WorldWideScience

Sample records for safety waste management

  1. Waste management safety

    International Nuclear Information System (INIS)

    Boehm, H.

    1983-01-01

    All studies carried out by competent authors of the safety of a waste management concept on the basis of reprocessing of the spent fuel elements and storage in the deep underground of the radioactive waste show that only a minor technical risk is involved in this step. This also holds true when evaluating the accidents which have occurred in waste management facilities. To explain the risk, first the completely different safety aspects of nuclear power plants, reprocessing plants and repositories are outlined together with the safety related characteristics of these plants. Also this comparison indicates that the risk of waste management facilities is considerably lower than the, already very small, risk of nuclear power plants. For the final storage of waste from reprocessing and for the direct storage of fuel elements, the results of safety analyses show that the radiological exposure following an accident with radioactivity releases, even under conservative assumptions, is considerably below the natural radiation exposure. The very small danger to the environment arising from waste management by reprocessing clearly indicates that aspects of technical safety alone will hardly be a major criterion for the decision in favor of one or the other waste management approach. (orig.) [de

  2. Safety in waste management plants: An Indian perspective

    International Nuclear Information System (INIS)

    Shekhar, P.; Ozarde, P.D.; Gandhi, P.M.

    2000-01-01

    Assurance of safety of public and plant workers and protection of the environment are prime objectives in the design and construction of Waste Management Plants. In India, waste management principles and strategies have been evolved in accordance with national and international regulations and standards for radiation protection. The regulations governing radiation protection have a far-reaching impact on the management of the radioactive waste. The wastes arise at each stages of the fuel cycle with varying chemical nature, generation rate and specific activity levels depending upon the type of the facility. Segregation of waste based on its chemical nature and specific activity levels is an essential feature, as its aids in selection of treatment and conditioning process. Selection of the process, equipment and materials in the plant, are governed by safety consideration alongside factors like efficiency and simplicity. The plant design considerations like physical separation, general arrangement, ventilation zoning, access control, remote handling, process piping routing, decontamination etc. have major role in realizing waste safety. Stringent quality control measures during all stages of construction have helped in achieving the design intended safety. These aspects together with operating experience gained form basis for the improved safety features in the design and construction of waste management plants. The comprehensive safety is derived from adoption of waste management strategies and appropriate plant design considerations. The paper briefly brings safety in waste management programme in India, in its current perspective. (author)

  3. Predisposal Management of Radioactive Waste. General Safety Requirements Pt. 5

    International Nuclear Information System (INIS)

    2010-01-01

    There are a large number of facilities and activities around the world in which radioactive material is produced, handled and stored. This Safety Requirements publication presents international consensus requirements for the management of radioactive waste prior to its disposal. It provides the safety imperatives on the basis of which facilities can be designed, operated and regulated. The publication is supported by a number of Safety Guides that provide up to date recommendations and guidance on best practices for management of particular types of radioactive waste, for storage of radioactive waste, for assuring safety by developing safety cases and supporting safety assessments, and for applying appropriate management systems. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Responsibilities associated with the predisposal management of radioactive waste; 4. Steps in the predisposal management of radioactive waste; 5. Development and operation of predisposal radioactive waste management facilities and activities; Annex: Predisposal management of radioactive waste and the fundamental safety principles.

  4. Predisposal Management of Radioactive Waste. General Safety Requirements Pt. 5

    International Nuclear Information System (INIS)

    2009-01-01

    There are a large number of facilities and activities around the world in which radioactive material is produced, handled and stored. This Safety Requirements publication presents international consensus requirements for the management of radioactive waste prior to its disposal. It provides the safety imperatives on the basis of which facilities can be designed, operated and regulated. The publication is supported by a number of Safety Guides that provide up to date recommendations and guidance on best practices for management of particular types of radioactive waste, for storage of radioactive waste, for assuring safety by developing safety cases and supporting safety assessments, and for applying appropriate management systems. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Responsibilities associated with the predisposal management of radioactive waste; 4. Steps in the predisposal management of radioactive waste; 5. Development and operation of predisposal radioactive waste management facilities and activities; Annex: Predisposal management of radioactive waste and the fundamental safety principles.

  5. Safety and Waste Management for SAM Pathogen Methods

    Science.gov (United States)

    The General Safety and Waste Management page offers section-specific safety and waste management details for the pathogens included in EPA's Selected Analytical Methods for Environmental Remediation and Recovery (SAM).

