use of radioactive isotopes in medicine and other non-energy industrial sectors is also expanding. The Pacific Nuclear Council member states participating in the Waste Management Working Group, are predicting, therefore, that the volume of radioactive waste for disposal will continue to grow

Non-fuel cycle radioactive waste policy in Turkey

International Nuclear Information System (INIS)

Izmir, A.I.; Uslu, I.

2001-01-01

Full text: Introduction. 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. It involves both short-lived and long lived radionuclides. In general, this includes radioactive materials, which are no longer useful and have their origin from practice or intervention both with unsealed and sealed sources. Radioactive Waste Management in Turkey. Utilisation of radioactive materials in Turkey requires special authorisations and falls under legal rules, in particular under the Radiation Safety Regulation of 24th March 2000 (Official Gazette number: 20983) outlining a general regulation for the protection of the population and workers against the danger of ionising radiation and subsequent amendments. There is also a requirement enforced by the Regulations for Radioactive Wastes Exempt from Regulatory Authority Control (published on 15 January 2000, Official Gazette number: 23934) that identifies the limits and other conditions for the discharges of radioactive substances to the environment. Radioactive waste is generally understood as material for which no further use is foreseen, and which has been managed in a system of reporting, authorisation and control as specified in International Atomic Energy Agency (IAEA) recommendations or national legislation. In this paper radioactive waste is considered in two categories: as originated from unsealed sources or from sealed sources. a) Management of Unsealed Sources. Unsealed radionuclides are utilised in human medicine for in vivo diagnosis, metabolic therapy and in vitro biological analysis. The most common types of radionuclides used in Turkey are C-14, Co-57, Cr-51, Fe-59, Ga-67, H-3, I-123, I-125, I-131, In-111, Mo-99, P-32, P-33, Re-186, S-35, Sr-89, Sr-90, Tc-99, Tl-201, Xe-133, Y-90 which are import of radiopharmaceuticals to Turkey in

NAGRA - Long-term safety - The main task of deep repositories for radioactive wastes

International Nuclear Information System (INIS)

2015-10-01

This comprehensive brochure published by the Swiss National Cooperative for the Disposal of Radioactive Waste (NAGRA) examines the necessity for the safe disposal of radioactive wastes in Switzerland and discusses the requirements placed on such long-term waste depositories The effects of ionizing radiation on people and the protection provided by the deep repositories are examined. The construction of such deep repositories is looked at, as are the developments expected in the depositories over thousands of years. A comparison with natural occurrences is made and lessons to be learned from nature are discussed. Ideas for the marking of the depository sites are presented. A glossary of relevant terms completes the report

Management of very low-level radioactive waste

International Nuclear Information System (INIS)

Chapalain, E.; Damoy, J.; Joly, J.M.

2003-01-01

This document comprises 3 articles. The first article presents the concern of very low-level radioactive wastes generated in nuclear installations, the second article describes the management of the wastes issued from the dismantling operations of the ALS (linear accelerator of Saclay) and of the Saturn synchrotron both located in Saclay Cea's center. The last article presents the storage facility which is specifically dedicated to very low-level radioactive wastes. This storage facility, which is located at Morvilliers, near the 'Centre de l Aube' (used to store the low-, and medium-level, short-lived radioactive wastes), will receive the first packages next summer. Like the other storage facilities, it will be managed by ANDRA (national radioactive waste management agency)

Classification of Radioactive Waste. General Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-11-15

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

Classification of Radioactive Waste. General Safety Guide

International Nuclear Information System (INIS)

2009-01-01

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

A HOLISTIC APPROACH FOR DISPOSITION OF LONG-LIVED RADIOACTIVE MATERIALS

International Nuclear Information System (INIS)

Eriksson, Leif G.; Dials, George E.; Parker, Frank L.

2003-01-01

During the past 45 years, one of the most challenging scientific, engineering, socio-economic, and political tasks and obligations of our time has been to site and develop technical, politically acceptable, solutions to the safe disposition of long-lived radioactive materials (LLRMs). However, at the end of the year 2002, the Waste Isolation Pilot Plant (WIPP) site in the United States of America (USA) hosts the world's only operating LLRM-disposal system, which (1) is based on the LLRM-disposal principles recommended by the National Academy of Sciences (NAS) in 1957, i.e., deep geological disposal in a ''stable'' salt vault/repository, (2) complies with the nation's ''Environmental Radiation Protection Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes'', and (3) may receive 175,584 cubic meters (m3) of transuranic radioactive waste (TRUW)a. Pending the scheduled opening of repositories for once-used nuclear fuel (OUNF) in the USA, Sweden, and Finland in the years 2010, 2015, and 2017, respectively, LLRM-disposal solutions remain the missing link in all national LLRM-disposition programs. Furthermore, for a variety of reasons, many nations with nuclear programs have chosen a ''spectator'' stance in terms of enhancing the global nuclear safety culture and the nuclear renaissance, and have either ''slow-tracked'' or deferred their LLRM-disposal programs to allow time for an informed national consensus to evolve based on LLRM-disposition experiences and solutions gained elsewhere. In the meantime, LLRMs will continue to amass in different types and levels of safeguarded storage facilities around the world. In an attempt to contribute to the enhancement of the global nuclear safety culture and the nuclear renaissance, the authors developed the sample holistic approach for synergistic disposition of LLRMs comprising LLRM-disposition components considered either ''proven'' or ''promising'' by the authors. The

Strategic areas in radioactive waste management. The viewpoint and work orientations of the Nea radioactive waste management committee

International Nuclear Information System (INIS)

1999-01-01

The NEA Radioactive Waste Management Committee (RWMC) is a forum of senior operators, regulators, policy makers, and senior representatives of R and D institutions in the field of radioactive waste management. The Committee assists Member countries by providing objective guidance on the solution of radioactive waste problems, and promotes Safety in the short- and long-term management of radioactive waste. This report identifies some of the major challenges currently faced by national waste management programmes, and describes the strategic areas in which the RWMC should focus its efforts in future years. (author)

Progress in determination of long-lived radionuclides by inductively coupled plasma mass spectrometry

International Nuclear Information System (INIS)

Becker, J.S.; Dietze, H.J.

2000-01-01

Mass spectrometric methods (such as inductively coupled plasma mass spectrometry - ICP-MS and laser ablation (LA)-ICP-MS) with their ability to provide a very sensitive multielemental and precise isotopic analysis have become established for the determination of radionuclides in quite different sample materials. The determination of long-lived radionuclides is of increasing interest for the characterization of radioactive waste materials and for the detection of radionuclide contamination in environmental materials in which several radioactive nuclides are present from fallout due to nuclear weapons testing, nuclear power plants or nuclear accidents. Due to its multielement capability, excellent sensitivity, low detection limits (up to sub pg I 1 range), very good precision, easy sample preparation and measurement procedures ICP-MS of aqueous solutions has been increasingly applied for the ultrasensitive determination of long-lived radionuclides such as 99 Tc, 129 I, 230 Th, 232 Th, 234 U, 235 U, 236 U, 239 Pu, 240 Pu and 241 Am and precise isotope ratio measurements of U,Th and Pu. The application especially of microanalytical methods (analysis of some MU by flow injection and on-line coupling techniques as capillary electrophoresis (CE-ICP-MS) or HPLC-ICP-MS) for the precise determination nuclide abundances and concentration of long-lived radionuclides at ultra trace concentration levels in radioactive waste and also for controlling contamination from radioactive waste in the environment is a challenging task

Long-term safety of the maintenance and decommissioning waste of the encapsulation plant

International Nuclear Information System (INIS)

Nummi, O.; Kylloenen, J.; Eurajoki, T.

2012-12-01

This report, Long-term safety of the maintenance and decommissioning waste of the encapsulation plant, presents the disposal concept for the low and intermediate level waste (L/ILW) that is generated during the operation and decommissioning of the encapsulation plant, and assesses the long-term safety of the disposal of the waste. Radioactive waste originates from the spent nuclear fuel transferred and dried in the encapsulation plant. Radioactive waste accumulates also in the maintenance of the components and systems of the encapsulation plant. The waste is collected, exempted from control if possible and treated for final disposal if necessary. The waste is disposed of in the L/ILW hall which is currently planned to be located at a depth of -180 meters along the access tunnel to the repository for spent fuel. The main engineered barrier in the L/ILW hall is a concrete basin that encases the dried liquid waste. The safety concept of L/ILW disposal is based on the slow release of radioactivity from the L/ILW hall and its limited transport through the bedrock into biosphere. The release and transport of the radioactivity is described by the assessment scenarios, which include expected evolution and unlikely events affecting the long-term safety. The scenarios act as guidelines according to which the conceptual and mathematical models are formed. The long-term safety of the L/ILW hall is assessed using deterministic and probabilistic modeling. Special issues such as human intrusion and radiation effects on other biota are also assessed. The most significant contributor to the dose rates is the short-lived radionuclide 90 Sr followed by long-lived nuclides 129 I and 108 mAg. The annual doses to the public, and release rates of radioactive substances stay below the regulatory constraints in all analyzed scenarios. (orig.)

Nuclear energy from radioactive waste

International Nuclear Information System (INIS)

Schwarzenberg, M.

1998-01-01

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

France's State of the Art Distributed Optical Fibre Sensors Qualified for the Monitoring of the French Underground Repository for High Level and Intermediate Level Long Lived Radioactive Wastes.

Science.gov (United States)

Delepine-Lesoille, Sylvie; Girard, Sylvain; Landolt, Marcel; Bertrand, Johan; Planes, Isabelle; Boukenter, Aziz; Marin, Emmanuel; Humbert, Georges; Leparmentier, Stéphanie; Auguste, Jean-Louis; Ouerdane, Youcef

2017-06-13

This paper presents the state of the art distributed sensing systems, based on optical fibres, developed and qualified for the French Cigéo project, the underground repository for high level and intermediate level long-lived radioactive wastes. Four main parameters, namely strain, temperature, radiation and hydrogen concentration are currently investigated by optical fibre sensors, as well as the tolerances of selected technologies to the unique constraints of the Cigéo's severe environment. Using fluorine-doped silica optical fibre surrounded by a carbon layer and polyimide coating, it is possible to exploit its Raman, Brillouin and Rayleigh scattering signatures to achieve the distributed sensing of the temperature and the strain inside the repository cells of radioactive wastes. Regarding the dose measurement, promising solutions are proposed based on Radiation Induced Attenuation (RIA) responses of sensitive fibres such as the P-doped ones. While for hydrogen measurements, the potential of specialty optical fibres with Pd particles embedded in their silica matrix is currently studied for this gas monitoring through its impact on the fibre Brillouin signature evolution.

Radioactive wastes. Their industrial management

International Nuclear Information System (INIS)

Lavie, J.M.

1982-01-01

This paper introduces a series that will review the present situation in the field of long-term management of radioactive wastes. Both the meaning and the purposes of an industrial management of radioactive wastes are specified. This short introduction is complemented by outline of data on the French problem [fr

Sorption-reagent treatment of brines produced by reverse osmosis unit for liquid radioactive waste management

International Nuclear Information System (INIS)

Avramenko, V. A.; Zheleznov, V. V.; Sergienko, V. I.; Chizhevsky, I. Yu

2003-01-01

The results of the pilot plant tests (2002-2003) of the sorption-reagent decontamination of high salinity radioactive waste (brines) remaining after the low-salinity liquid radioactive waste (LRW) treatment in the reverse-osmosis unit from long-lived radionuclides are presented. The sorption-reagent materials used in this work were developed in the Institute of Chemistry FEDRAS. They enable one to decontaminate brines with total salt content up to 50 g/l from long-lived radionuclides of Cs, Sr and Co. At joint application of the reverse-osmosis and sorption-reagent technologies total volume of solid radioactive waste (SRW) decreases up to 100-fold as compared to the technology of cementation of reverse osmosis brines. In this case total cost of LRW treatment and SRW disposal decreases more than 10-fold. Brines decontaminated from radionuclides are then diluted down to the ecologically safe total salts content in water to be disposed of. Tests were performed to compare the efficiency of technologies including evaporation of brines remaining after reverse osmosis process and their decontamination by means of the sorption-reagent method. It was shown that, as compared to evaporation, the sorption-reagent technology provides substantial advantages as in regard to radioactive waste total volume reduction as in view of total cost of the waste management

Status and challenges for radioactive waste management

International Nuclear Information System (INIS)

Riotte, H.

2011-01-01

In its 2008 Nuclear Energy Outlook the NEA reviewed the status of radioactive waste management world-wide and noted that the technology for disposal of short-lived low- and intermediate-level radioactive waste is well developed. The review concluded that all OECD countries with major nuclear programmes either operate corresponding waste disposal facilities or are in an advanced stage of developing them. By contrast, the developmental progress of HLW/SNF management programmes varies widely between countries; not to mention that there is currently no repository operating that could take spent nuclear fuel or high-level waste from reprocessing. In its collective opinion 'Moving forward with geological disposal' the NEA noted that deep underground disposal in geological formations is seen worldwide as the only sustainable endpoint for the management of these types of waste, as it affords unparalleled protection without reliance on active safety monitoring and controls. While waste management programmes in some countries are well matured and countries like Finland, France and Sweden aim to operate geologic repositories in the next decade, others need to develop their national strategies, plans and corresponding actions for managing radioactive waste further. Periodically reviewed national waste management plans, as legally required for EU member countries by a recent Directive, can provide a co-operation framework for all national institutional players and a means to measure progress. In implementing sustainable solutions for the long-term management of HLW/SNF, specific challenges lay in establishing an efficient policy and regulatory framework that (a) defines a desired level of safety over the various time scales to be considered and (b) allows for sustainable decision making procedures by involving public and stakeholder in a flexible, step-wise implementation process. Technical confidence in the safety of a repository needs to be demonstrated in a modern

Management of radioactive wastes from nuclear fuels and power plants in Canada

International Nuclear Information System (INIS)

Tomlinson, M.; Mayman, S.A.; Tammemagi, H.Y.; Gale, J.; Sanford, B.

1977-05-01

The nature of Canadian nuclear fuel and nuclear generating plant radioactive wastes is summarized. Principles of a scheme for disposal of long-lived radioactive wastes deep underground in isolation from man and the biosphere are outlined. The status of the development and construction program is indicated. We have demonstrated incorporation of fission products in solids that in the short term (17 years) dissolve more slowly than plutonium decays. Investigations of long-term stability are in hand. Additional capacity for storage of used fuel prior to reprocessing and disposal is required by 1986 and a preliminary design has been prepared for a pool facility to be located at a central fuel recycling and disposal complex. A demonstration of dry storage of fuel in concrete containers is in progress. The quantities of CANDU generating-station wastes and the principles and methods for managing them are summarized. A radioactive-waste operations site is being developed with several different types of surface storage, each with multiple barriers against leakage. A reactor decommissioning study has been completed. Estimated costs of the various waste management operations are summarized. (author)

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

Basic approaches to the limitation of doses and radiological risks from surface disposal of long-lived radioactive waste for future generations

International Nuclear Information System (INIS)

Likhtarev, I.; Kovgan, L.; Berkovskiy, V.

2001-01-01

National radiation standards of Ukraine (NRSU-97/D-2000) recently put into force, which consider the basic principles of radiological protection from the sources of potential exposure, introduce four groups of potential exposure sources depending on types and scope of the consequences of occurrence of different critical events. In the third group are those occurrence which are associated with the events that can take place in the future (including the distant future) at the exempted from regulation facilities as a result of natural abnormal processes and catastrophes as well as inadvertent human intrusions. Future generations living at the moment of the event occurrence can become the subject of exposure. These sources must be taken into account at the stage of radioactive waste repositories designing. Taking into account the peculiarity of sources of the third group of potential, that they are associated with those critical events, which can take place in the distant future (in hundreds and thousands of years) and as a consequence may result in the exposure of future generations of people NRSU-97/D2000 sets an additional principle for potential exposure from sources of third group which requires that the future generations are guaranteed to have at least the same level of radiation protection against actions undertaken nowadays as the present generation. This principle is implemented through setting a requirement that harm for human health of future generation must not exceed the harm corresponding to negligible risk which is 5 x 10 -7 year -1 . NRSU-97/D-2000 establishes two reference dose levels A and B (50 and 1 mSv year -1 ) depending on which the acceptability of surface (or near-surface) disposals of long-lived radioactive waste is determined. In presentation the requirements on the critical events occurrence probability, two groups of scenario, which can lead to the critical event, and five reference scenarios of exposure and their parameters are discussed

Radioactive waste management policy

International Nuclear Information System (INIS)

Werthamer, N.R.

1977-01-01

The State of New York, some 15 years ago, became a party to an attempt to commercialize the reprocessing and storage of spent nuclear fuels at the West Valley Reprocessing Facility operated by Nuclear Fuel Services, Inc. (NFS). That attempted commercialization, and the State of New York, have fallen victim to changing Federal policies in the United States, leaving an outstanding and unique radioactive waste management problem unresolved. At the beginning of construction in 1963, the AEC assured both NFS and New York State of the acceptability of long-term liquid tank storage for high level wastes, and New York State ERDA therefore agreed to become the responsible long-lived stable institution whose oversight was needed. It was understood that perpetual care and maintenance of the wastes, as liquid, in on-site underground tanks, would provide for safe and secure storage in perpetuity. All that was thought to be required was the replacement of the tanks near the end of their 40-year design life, and the transferring of the contents; for this purpose, a perpetual care trust fund was established. In March of 1972, NFS shut West Valley down for physical expansion, requiring a new construction permit from the AEC. After four years of administrative proceedings, NFS concluded that changes in Federal regulations since the original operating license had been issued would require about 600 million dollars if operations were to resume. In the fall of 1976, NFS informed the NRC, of its intention of closing the reprocessing business. The inventories of wastes left are listed. The premises upon which the original agreements were based are no longer valid. Federal responsibilities for radioactive wastes require Federal ownership of the West Valley site. The views of New York State ERDA are discussed in detail

Annual report of the Aube storage center for very-low-level radioactive wastes (CSTFA) - 2011

International Nuclear Information System (INIS)

2012-08-01

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. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2011 activity report of the center for very-low-level radioactive wastes. It presents a review of the activities of the center: presentation of the installations, safety, security and radiation protection, environmental monitoring and effluents, public information and communication

The new ICRP recommendations on radiological protection in geological disposal of long-lived solid radioactive waste

International Nuclear Information System (INIS)

Lochard, Jacques; Schneider, Thierry

2014-01-01

Radioactive waste management has been the subject of several recommendations of the International Commission on Radiological Protection (ICRP) since 1985. The aim of the new Publication 122 (2013) is to describe how the 2007 general recommendations of the Commission (Publication 103) can be applied in the context of geological disposal. For this purpose, it is important to emphasise that the new approach developed by ICRP is based on three types of exposure situations: planned, emergency and existing: - Planned exposure situations correspond to situations where exposures result from the operation of deliberately introduced sources. Exposures can be planned and fully controlled. - Emergency exposure situations correspond to situations where exposures result from the loss of control of a source within a planned exposure, or from an unexpected situation (e.g. malevolent event). These situations require urgent actions to prevent or mitigate exposures. - Existing exposure situations correspond to situations where exposures result from sources that already exist when decisions are taken to control them. The characterisation of exposure is therefore a prerequisite for their control. The application of the three basic radiological protection principles - justification, optimisation of protection and limitation of individual doses - are therefore considered in this new framework with justification and optimisation applying to the three types of exposure situations and limitation only to planned exposure situations. The main points highlighted in Publication 122 for the application of the system of radiological protection to geological disposal of long-life solid radioactive waste are summarized

Managing Australian radioactive wastes in an international framework

International Nuclear Information System (INIS)

Kurzeme, M.; MCCombie, C.; Chapman, N.

2006-01-01

In the past few years, there has been an active public discussion in Australia about radioactive wastes and the search for suitable sites for their storage and disposal. Much of the debate has revolved around the Australian Government plans for building a near surface repository and for rinding a storage site for those radioactive wastes that will not be acceptable at a repository of this type. During the same period, there has been an international debate in progress concerning the pros and cons of multinational repositories that would accept waste from a rage of countries. One of the early initiatives in this area involved a proposal (the Pangea Project) to study the feasibility of disposing of multinational wastes deep down in the geologically very stable rock formations underlying much of the desert regions of Western Australia. These diverse projects have led to confusion - sometimes deliberately provoked - between the various initiatives for storage and disposal of radioactive waste in Australia. There have been three types of technical facilities being developed throughout the world: 1. Near surface repositories for permanent disposal of LLW on, or near to, the ground surface; 2. Surface storage facilities, which are an interim or temporary measure used for long-lived waste that must eventually be disposed of in deep geological repositories; 3. Deep geological repositories for permanent disposal of high-level radioactive waste, spent fuel from nuclear reactors and all other long-lived waste. For Australian wastes, all three types of facility are needed. Implementation of the first two is a trivial technical challenge - but an immense societal problem, as recent developments in Australia have shown. However, the requirements for siting a deep geological repository for Australia's ELW are very stringent and world-class science is indeed required here. Guaranteeing long-term safety depends upon gaining a good understanding of the deep geological environment

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.)

Safety assessment for the underground disposal of radioactive wastes

International Nuclear Information System (INIS)

1981-01-01

This document is addressed to authorities and specialists responsible for or involved in planning, performing and reviewing safety assessments of underground radioactive waste repositories. It introduces and discusses in a general manner approaches and areas to be considered in making such safety assessments; its emphasis is on repositories for long-lived radioactive wastes in deep geological formations. It is hoped that this document will contribute to providing a base for a common understanding among the authorities and specialists concerned with the numerous studies involving a variety of scientific disciplines. While providing guidance, the document is also intended to stimulate further international discussion on this subject. It is the intention of the IAEA to develop more specific reports providing examples for the application of safety analyses for underground waste disposal

Safety assessment for the underground disposal of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

1981-01-01

This document is addressed to authorities and specialists responsible for or involved in planning, performing and reviewing safety assessments of underground radioactive waste repositories. It introduces and discusses in a general manner approaches and areas to be considered in making such safety assessments; its emphasis is on repositories for long-lived radioactive wastes in deep geological formations. It is hoped that this document will contribute to providing a base for a common understanding among the authorities and specialists concerned with the numerous studies involving a variety of scientific disciplines. While providing guidance, the document is also intended to stimulate further international discussion on this subject. It is the intention of the IAEA to develop more specific reports providing examples for the application of safety analyses for underground waste disposal.

Radioactive waste management - with evidence

International Nuclear Information System (INIS)

1988-01-01

The select committee was appointed to report on the present (1988) situation and future prospects in the field of radioactive waste management in the European Community. The report covers all aspects of the subject. After an introduction the parts of the report are concerned with the control of radiation hazards, the nuclear fuel cycle and radioactive waste, the control of radioactive effluents, storage and disposal of solid radioactive wastes, research programmes, surface storage versus deep geological disposal of long-term wastes, the future of reprocessing and the public debate. Part 10 is a resume of the main conclusions and recommendations. It is recommended that the House of Lords debate the issue. The oral and written evidence presented to the committee is included in the report. (U.K.)

Institutional aspects of radioactive waste management

International Nuclear Information System (INIS)

Strohl, P.

1996-01-01

Rules and regulations in force, the work of specialized agencies and the control exercised by regulatory authorities in the area of radioactive waste management need to emphasised in public information programmes. Radioactive waste management is a well-regulated area, with government institutions aiming for long-term safety, in particular for the final disposal of wastes, and imposing strict obligations on the nuclear industry. The issue of public perception of the problems involved with the long-term safety of radioactive waste management is sensitive. Given the complexity of this issue, and the public's legitimate doubts regarding the continued efficiency of long- or very long-term waste management policies, public information specialists must seek to reassure. The major factors that need to be made clear to the public are the following: our capacity to master long-term risks will depend upon the quality of the decisions taken today; experience has shown that the functioning of institutional mechanisms is generally efficient and permanent when their purpose is to protect society's vital interests; a well-informed public, together with other factors can contribute to the maintenance of these; the importance of the 'passive' safety of technological systems, as well as institutional instruments with respect to guaranteeing long-term safety, must be underlined; institutional instruments, although indispensable with regard to long-term safety, should only be considered as making a contribution of relative importance and of limited duration, and this must be made clear. Public information policies should therefore underline the relative contribution of institutional instruments, as well as their limited duration, in the safety of long-term radioactive waste management. (authors)

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.)

Environmental restoration and management of low-level radioactive and mixed waste at Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Kendrick, C.M.

1994-03-01

Management of radioactive waste at Oak Ridge National Laboratory (ORNL) must address several major challenges. First, contaminants from some disposed wastes are leaching into the groundwater and these disposal sites must be remediated. Second, some of these ``legacy`` wastes, as well as currently generated radioactive wastes, are also contaminated with chemicals, including polychlorinated biphenyls (PCBs), solvents, and metals (i.e., mixed waste). Third, wastes containing long-lived radionuclides in concentrations above established limits have been determined unsuited for disposal on the Oak Ridge Reservation. Reflecting these challenges, ORNL`s strategy for managing its radioactive wastes continues to evolve with the development of improved technologies and site-specific adaptation of some standard technologies.

Assessing inventories of past radioactive waste arisings at Chalk River Laboratories

International Nuclear Information System (INIS)

Csullog, G.W.; TerHuurne, M.A.; Miller, M.T.; Edwards, N.W.; Hulley, V.R.; McCann, D.J.

1998-01-01

' is used to support the management of currently accumulating radioactive wastes and how this same 'warehouse of information' is the basis for the development of a novel way to assess historic waste inventories. Records of waste emplaced into storage facilities at CRL since the mid 1940's are in a variety of formats and the quality of the data recorded is inconsistent. In addition, prior to recent improvements in waste management, wastes that should have been collected and handled separately (short-lived versus long-lived) were usually handled and stored together on the basis of external radiation field not on their requirements for long-term management. As such, the challenge is to assess historic waste management records in the context of today's waste management practices. Recent enhancements to the WIP-III application have provided the tools for this assessment. Historic records are entered into WIP-III 'as-is'. Next, using additional data entry screens, expert interpretation is used to identify historic wastes as similar to a current waste or similar to a mixture of current wastes. Next, the historic waste is assigned the characteristics of a current waste or of a mixture of current wastes, using the 'warehouse of information'. The interpretation process improves the quality of historic waste inventory records, which will allow AECL-CRL to provide defensible estimates of the characteristics of its historic wastes. This paper describes how the interpretation process can be generically applied to any waste site with historic wastes, independently of how those sites manage their current wastes. (author)

Progress in radioactive graphite waste management

International Nuclear Information System (INIS)

2010-07-01

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

Involvement of AVN as TSO in the safety analysis of radioactive waste disposal

International Nuclear Information System (INIS)

Gelder, P. de; Nys, V.; Smidts, O.; Boeck, B. de

2004-01-01

In 1998, ONDRAF/NIRAS, the agency responsible for radioactive waste management in Belgium, was requested by the government to involve the nuclear safety authorities in its activities of safety evaluation of site-specific waste disposal options (deep or surface disposal) for the short-lived low-level waste. A working group was created in which ONDRAF/NIRAS, FANC (the Federal Agency for Nuclear Control) and AVN discuss different aspects of the ONDRAF/NIRAS program concerning the long-term management of short-lived low-level radioactive waste disposal. It includes also the review of technical safety assessments performed by ONDRAF/NIRAS or by contractors for ONDRAF/NIRAS. The involvement of AVN (the Belgian TSO) in the pre-project phase appears to be positive for all partners. Indeed, all felt the need for an independent actor, with a strong technical basis. Through this presentation, the experience and the topics discussed since 1998 will be developed. Mainly, the presentation will focus on the approach followed to develop competency in the radioactive waste field, on the discussions about the development of a regulatory framework adapted to final disposal of low-level radioactive waste, and on the technical regulatory positions developed so far. Also the experience related to the interaction with local stakeholders will be described. (orig.)

Research programme on radioactive wastes

International Nuclear Information System (INIS)

Eckhardt, A.; Hufschmid, P.; Jordi, S.; Schanne, M.; Vigfusson, J.

2009-11-01

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

Public debate on the general options relative to the management of high-medium activity and long-lived radioactive wastes; Debat public sur les options generales en matiere de gestion des dechets radioactifs de haute activite et de moyenne activite a vie longue

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-09-15

The law from December 30, 1991, precisely defines 3 axes of researches for the management of high level and long-lived radioactive wastes: separation/transmutation, surface storage and underground disposal. A global evaluation report about these researches is to be supplied in 2006 by the French government to the Parliament. A first synthesis of the knowledge gained after 14 years of research has led the national commission of the public debate (CNDP) to organize a national debate about the general options of management of high-level and long-lived radioactive wastes before the 2006 date line. This document presents the organizational aspects of the debate: origin, organization committee (mission, members, commitments), framework (the December 31, 1991 law, technical enlargement, society aspects), topics (summary of the debate in ten questions), organization modalities (4 main steps, schedule, venues), objectives and perspectives (sharing information, decision making processes to be implemented by 2006). (J.S.)

The management of radioactive waste

International Nuclear Information System (INIS)

1991-08-01

One of the key questions asked about nuclear power production is whether the industry can manage its waste safely and economically. Management must take account of long term safety, since some radioisotopes take a very long time to decay. This long term decay, which can take millions of years, focused attention for the first time on the need for some wastes to be managed for a very long time beyond the lifetime of those who generated the waste. This paper reviews what the different types of waste are, what the technical consensus is on the requirements for their safe management, and how the present state of knowledge developed. It describes how radioactive waste management is practised and planned within the fuel cycle and indicates the moderate scale of the costs in relation to the total cost of producing electricity. Country annexes give more information about what is being done in a selection of countries, in order to indicate how radioactive waste management is carried out in practice. (Author)

Radioactive wastes in Oklo

International Nuclear Information System (INIS)

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

2006-01-01

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

The radiation protection and the radioactive wastes management

International Nuclear Information System (INIS)

Servais, F.; Woiche, Ch.; Hunin, Ch.

2003-01-01

This chapter concerns the radiation protection in relation with the radioactive waste management. Three articles make the matter of this file, the management of radioactive medical waste into hospitals, a new concept of waste storage on site, the protection devices on the long term with some lessons for the radioactive waste management. (N.C.)

Precision Gamma-Ray Branching Ratios for Long-Lived Radioactive Nuclei

Energy Technology Data Exchange (ETDEWEB)

Tonchev, Anton [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2017-10-19

Many properties of the high-energy-density environments in nuclear weapons tests, advanced laser-fusion experiments, the interior of stars, and other astrophysical bodies must be inferred from the resulting long-lived radioactive nuclei that are produced. These radioactive nuclei are most easily and sensitively identified by studying the characteristic gamma rays emitted during decay. Measuring a number of decays via detection of the characteristic gamma-rays emitted during the gamma-decay (the gamma-ray branching ratio) of the long-lived fission products is one of the most straightforward and reliable ways to determine the number of fissions that occurred in a nuclear weapon test. The fission products ¹⁴⁷Nd, ¹⁴⁴Ce, ¹⁵⁶Eu, and certain other long-lived isotopes play a crucial role in science-based stockpile stewardship, however, the large uncertainties (about 8%) on the branching ratios measured for these isotopes are currently limiting the usefulness of the existing data [1,2]. We performed highly accurate gamma-ray branching-ratio measurements for a group of high-atomic-number rare earth isotopes to greatly improve the precision and reliability with which the fission yield and reaction products in high-energy-density environments can be determined. We have developed techniques that take advantage of new radioactive-beam facilities, such as DOE's CARIBU located at Argonne National Laboratory, to produce radioactive samples and perform decay spectroscopy measurements. The absolute gamma-ray branching ratios for ¹⁴⁷Nd and ¹⁴⁴Ce are reduced <2% precision. In addition, high-energy monoenergetic neutron beams from the FN Tandem accelerator in TUNL at Duke University was used to produce ¹⁶⁷Tm using the ¹⁶⁹Tm(n,3n) reaction. Fourtime improved branching ratio of ¹⁶⁷Tm is used now to measure reaction-in-flight (RIF) neutrons from a burning DT capsule at NIF [10]. This represents the

Prediction of long term stability for geological disposal of radioactive waste

International Nuclear Information System (INIS)

Sasaki, Takeshi; Morikawa, Seiji; Koide, Hitoshi; Kono, Itoshi

1998-01-01

On geological disposal of radioactive wastes, study on prediction of diastrophism has been paid many attentions, and then long term future prediction ranging from some thousands to some tends thousands years may be necessary for some target nuclides. As there are various methods in the future prediction, it is essential to use a computational dynamic procedure to conduct a quantitative prediction. However, it causes an obstacle to advancement of the prediction method that informations on deep underground have a lot of uncertain elements because of their few and indirect data. In this paper, a long term prediction procedure of diastrophism relating to geological disposal of radioactive wastes with low level but isolation terms required to some thousands years was investigated and each one example was shown on flow of the investigation and its modeling method by using the finite element method. It seems to be a key to upgrade accuracy of future diastrophism prediction how an earth fault can be analyzed. And, as the diastrophism is a long term and complex phenomenon and its prediction has many uncertain elements, it is important to judge comprehensively results of its numerical analysis geologically and on rock engineering. (G.K.)

Industrial radioactive wastes: what are we talking about?

International Nuclear Information System (INIS)

Le Bars, Y.

2001-01-01

The subject of radioactive wastes is developed through their origin, their classification, their scale of size. The different storage centers are given and the new channels of radioactive wastes management are tackled. The particular case of high level and long term radioactive wastes is detailed. (N.C.)

Occupational monitoring at radioactive waste deposit

Energy Technology Data Exchange (ETDEWEB)

Pereira, Wagner S.; Cunha, Franklin S. [Indústrias Nucleares do Brasil (COMAP.N/FCN/INB), Resende, RJ (Brazil). Fábrica de Combustível Nuclear. Coordenação de Meio Ambiente e Proteção Radiológica Ambiental; Kelecom, Alphonse [Universidade Federal Fluminense (LARARA-PLS/UFF), Niterói, RJ (Brazil). Lab. de Radiobiologia e Radiometria Pedro Lopes dos Santos; Silva, Ademir X., E-mail: pereiraws@gmail.com, E-mail: wspereira@inb.gov.br, E-mail: franklincunha@inb.gov.br, E-mail: lararapls@hotmail.com, E-mail: Ademir@nuclear.ufrj.br [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (PEN/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

2017-07-01

The Initial Deposit of Low Activity Radioactive Waste - DIRBA is an ancillary facility to the Nuclear Fuel Factory - FCN for the initial storage of low activity radioactive waste generated in the nuclear fuel cycle under the responsibility of the FCN. Currently approximately 460 200-liter drums containing Class 2.3 waste are stored: Waste containing Natural Radionuclides (RBMN-RN). As part of the nuclear licensing of the facility, an area radiological monitoring program was developed with monthly monitoring of 17 exposure points, 3 direct long-distance air sampling points with CAM alpha-7 monitors, monitored in January and 9 points where smears of alpha long half-life emitters were monitored in January. The mean exposure rate between points was 0.5 μSv∙h{sup -1}, with a maximum of 1.27 μSv∙h{sup -1} varying, on average, between 0.98 μSv∙h{sup -1} at point P1 to 0.23 μSv∙h{sup -1} at P11. The monthly average was the same, 0.50 μSv∙h-1, ranging from 0.46 μSv∙h{sup -1} (November) to 0.57 μSv∙h{sup -1} (August). The half-life long-lived alpha sampling were all below the MDA as well as the 9 smears. Regarding the requirements of monitored areas, the deposit must be considered as supervised area, from the point of view of radioprotection. The possibility of tipping the drums or other accidents with spillage of material contained into them caused, in a proactive way, the area to be considered a controlled area. (author)

Minimization and segregation of radioactive wastes

International Nuclear Information System (INIS)

1992-07-01

The report will serve as one of a series of technical manuals providing reference material and direct know-how to staff in radioisotope user establishments and research centres in Member States without nuclear power and the associated range of complex waste management operations. Considerations are limited to the minimization and segregation of wastes, these being initial steps on which the efficiency of the whole waste management system depends. The minimization and segregation operations are examined in the context of the restricted quantities and predominantly shorter lived activities of wastes from nuclear research, production and usage of radioisotopes. Liquid and solid wastes only are considered in the report. Gaseous waste minimization and treatment are specialized subjects and are not examined in this document. Gaseous effluent treatment in facilities handling low and intermediate level radioactive materials has been already the subject of a detailed IAEA report. Management of spent sealed sources has specifically been covered in a previous manual. Conditioned sealed sources must be taken into account in segregation arrangements for interim storage and disposal where there are exceptional long lived highly radiotoxic isotopes, particularly radium or americium. These are unlikely ever to be suitable for shallow land burial along with the remaining wastes. 30 refs, 5 figs, 8 tabs

Radioactive waste management in Switzerland

International Nuclear Information System (INIS)

Hugi, M.

2011-01-01

The Federal Nuclear Safety Inspectorate ENSI is the Supervisory Authority for Nuclear Safety and Security of Swiss Nuclear Facilities. The responsibilities include the evaluation and operational monitoring of the existing five Swiss nuclear power plants, the radioactive waste disposals and the nuclear research facilities. The supervisory area includes project planning, operational issues, and decommissioning of plants. ENSI supervises the formation, handling and storage of radioactive waste, the work on deep geological disposal and the transport of radioactive materials. The disposal of radioactive waste is regulated by the Swiss Nuclear Energy Act (2005) and the Nuclear Energy Ordinance (2005). The protection of humans and the environment must be guaranteed permanently. Waste disposal must be carried out in the own country by deep geological repositories. The licensing procedure for the disposal facilities is concentrated at the federal level, the cooperation of the location canton, neighboring cantons and the neighboring countries is ensured. The general license for the deep geological repository is subject to an optional referendum. The polluter pays principle applies to the disposal of radioactive waste. The waste producers are legally obliged to dispose of them and have founded the National Cooperative for the Storage of Radioactive Waste (Nagra). The federal government is responsible for waste from medicine, industry and research (MIF). The Federal Council approved the waste management certificate for low and intermediate level waste (SMA) in 1988. High-level-waste (HAA) and long-live-intermediate-level-waste (LMA), where approved in 2006. Nagra's disposal concept envisages two separate deep geological repositories for SMA and HAA / LMA in a suitable, tectonically stable, low-permeability rock formation. If a site meets both the SMA and HAA / LMA storage requirements, the selection process may result in a common location for all radioactive waste. Until the

Feasibility of Space Disposal of Radioactive Nuclear Waste. 1: Executive Summary

Science.gov (United States)

1973-01-01

This NASA study, performed at the request of the AEC, concludes that transporting radioactive waste (primarily long-lived isotopes) into space is feasible. Tentative solutions are presented for technical problems involving safe packaging. Launch systems (existing and planned), trajectories, potential hazards, and various destinations were evaluated. Solar system escape is possible and would have the advantage of ultimate removal of the radioactive waste from man's environment. Transportation costs would be low (comparable to less than a 5 percent increase in the cost of electricity) even though more than 100 space shuttle launches per year would be required by the year 2000.

France’s State of the Art Distributed Optical Fibre Sensors Qualified for the Monitoring of the French Underground Repository for High Level and Intermediate Level Long Lived Radioactive Wastes

Directory of Open Access Journals (Sweden)

Sylvie Delepine-Lesoille

2017-06-01

Full Text Available This paper presents the state of the art distributed sensing systems, based on optical fibres, developed and qualified for the French Cigéo project, the underground repository for high level and intermediate level long-lived radioactive wastes. Four main parameters, namely strain, temperature, radiation and hydrogen concentration are currently investigated by optical fibre sensors, as well as the tolerances of selected technologies to the unique constraints of the Cigéo’s severe environment. Using fluorine-doped silica optical fibre surrounded by a carbon layer and polyimide coating, it is possible to exploit its Raman, Brillouin and Rayleigh scattering signatures to achieve the distributed sensing of the temperature and the strain inside the repository cells of radioactive wastes. Regarding the dose measurement, promising solutions are proposed based on Radiation Induced Attenuation (RIA responses of sensitive fibres such as the P-doped ones. While for hydrogen measurements, the potential of specialty optical fibres with Pd particles embedded in their silica matrix is currently studied for this gas monitoring through its impact on the fibre Brillouin signature evolution.

France’s State of the Art Distributed Optical Fibre Sensors Qualified for the Monitoring of the French Underground Repository for High Level and Intermediate Level Long Lived Radioactive Wastes

Science.gov (United States)

Delepine-Lesoille, Sylvie; Girard, Sylvain; Landolt, Marcel; Bertrand, Johan; Planes, Isabelle; Boukenter, Aziz; Marin, Emmanuel; Humbert, Georges; Leparmentier, Stéphanie; Auguste, Jean-Louis; Ouerdane, Youcef

2017-01-01

This paper presents the state of the art distributed sensing systems, based on optical fibres, developed and qualified for the French Cigéo project, the underground repository for high level and intermediate level long-lived radioactive wastes. Four main parameters, namely strain, temperature, radiation and hydrogen concentration are currently investigated by optical fibre sensors, as well as the tolerances of selected technologies to the unique constraints of the Cigéo’s severe environment. Using fluorine-doped silica optical fibre surrounded by a carbon layer and polyimide coating, it is possible to exploit its Raman, Brillouin and Rayleigh scattering signatures to achieve the distributed sensing of the temperature and the strain inside the repository cells of radioactive wastes. Regarding the dose measurement, promising solutions are proposed based on Radiation Induced Attenuation (RIA) responses of sensitive fibres such as the P-doped ones. While for hydrogen measurements, the potential of specialty optical fibres with Pd particles embedded in their silica matrix is currently studied for this gas monitoring through its impact on the fibre Brillouin signature evolution. PMID:28608831

Risk perception, risk evaluation and human values: cognitive bases of acceptability of a radioactive waste repository

Energy Technology Data Exchange (ETDEWEB)

Earle, T.C.; Lindell, M.K.; Rankin, W.L.

1981-07-01

Public acceptance of radioactive waste management alternatives depends in part on public perception of the associated risks. Three aspects of those perceived risks were explored in this study: (1) synthetic measures of risk perception based on judgments of probability and consequences; (2) acceptability of hypothetical radioactive waste policies, and (3) effects of human values on risk perception. Both the work on synthetic measures of risk perception and on the acceptability of hypothetical policies included investigations of three categories of risk: (1) Short-term public risk (affecting persons living when the wastes are created), (2) Long-term public risk (affecting persons living after the time the wastes were created), and (3) Occupational risk (affecting persons working with the radioactive wastes). The human values work related to public risk perception in general, across categories of persons affected. Respondents were selected according to a purposive sampling strategy.

Geological storage of radioactive waste

International Nuclear Information System (INIS)

Barthoux, A.

1983-01-01

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

Regulatory document R-104, Regulatory objectives, requirements and guidelines for the disposal of radioactive wastes - long-term aspects

International Nuclear Information System (INIS)

1987-01-01

The purpose and scope of this document is to present the regulatory basis for judging the long-term acceptability of radioactive waste disposal options. The basic objectives of radioactive waste disposal are given as are the regulatory requirements to be satisfied. (NEA)

Technologies for destruction of long-lived radionuclides in high-level nuclear waste - overview and requirements

International Nuclear Information System (INIS)

Arthur, E.D.

1993-01-01

A major issue surrounding current nuclear power generation is the management and disposal of long-lived, high-level waste (HLW). The planned and scientifically acceptable destination for this waste is in deep underground, geologically stable, repositories. However, public concerns surrounding such disposal of long-lived nuclear wastes and other issues such as proliferation and safety negatively affect the potential role that nuclear power can play in meeting current and future national energy needs. This paper and this topical session on nuclear waste minimization, management, and remediation focus on two nuclear systems and their associated technologies that have the potential to address concerns surrounding long-lived radionuclides in HLW. Both systems offer technology applicable to HLW from current light water reactors (LWRs). In addition, these systems represent advanced nuclear power concepts that have important features associated with integrated management of wastes long-term fuel supplies, and enhanced safety. The first system is the integral fast reactor (IFR) concept. This system incorporates a metal-fueled fast reactor coupled with chemical separations based on pyroprocessing to produce power while burning long-lived actinide waste. The IFR applications include the burning of actinides from current LWR spent fuel and energy production in a breeder environment. The second concept, accelerator transmutation of waste (ATW), is based on an accelerator-induced intense source of thermal neutrons and is aimed at the destruction of long-lived actinides and fission products. This concept can be applied to long-lived radionuclides in spent-fuel HLW as well as a future fission power source built around use of natural thorium or uranium as fuels coupled with concurrent waste destruction

Current and perspective on the radioactive waste management at territory of the Kola Peninsula

International Nuclear Information System (INIS)

Amazova, Ludmila

1999-01-01

According to this presentation, 25 thousand cubic metres of solid radioactive waste of one million Ci activity has accumulated in the Murmansk Region because of previous civilian and military activities and more will come as a result of the coming decommissioning of nuclear submarines and nuclear power plants. Only a part of the solid radioactive waste is reprocessed at the Kola nuclear power plant and at the repairing and technological enterprise Atomflot. Compaction and incineration are used to decrease the volume of waste. An incineration facility at Atomflot fails to satisfy new requirements and even releases more radioactivity to the atmosphere than what used to come from the Kola nuclear power plant operation. Solid radioactive waste is stored non-reprocessed Spetscombinat special plant Radon. This plant collects and stores radioactive waste produced by the civil industry and at the bases of the Northern Fleet. It is emphasised, however, that during the observation period there were no cases of dangerous increase in radioactivity in the atmosphere. Soil and vegetation contamination by long-lived radionuclides was at the background level. The establishment of a common reprocessing and regional storage facility for long-term storage has been proposed by the Ministry for Atomic Energy

R and D developments on the disposal of radioactive wastes recently carried out at CEA (France)

International Nuclear Information System (INIS)

Petit, J.C.

1993-01-01

Since the law of december 31, 1991 voted by the French Parliament, disposal in geological formations is not the sole option considered for the management of radioactive wastes. Scientists and engineers, notably within the 'Commissariat a l'Energie Atomique' (CEA), must investigate in parallel two other options, namely i. advanced separation of long-lived radioisotopes and transmutation, and ii. improvement of radioactive waste matrices and long-term storage. Still, the geological disposal of radioactive wastes, which has generated within the last decade an immense amount of Research and Development, remains a major proposed solution to the long-term management of transuranic and high-level wastes. In this paper, we will describe some of the Research and Development carried out within CEA, avoiding the industrial and engineering aspects of the issues dealt with. Rather, we will illustrate major points of our basic research, underlining in particular methodological considerations

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

International Nuclear Information System (INIS)

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

2003-01-01

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

Managing radioactive waste safely. Proposals for developing a policy for managing solid radioactive waste in the UK

International Nuclear Information System (INIS)

2001-09-01

More than 10,000 tonnes of radioactive waste are safely stored in the UK, but await a decision on their long-term future. This will increase to 250,000 tonnes when nuclear material currently in use is converted into solid waste. Even if no new nuclear power plants are built and reprocessing of spent nuclear fuel ends when existing plants reach the end of their working lives, about another 250,000 tonnes of waste will arise during the clean-up of those plants over the next century. Most of this waste results from the work of Government agencies or publicly owned companies since the 1940s. Some of the substances involved will be radioactive and potentially dangerous for hundreds of thousands of years. There are much larger amounts of low-level (less radioactive) waste. Currently, these are disposed of at a special surface repository in Cumbria. But again, much larger amounts will arise as existing nuclear facilities are cleaned up. We must decide how to manage this waste in the long term. Implementing that decision will take decades. So now is the time to start planning for our future. In this paper, the UK Government and the Devolved Administrations for Scotland, Wales and Northern Ireland are launching a national debate which will lead up to that decision, and beyond it. The aim is to develop, and implement, a UK nuclear waste management programme which inspires public support and confidence. To do this, we propose a major programme of research and public discussion, using many techniques - some traditional, some relatively new - to stimulate informed discussion, and to involve as many people and groups as possible. We want to inspire public confidence in the decisions and the way in which they are implemented. To do that, we have to demonstrate that all options are considered; that choices between them are made in a clear and logical way; that people's values and concerns are fully reflected in this process; and that information we provide is clear, accurate

Decree of the 23 February 2017 in application of the decree nr 2017-231 of the 23 February 2017 in application of the article L. 542-1-2 of the Code of the Environment, and establishing prescriptions of the National Plan of Management of Radioactive Materials and Wastes

International Nuclear Information System (INIS)

Royal, Segolene

2017-01-01

This decree defines legal arrangements about the implementation of the French national plan of management of radioactive materials and wastes (PNGMDR). It contains some general arrangements, issues related to radioactive materials (depleted uranium, uranium from reprocessing, plutonium and spent fuels, thorium-containing materials), and issues related to the long term management of radioactive wastes. These issues notably concern historical storages and the different types of radioactive wastes: very low level radioactive wastes, short lived low and intermediate level wastes, long-lived intermediate level wastes, long-lived high and intermediate level wastes, radioactive wastes requiring specific works such as mercury-containing wastes, organic liquids and oils, tritiated wastes, and so on, and uranium tailings

Your radioactive garden

International Nuclear Information System (INIS)

Marshall, W.G.

1986-01-01

The booklet on radiation risks from nuclear waste is based on lectures given by the author at Westminster School (United Kingdom) and elsewhere during 1986. A description is given of naturally-occurring radioactivity, and the health risks due to this radiation. The types of radioactive wastes produced by the nuclear industry are described, including low-level wastes, short-lived and long-lived intermediate-level wastes, and high level wastes. These wastes are discussed with respect to their potential health risks and their disposal underground. (U.K.)

Issues and Experiences on Radioactive Waste Quality Control / Quality Assurance with Regard to Future Disposal

International Nuclear Information System (INIS)

Beckmerhagen, I.; Brennecke, P.; Steyer, S.; Bandt, G.

2006-01-01

In the Federal Republic of Germany all types of radioactive waste (short-lived, long-lived) are to be disposed of in deep geological formations. Thus, the safe management of radioactive waste presupposes an appropriate conditioning of primary waste-to-waste packages suitable for emplacement in a repository as well as the documentation of pre-treatment, processing and packaging steps and the waste package characteristics being relevant for disposal. Due to the operation, decommissioning and dismantling of nuclear facilities as well as the application of radioisotopes in industry, medicine and research and development radioactive waste continuously arises in Germany. In order to manage this waste different measures and procedures regarding its conditioning and quality control/quality assurance were introduced and since many years successfully applied. Waste conditioning is especially characterized by a flexible application of the Konrad waste acceptance requirements. The rationale for this approach is due to the present non-availability of a repository in Germany. Several examples of a 'tailor-made' application of the waste acceptance requirements in treatment, conditioning and documentation processes as well as the quality assurance/quality control processes illustrate the current German approach. (authors)

Disposal and environmental assessment of solid waste and radioactive waste

International Nuclear Information System (INIS)

Tan Chenglong

2000-01-01

Along with the development of economic construction, the industrial and agricultural production, military and scientific activities of human being, large amounts of solid and radioactive wastes have been produced, causing serious pollution of ecologic environments and living space of human being itself. To assess and administer the solid and radioactive wastes in geologic-ecologic environments are duty-bound responsibilities of modern geologists and the focus of recent geo-ecologic work

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

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.)

Decontamination processes for low level radioactive waste metal objects

International Nuclear Information System (INIS)

Longnecker, E.F.; Ichikawa, Sekigo; Kanamori, Osamu

1996-01-01

Disposal and safe storage of contaminated nuclear waste is a problem of international scope. Although the greatest volume of such waste is concentrated in the USA and former Soviet Union, Western Europe and Japan have contaminated nuclear waste requiring attention. Japan's radioactive nuclear waste is principally generated at nuclear power plants since it has no nuclear weapons production. However, their waste reduction, storage and disposal problems may be comparable to that of the USA on an inhabited area basis when consideration is given to population density where Japan's population, half that of the USA, lives in an area slightly smaller than that of California's. If everyone's backyard was in California, the USA might have insoluble radioactive waste reduction, storage and disposal problems. Viewing Japan's contaminated nuclear waste as a national problem requiring solutions, as well as an economic opportunity, Morikawa began research and development for decontaminating low level radioactive nuclear waste seven years ago. As engineers and manufacturers of special machinery for many years Morikawa brings special electro/mechanical/pneumatic Skills and knowledge to solving these unique problems. Genden Engineering Services and Construction Company (GESC), an affiliate of Japan Atomic Power Company, recently joined with Morikawa in this R ampersand D effort to decontaminate low level radioactive nuclear waste (LLW) and to substantially reduce the volume of such nuclear waste requiring long term storage. This paper will present equipment with both mechanical and chemical processes developed over these several years by Morikawa and most recently in cooperation with GESC

A HOLISTIC APPROACH FOR DISPOSITION OF LONG-LIVED RADIOACTIVE MATERIALS

Energy Technology Data Exchange (ETDEWEB)

Eriksson, Leif G.; Dials, George E.; Parker, Frank L.

2003-02-27

During the past 45 years, one of the most challenging scientific, engineering, socio-economic, and political tasks and obligations of our time has been to site and develop technical, politically acceptable, solutions to the safe disposition of long-lived radioactive materials (LLRMs). However, at the end of the year 2002, the Waste Isolation Pilot Plant (WIPP) site in the United States of America (USA) hosts the world's only operating LLRM-disposal system, which (1) is based on the LLRM-disposal principles recommended by the National Academy of Sciences (NAS) in 1957, i.e., deep geological disposal in a ''stable'' salt vault/repository, (2) complies with the nation's ''Environmental Radiation Protection Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes'', and (3) may receive 175,584 cubic meters (m3) of transuranic radioactive waste (TRUW)a. Pending the scheduled opening of repositories for once-used nuclear fuel (OUNF) in the USA, Sweden, and Finland in the years 2010, 2015, and 2017, respectively, LLRM-disposal solutions remain the missing link in all national LLRM-disposition programs. Furthermore, for a variety of reasons, many nations with nuclear programs have chosen a ''spectator'' stance in terms of enhancing the global nuclear safety culture and the nuclear renaissance, and have either ''slow-tracked'' or deferred their LLRM-disposal programs to allow time for an informed national consensus to evolve based on LLRM-disposition experiences and solutions gained elsewhere. In the meantime, LLRMs will continue to amass in different types and levels of safeguarded storage facilities around the world. In an attempt to contribute to the enhancement of the global nuclear safety culture and the nuclear renaissance, the authors developed the sample holistic approach for synergistic disposition of LLRMs comprising LLRM

Intended long term performances of cementitious engineered barriers for future storage and disposal facilities for radioactive wastes in Romania

Directory of Open Access Journals (Sweden)

Sociu F.

2013-07-01

Full Text Available Considering the EU statements, Romania is engaged to endorse in the near future the IAEA relevant publications on geological repository (CNCANa, to update the Medium and Long Term National Strategy for Safe Management of Radioactive Waste and to approve the Road Map for Geological Repository Development. Currently, for example, spent fuel is wet stored for 6 years and after this period it is transported to dry storage in MACSTOR-200 (a concrete monolithic module where it is intended to remain at least 50 years. The present situation for radioactive waste management in Romania is reviewed in the present paper. Focus will be done on existent disposal facilities but, also, on future facilities planned for storage / disposal of radioactive wastes. Considering specific data for Romanian radioactive waste inventory, authors are reviewing the advance in the radioactive waste management in Romania considering its particularities. The team tries to highlight the expected limitations and unknown data related with cementitious engineered barriers that has to be faced in the near future incase of interim storage or for the upcoming long periods of disposal.

Measurement methodology for fulfilling of waste acceptance criteria for low and intermediate level radioactive waste in storages - 59016

International Nuclear Information System (INIS)

Sokcic-Kostic, M.; Langer, F.; Schultheis, R.

2012-01-01

with half life longer than Cs-137, whereas intermediate level waste is sub-classified as short lived waste and long lived waste. Long lived isotopes are mainly alpha emitters which result from contamination of the RAW by nuclear fuel material and its fission and breeding products. The sub-classification is made on base of mass specific alpha activity of the waste. Before being sent to storage the waste has to be treated. This includes volume reduction by combustion or compaction, depending on the physical properties of the waste, as well as immobilisation by grouting, saving thereby storage space and costs. After the treatment the waste is filled into packages preferably drums or containers. Before the waste is sent to the waste storage a passport is generated which includes all relevant data to show that the waste package fulfils the requirements as defined by the waste storage operating company. NUKEM Technologies has developed a large number of monitors for a radiological waste characterisation. The preferred methods are non-destructive, allowing high throughput and giving detailed information. Parameters that cannot be measured after treatment, have to be measured during the treatment process or data has to be collected from available sources like the origin of the waste or from the waste deliverer. To optimise this process NUKEM Technologies has developed a tracking system which traces the waste during treatment starting from delivery and finishing by the transportation to the final storage. (authors)

Radioactive waste management

International Nuclear Information System (INIS)

Strohl, P.

1985-01-01

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

No 2906. Proposal of law with the aim of organizing the durable management of radioactive wastes; No 2906. Proposition de loi tendant a organiser la gestion durable des dechets radioactifs

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-02-15

This proposal of law is the result of a long thinking enriched by 15 years of reports preparation, workshops and exchange with foreign organizations in charge of radioactive waste management, mainly carried out in the framework of the December 30, 1991 law. This proposal of law deals with the following points: general conditions of the management of radioactive wastes, rules relative to the reprocessing of foreign wastes, national plan for the management of radioactive wastes, creation of a national commission of evaluation of the research work on the management of high-activity and long-lived radioactive wastes, creation of a funds for the financing of the research and the industrial management of radioactive wastes, the three complementary methods of waste management for the high-activity and long-lived wastes, date lines for the implementation of a first experimental reactor for transmutation, for a long duration surface or sub-surface storage facility and for a reversible disposal center, concerting obligation with people's representatives and creation of a public interest group, financial contribution allocated to territory authorities, radioactive wastes proprietorship, creation of a local information and follow-up committee for radioactive waste facilities, and eventual charge compensations relative to the implementation of this law. (J.S.)

Technologies for destruction of long-lived radionuclides in high-level nuclear waste: Overview and requirements

International Nuclear Information System (INIS)

Arthur, E.D.

1993-01-01

This paper, and this topical session on Nuclear Waste Minimization, Management and Remediation, focuses on two nuclear systems, and their associated technologies, that have the potential to address concerns surrounding long-lived radionuclides in high-level waste. Both systems offer technology applicable to HLW from present light-water reactors (LWR). Additionally these systems represent advanced nuclear power concepts that have important features associated with integrated management of wastes, long-term fuel supplies, and enhanced safety. The first system is the Integral Fast Reactor (IFR) concept. This system incorporates a metal-fueled fast reactor coupled with chemical separations based on pyroprocessing to produce power while simultaneously burning long-lived actinide waste. IFR applications include burning of actinides from current LWR spent fuel and energy production in a breeder environment. The second concept, Accelerator Transmutation of Waste (ATW), is based upon an accelerator-induced intense source of thermal neutrons and is aimed at destruction of long-lived actinides and fission products. This concept can be applied to long-lived radionuclides in spent fuel HLW as well as a future fission power source built around use of natural thorium or uranium as fuels coupled with concurrent waste destruction

Long-term management of radioactive waste - will the Price-Anderson system work for third party liability issues arising from the Nuclear Waste Policy Act of 1982

International Nuclear Information System (INIS)

Kuznick, S.K.

1985-01-01

Two pieces of legislation have been enacted in the United States to provide a framework for the management of radioactive waste and spent nuclear fuel: the Low-level Radioactive Waste Policy Act (1980) and the Nuclear Waste Policy Act of 1982. Neither of these statutes provide a means for resolving third party liability issues arising out of radioactive waste management. However, the Price Anderson Act (originally enacted in 1957) provides a system of financial protection that can be applied to waste management activities and that can resolve most issues pertaining to liability for nuclear damage that may result from long-term management of radioactive waste and spent nuclear fuel. (NEA) [fr

Classification of radioactive wastes produced by the nuclear industry

International Nuclear Information System (INIS)

2013-01-01

This document first indicates the origins of radioactive wastes (mainly electronuclear industry), and the composition of spent fuel, and that only fission products and minor actinides are considered as radioactive wastes whereas uranium and plutonium can be used as new fuel after recycling. The classification of radioactive wastes is indicated in terms of radioactivity level and radionuclide half-life: high level (0.2 per cent of the total waste volume but 96 per cent of total waste radioactivity), medium level long life (3 per cent of volume, 4 per cent of radioactivity), low level long life (7 per cent of volume, 0.1 per cent of radioactivity), low and medium level and short life (63 per cent of volume and 0.02 per cent of radioactivity), very low level (27 per cent of volume and less than 0.01 per cent of radioactivity). An overview of radioactive waste processing and storage in France is presented for each category. Current and predicted volumes are indicated for each category. The main challenges are briefly addressed: spent fuel recycling, waste valorisation by fourth-generation reactors. Processing locations in France and in the World are indicated. Some key figures are provided: 2 kg of radioactive waste are produced per inhabitant and per year, and waste management costs represent 5 per cent of the total cost of produced electricity

Clays in natural and engineered barriers for radioactive waste confinement

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-07-01

Andra organised an International Symposium on the use of Natural and Engineered Clay-based Barriers for the Containment of Radioactive Waste hold at the Congress Centre of Tours, France, in March 2005. The symposium provided an opportunity to take stock of the potential properties of the clay-based materials present in engineered or natural barriers in order to meet the containment specifications of a deep geological repository for radioactive waste. It was intended for specialists working in the various disciplines involved with clays and clay based minerals, as well as scientists from agencies and organisations dealing with investigations on the disposal of high-level and long-lived radioactive waste. The themes of the Symposium included geology, geochemistry, transfers of materials, alteration processes, geomechanics, as well as the recent developments regarding the characterisation of clays, as well as experiments in surface and underground laboratories. The symposium consisted of plenary sessions, parallel specialized sessions and poster sessions. (author)

Estimation of long-term probabilities for inadvertent intrusion into radioactive waste management areas

International Nuclear Information System (INIS)

Eedy, W.; Hart, D.

1988-05-01

The risk to human health from radioactive waste management sites can be calculated as the product of the probability of accidental exposure (intrusion) times the probability of a health effect from such exposure. This report reviews the literature and evaluates methods used to predict the probabilities for unintentional intrusion into radioactive waste management areas in Canada over a 10,000-year period. Methods to predict such probabilities are available. They generally assume a long-term stability in terms of existing resource uses and society in the management area. The major potential for errors results from the unlikeliness of these assumptions holding true over such lengthy periods of prediction

Determination of annual limit of intake for long-lived radioactive dust

International Nuclear Information System (INIS)

Ching, S.H.; Horvath, F.J.

1989-08-01

A method for the determination of the annual limit on intake (ALI) for long-lived radioactive dust that is associated with every step in the uranium production process is proposed. It is based on methodology indicated in ICRP 26. A sample calculation for the ALI of fresh yellowcake is provided to assist in explaining this method

Greater-confinement disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

Trevorrow, L.E.; Gilbert, T.L.; Luner, C.; Merry-Libby, P.A.; Meshkov, N.K.; Yu, C.

1985-01-01

Low-level radioactive wastes include a broad spectrum of wastes that have different radionuclide concentrations, half-lives, and physical and chemical properties. Standard shallow-land burial practice can provide adequate protection of public health and safety for most low-level wastes, but a small volume fraction (about 1%) containing most of the activity inventory (approx.90%) requires specific measures known as ''greater-confinement disposal'' (GCD). Different site characteristics and different waste characteristics - such as high radionuclide concentrations, long radionuclide half-lives, high radionuclide mobility, and physical or chemical characteristics that present exceptional hazards - lead to different GCD facility design requirements. Facility design alternatives considered for GCD include the augered shaft, deep trench, engineered structure, hydrofracture, improved waste form, and high-integrity container. Selection of an appropriate design must also consider the interplay between basic risk limits for protection of public health and safety, performance characteristics and objectives, costs, waste-acceptance criteria, waste characteristics, and site characteristics. This paper presents an overview of the factors that must be considered in planning the application of methods proposed for providing greater confinement of low-level wastes. 27 refs

Long term industrial management of radioactive wastes in France

International Nuclear Information System (INIS)

Lavie, J.

1981-01-01

All human activities including energy generation entail the wastes. This definitely applies also to nuclear power generation. Currently the nuclear power program is very extensive, and the plans of fuel reprocessing proceed along this line. In consequence, the Government has decided on tackling the problem of industrial radioactive waste management in earnest. For the purpose, the National Radioactive Waste Management Agency (ANDRA) was created in November, 1979, within the French Atomic Energy Commission (CEA). Its main functions are the design, siting and construction of waste disposal centers and their management, the establishment of waste treatment and disposal standards, and the research and development. The following matters are described: the need for comprehensive industrial approach, the concept of industrial management, ANDRA business program, the industrial policy on waste disposal, and ANDRA financing. (J.P.N.)

Method of solidifying radioactive solid wastes

International Nuclear Information System (INIS)

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

1984-01-01

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

Low-level radioactive waste management in France: two decades of experience

International Nuclear Information System (INIS)

Marque, Y.

1993-01-01

Human activities generate wastes and these wastes have potential impacts on our environment and important implications for the twilight years of the twentieth century. Radioactive wastes, in particular, is a matter of considerable concern to the public, with emotional debate often clouding the legitimate need of the public for information for the subject. In France, the development of the nuclear power program and the widespread use of radioisotopes by the medical profession, industry and the research community called for a radioactive waste management program. In 1979, the French Government created ANDRA, the National Radioactive Waste Management Agency, which has the complete responsibility for radioactive waste disposal, including design, siting, construction and operation of waste disposal facilities. In 1991, the Waste Law reaffirmed ANDRA's principle functions and created the National Waste Observatory within ANDRA, whose the mission is to establish and maintain a current inventory of all radioactive waste storage and disposal sites on French territory. The present paper describes the generation of short-lived waste in France, the french policy on short-lived waste disposal, operation and cancellation of Manche plant, design and construction of Aube plant

Emerging concepts and requirements for the long-term management of non-radioactive hazardous wastes - would geological disposal be an appropriate solution for some of these wastes

International Nuclear Information System (INIS)

Rein, K. von

1994-01-01

This work deals with the emerging concepts and requirements for the long-term management of non-radioactive hazardous wastes. After some generalities on the pollution of natural environment and the legislations taken by the swedish government the author tries to answer to the question : would geological disposal be an appropriate solution for the non-radioactive hazardous wastes? Then is given the general discussion of the last three articles concerning the background to current environmental policies and their implementation and more particularly the evolution and current thoughts about environmental policies, the managing hazardous activities and substances and the emerging concepts and requirements for the long-term management of non-radioactive hazardous wastes. Comments and questions concerning the similarity or otherwise between the present position of radioactive waste disposal and the background to current environmental policies are indicated. (O.L.)

Radioactive wastes: present problems and future prospects

International Nuclear Information System (INIS)

Gauvenet, Andre

1975-01-01

The main characteristics of radioactive wastes are described and the present problems arising from liquid or gas effluents are considered. It is concluded that nuclear power stations are considerably less pollutant, at equal capacity, than conventional power stations. Programs of investigation are now being developed to meet with the foreseeable increase of activity. The problem is: first, to maintain absorbed doses at their present level and second, to study the problem of long-lived elements the storage of which would, in the long run create a nuisance on a world scale. The different waste storage techniques now in use are described and current investigations and works are exposed some of which, like vitrification, have already begun to be put into application. After having noted that the problem of wastes constitutes doubtless a difficulty in the technical field and, maybe even more so in the psychological field, the conditions are defined which will have to be met in order that this problem should not hinder the short- and long-term development of nuclear energy [fr

Occupational and Public Exposure During Normal Operation of Radioactive Waste Disposal Facilities

Directory of Open Access Journals (Sweden)

M. V. Vedernikova

2017-01-01

Full Text Available This paper focuses on occupational and public exposure during operation of disposal facilities receiving liquid and solid radioactive waste of various classes and provides a comparative analysis of the relevant doses: actual and calculated at the design stage. Occupational and public exposure study presented in this paper covers normal operations of a radioactive waste disposal facility receiving waste. Results: Analysis of individual and collective occupational doses was performed based on data collected during operation of near-surface disposal facilities for short-lived intermediate-, lowand very low-level waste in France, as well as nearsurface disposal facilities for long-lived waste in Russia. Further analysis of occupational and public doses calculated at the design stage was completed covering a near-surface disposal facility in Belgium and deep disposal facilities in the United Kingdom and the Nizhne-Kansk rock massive (Russia. The results show that engineering and technical solutions enable almost complete elimination of internal occupational exposure, whereas external exposure doses would fall within the range of values typical for a basic nuclear facility. Conclusion: radioactive waste disposal facilities being developed, constructed and operated meet the safety requirements effective in the Russian Federation and consistent with relevant international recommendations. It has been found that individual occupational exposure doses commensurate with those received by personnel of similar facilities abroad. Furthermore, according to the forecasts, mean individual doses for personnel during radioactive waste disposal would be an order of magnitude lower than the dose limit of 20 mSv/year. As for the public exposure, during normal operation, potential impact is virtually impossible by delaminating boundaries of a nuclear facility sanitary protection zone inside which the disposal facility is located and can be solely attributed to the use

Database for long lived radionuclides (LLRN). CEA working group report

International Nuclear Information System (INIS)

2003-01-01

This report constitutes a data base for long lived radionuclides (with half lives ranging from 30 to 10 14 years) presenting informations on seven different topics: 'Radioactive data' gathers fundamental data characterising radioactive properties of considered radionuclides (half-life, disintegration mode, radiation energy,...); 'Formation and inventory' collects data on radionuclide formation ways as well as quantities formed during fuel irradiation; 'Biological effects' gives data characterising both radiotoxicity for each radionuclide and chemical toxicity for the considered element; 'Partitioning' specifies element repartition according to the different ways of Purex reprocessing and complementary partitioning processes possible for isolating chemical elements corresponding to the considered radionuclides; 'Transmutation' provides data allowing in part to evaluate the feasibility and destruction performances of radionuclides by transmutation with neutrons; 'Behaviour in waste packages' gathers some data relative to the properties of waste packages confinement. Only data on vitrified waste packages are given there; 'Behaviour in diluted solution' provides data used for element migration calculations. (author)

Concentration Limits in the Cement Based Swiss Repository for Long-lived, Intermediate-level Radioactive Wastes (LMA)

International Nuclear Information System (INIS)

Berner, Urs

1999-12-01

The Swiss repository concept for long-lived, intermediate-level radioactive wastes (LMA), in Swiss terminology) foresees cylindrical concrete silos surrounded by a ring of granulated bentonite to deposit the waste. As one of the possible options and similar to the repository for high level wastes, the silos will be located in a deep crystalline host rock. Solidified with concrete in steel drums, the waste is stacked into a silo and the silo is then backfilled with a porous mortar. To characterize the release of radionuclides from the repository, the safety assessment considers first the dissolution into the pore water of the concrete, and then diffusion through the outer bentonite ring into the deep crystalline groundwater. For 19 safety relevant radionuclides (isotopes of U, Th, Pa, Np, Pu, Am, Ni, Zr, Mo, Nb, Se, Sr, Ra, Tc, Sn, I, C, Cs, Cl) the report recommends maximum elemental concentrations to be expected in the cement pore water of the particularly considered repository. These limits will form the parameter base for subsequent release model chains. Concentration limits in a geochemical environment are usually obtained from thermodynamic equilibrium calculations performed with geochemical speciation codes. However, earlier studies revealed that this procedure does not always lead to reliable results. Main reasons for this are the complexity of the systems considered, as well as the lacking completeness of, and the uncertainty associated with the thermodynamic data. To improve the recommended maximum concentrations for a distinct repository design, this work includes additional design- and system-dependent criteria. The following processes, inventories and properties are considered in particular: a) recent experimental investigations, particularly from cement systems, b) thermodynamic model calculations when reliable data are available, c) total inventories of radionuclides, d) sorption- and co-precipitation processes, e) dilution with stable isotopes, f

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.)

The fixation of radioactive wastes in cement

International Nuclear Information System (INIS)

Kulichenko, V.V.; Dukhovich, F.S.; Volkova, O.I.; Boyarinova, M.V.

1976-01-01

The authors study the leaching behaviour of the main long-lived fission products 90 Sr and 137 Cs. It is found that 90 Sr and 137 Cs have high elution values, namely (2-12) x 10 -2 resp. (2-6) x 10 -2 g/cm 2 /24h, independently of the type of waste. On the basis of these results, maximum concentrations for the solutions in the cement/solution mixtures are proposed. Further studies relate to the formation of radiolysis gas in the waste fixed to cement. Experiments are described to make use of the empty space in the containers, filled with solid waste by filling them with mixtures of cement and liquid radioactive waste of 10 -4 to 1- 6 Ci. The ratio solution/cement should amount to 0.5. The containers are then buried underground. This method of combined waste storage helped to reduce the cost for the storage of liquid waste by about 40-50%. (RB) [de

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.)

Nuclear power and radioactive waste

International Nuclear Information System (INIS)

Grimston, M.

1991-03-01

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

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

Current situation with the centralized storage facilities for non-power radioactive wastes in Latin American countries

International Nuclear Information System (INIS)

Benitez, Juan C.; Salgado, Mercedes; Idoyaga Navarro, Maria L.; Escobar, Carolina; Mallaupoma, Mario; Sbriz, Luciano; Moreno, Sandra; Gozalez, Olga; Gomez, Patricia; Mora, Patricia; Miranda, Alberto; Aguilar, Lola; Zarate, Norma; Rodriguez, Carmen

2008-01-01

Full text: Several Latin American (LA) countries have been firmly committed to the peaceful applications of ionizing radiations in medicine, industry, agriculture and research in order to achieve socioeconomic development in diverse sectors. Consequently the use of radioactive materials and radiation sources as well as the production of radioisotopes and labeled compounds may always produce radioactive wastes which require adequate management and, in the end, disposal. However, there are countries in the Latin American region whose radioactive waste volumes do not easily justify a national repository. Moreover, such facilities are extremely expensive to develop. It is unlikely that such an option will become available in the foreseeable future for most of these countries, which do not have nuclear industries. Storage has long been incorporated as a step in the management of radioactive wastes. In the recent years, there have been developments that have led some countries to consider whether the roles of storage might be expanded to provide longer-term care of long-live radioactive wastes The aim of this paper is to discuss the current situation with the storage facilities/conditions for the radioactive wastes and disused sealed radioactive sources in Latin-American countries. In some cases a brief description of the existing facilities for certain countries are provided. In other cases, when no centralized facility exists, general information on the radioactive inventories and disused sealed sources is given. (author)

Radioactive wastes

International Nuclear Information System (INIS)

Teillac, J.

1988-01-01

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

Management of radioactive waste from nuclear applications

International Nuclear Information System (INIS)

1997-01-01

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

Supercompaction of radioactive waste at NPP Krsko

International Nuclear Information System (INIS)

Fink, K.; Sirola, P.

1996-01-01

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

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

Long-time leaching on full size radioactive waste blocks

International Nuclear Information System (INIS)

Bernard, Andre; Nomine, J.-C.; Cornec, Georges; Bonnet, Andre; Farges, Louis.

1980-12-01

Leaching is generally accepted as the fundamental characteristic when judging the quality of radioactive waste packaging. Long duration leaching tests have been carried out on full size waste blocks at the Commissariat a l'Energie Atomique. The monoliths studied are 200 litre cylinders made up of α, β and γ emitting liquid or solid waste embedded in cement or bitumen. Leaching takes place in accordance with rules based on I.A.E.A. recommendations embodying the specific concerns of safety and radiological capacity of storage sites. The tests are carried out at a Testing Station purpose built at Saclay. It includes several loops with instrumentation (volume: 3000 litres). The counting and analyses of the leached products have enabled the aggregated released fractions of the radionuclides and the structural and chemical modifications of the matrices to be assessed. The fractions of 137 Cs and 239 Pu released at 18 months are 10 -2 and 5x10 -6 for the cement coated wastes, and 10 -4 and 10 -5 for the bitumen coated wastes. The evaluation of the changes in the matrices made it possible, in particular, to observe the start of carbonation in the cement coated wastes. These trials are to be pursued for several years so as to obtain a better understanding of the exchange mechanics between the packaged wastes and the environment [fr

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

Mental Models of Radioactivity and Attitudes towards Radioactive Waste

International Nuclear Information System (INIS)

Zeleznik, N.

2010-01-01

Siting of a radioactive waste repository presents a great problem in almost every country that produces such waste. The main problem is not a technical one, but socio-psychological, namely the acceptability of this kind of repository. Previous research on people's perception of the LILW repository construction, their attitudes towards radioactive waste, their willingness to accept it, indicated significant differences in answers of experts and lay persons, mainly regarding evaluation of the consequences of repository construction. Based on the findings of pilot investigations a mental model approach to the radioactivity, radioactive waste and repository was used as a method for development better risk communication strategies with local communities. The mental models were obtained by adjustment of the method developed by Morgan and co-workers where expert model of radioactivity is compared with mental model of lay people obtained through individual opened interviews. Additional information on trust, risk perception, role of main actors in the site selection process and their credibility was gained with the overall questionnaire on the representative sample of Slovenian population. Results of the survey confirm some already known findings, in addition we gained new cognitions and with analyses obtained the relationships and ratios between different factors, which are characteristics both for the general public and for the public, which is involved in the site selection process for a longer period and has been living beside a nuclear power plant for one generation. People have in general negative associations regarding the repository, the perceived risk for nuclear facilities is high, and trust in representatives of governmental institutions is low. Mental models of radioactivity, radioactive waste and the LILW repository are mostly irregular and differ from the experts' models. This is particularly valid for the models of radioactivity and the influences of

Clay 2001 dossier: progress report on feasibility studies and research into deep geological disposal of high-level, long-lived waste

International Nuclear Information System (INIS)

2001-12-01

A French Act of Parliament passed on 30 December 1991 set out the main areas of research required to prepare solutions for the long-term management of high-level, long-lived radioactive waste. The three avenues of research listed in the Act included a feasibility study of the deep geological disposal of these waste, with responsibility for steering the study given to ANDRA, France National Agency for Radioactive Waste Management. Following government decisions taken in 1998, the study focused on two types of geological medium, clay and granite. The clay formations study is essentially based on results from an underground laboratory sited at the border between the Meuse and Haute-Marne departments, where the Callovo-Oxfordian argillite beds are being investigated. No site has yet been chosen for an underground laboratory for the granite study, so for the time being this will draw on generic work and on research carried out in laboratories outside France. ANDRA has decided to present an initial report on the results of its research programme, publishing a dossier on the work on clay formations in 2001 with a second dossier covering the work on granite due for release in 2002. This dossier is thus a review of the work carried out by ANDRA on the feasibility study into a radioactive waste repository in a clay formation. It represents one step in a process of studies and research work leading up to the submission of a report due in 2005 containing ANDRA conclusions on the feasibility of a repository in the clay formation. (author)

Effects of post-disposal gas generation in a repository for spent fuel, high-level waste and long-lived intermediate level waste sited in opalinus clay

International Nuclear Information System (INIS)

Johnson, L.; Marschall, P.; Zuidema, P.; Gribi, P.

2004-07-01

This comprehensive report issued by the Swiss National Cooperative for the Disposal of Radioactive Waste NAGRA takes a look at post-disposal gas generation in a repository for spent fuel and highly radioactive wastes in Opalinus clay strata. This study provides a comprehensive treatment of the issue of gas generation in a repository for spent fuel (SF), vitrified high-level waste (HLW) and long-lived intermediate-level waste (ILW), sited in the Opalinus clay of the Zuercher Weinland in northern Switzerland. The issue of how gas generation in and transport from waste repositories may influence disposal system performance has been under study for many years, both at Nagra and internationally. The report consists of three main parts: (i) A synthesis of basic information on the host rock and on details of repository construction; (ii) A discussion on gas transport characteristics of the engineered barrier system and the geosphere; (iii) A discussion on the effects of gas on system performance, based on the available information on gas generation, gas transport properties and gas pathways provided in the previous parts of the report. Simplified model calculations based on a mass balance approach for the gas generated within the repository are presented and discussed

Different types of radioactive waste repositories, each suited for a given type of radioactive waste - 59293

International Nuclear Information System (INIS)

Voinis, Sylvie; Boissier, Fabrice; Griffault, Lise; Maillard, Jean Louis; Dutzer, Michel

2012-01-01

Document available in abstract form only. Full text of publication follows: The aim of this article is to present how Andra implements a dedicated solution per waste category. It relies on response to a series of questions concerning the appropriate waste disposal system such as: What type of radiological inventory is involved? What are the half-lives of the radionuclides and the associated timescales concerned for achieving the fundamental protection objective? In that respect, Andra has developed and has implemented methods for all disposal facilities in order to reach common objectives: The immediate and long term protections of human beings and the environment constitute the fundamental objectives of all radioactive-waste disposal facilities. In order to achieve those protections, disposal facilities must be safe. Thus, Andra safety encompasses all design, implementation and operational measures for preventing risks of all kind internal, external during operation and after closure in consistency with defense in depth principles taken into account the peculiarity of waste disposal facilities: (i) balancing operational safety and post-closure safety, (ii) management of nuclear risks in underground repository for some of them, (iii) management of scientific understanding and related uncertainties, and (iv) management of long or very long- timescales. The presentation will illustrate Andra's approach that has or will be conducted and will focus on communalities or peculiarities according to the type of waste and related disposal options regarding the following iterative steps: regulatory safety rules, input data, scenarios, safety assessments. (authors)

Radioactive waste communication policy in Spain

International Nuclear Information System (INIS)

Gonzalez, V.

1993-01-01

ENRESA (Empresa Nacional de Residuos Radiactivos, S.A.), is a State-owned company, founded in 1985 and is responsible for radioactive waste management in Spain. ENRESA's activities are developed following a General Radioactive Waste Plan approved by the Spanish Government. As in most countries, Spanish public opinion is concerned with the most activities related to radioactivity or rad-waste management due to different facts but mainly to a lack of information on the matter. This situation provides misuse of information on it by some politicians, green groups and media which increases distrust of public on responsible companies and institutions. To gain public acceptance, it would be necessary to develop long-term information policy, due to the fact that results in communication are reached in the long term. ENRESA is carrying out a Communication Plan (CP) which has been implemented in a continuous way with success around the area of the disposal site of low and intermediate level wastes as well as around an old uranium mill factory in which remedial actions are being implemented. The implantation of CP at a national level is being done stepwise. The more relevant issues related to the radioactive waste situation in Spain, as well as the communication actions are explained in this document

Radioecological activity limits for radioactive waste disposal

International Nuclear Information System (INIS)