  6. Safety and Waste Management for SAM Biotoxin Methods

    Science.gov (United States)

    The General Safety and Waste Management page offers section-specific safety and waste management details for the biotoxins included in EPA's Selected Analytical Methods for Environmental Remediation and Recovery (SAM).

  7. Safety and Waste Management for SAM Chemistry Methods

    Science.gov (United States)

    The General Safety and Waste Management page offers section-specific safety and waste management details for the chemical analytes included in EPA's Selected Analytical Methods for Environmental Remediation and Recovery (SAM).

  8. Safety and Waste Management for SAM Radiochemical Methods

    Science.gov (United States)

    The General Safety and Waste Management page offers section-specific safety and waste management details for the radiochemical analytes included in EPA's Selected Analytical Methods for Environmental Remediation and Recovery (SAM).

  9. Project safety studies - nuclear waste management (PSE)

    International Nuclear Information System (INIS)

    1981-10-01

    The project 'Safety Studies-Nuclear Waste Management' (PSE) is a research project performed by order of the Federal Minister for Research and Technology, the general purpose of which is to deepen and ensure the understanding of the safety aspects of the nuclear waste management and to prepare a risk analysis which will have to be established in the future. Owing to this the project is part of a series of projects which serve the further development of the concept of nuclear waste management and its safety, and which are set up in such a way as to accompany the realization of that concept. This report contains the results of the first stage of the project from 1978 to mid-1981. (orig./RW) [de

  10. Predisposal management of low and intermediate level radioactive waste. Safety guide

    International Nuclear Information System (INIS)

    2003-01-01

    Radioactive waste is generated in the generation of electricity in nuclear power reactors and in the use of radioactive material in industry, research and medicine. The importance of the safe management of radioactive waste for the protection of human health and the environment has long been recognized. The principles and requirements that govern the safety of the management of radioactive waste are presented in 'The Principles of Radioactive Waste Management', 'Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety' and 'Predisposal Management of Radioactive Waste, Including Decommissioning'. The objective of this Safety Guide is to provide regulatory bodies and the operators that generate and manage radioactive waste with recommendations on how to meet the principles and requirements established in Refs for the predisposal management of LLW. This Safety Guide deals with the safety issues associated with the predisposal management of LLW from nuclear fuel cycle facilities, large research and development installations and radioisotope production facilities. This includes all steps and activities in the management of waste, from its initial generation to its final acceptance at a waste disposal facility or the removal of regulatory control. The predisposal management of radioactive waste includes decommissioning. The term 'decommissioning' encompasses both the process of decommissioning a facility and the management of the waste that results (prior to its disposal). Recommendations on the process of decommissioning are provided in Refs. Recommendations on the management of the waste resulting from decommissioning are included in this Safety Guide. Although the mining and milling of uranium and thorium ores is part of the nuclear fuel cycle, the management of the operational waste (e.g. waste rock, tailings and effluent treatment waste) from these activities is not within the scope of this Safety Guide. The LLW that is

  11. Predisposal management of high level radioactive waste. Safety guide

    International Nuclear Information System (INIS)

    2005-01-01

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

  12. Implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

    International Nuclear Information System (INIS)

    Stewart, L.; Tonkay, D.

    2004-01-01

    This paper discusses the implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The Joint Convention: establishes a commitment with respect to safe management of spent nuclear fuel and radioactive waste; requires the Parties to ''take appropriate steps'' to ensure the safety of their spent fuel and waste management activities, but does not delineate standards the Parties must meet; and seeks to attain, through its Contracting Parties, a higher level of safety with respect to management of their spent nuclear fuel, disused sealed sources, and radioactive waste

  13. Safety of radioactive waste management. Proceedings of an international conference

    International Nuclear Information System (INIS)

    2000-01-01

    The principal objective of the Conference was to enable members of the scientific community and representatives of facilities which produce radioactive waste, of bodies responsible for radioactive waste management, of nuclear regulatory bodies and of public interest groups, among others, to engage in an open dialogue. The open dialogue which took place may, by providing policy and decision makers with a basis for political action, prove to be an important step in the search for the international consensus so essential in the area of radioactive waste management. The relevant policies and activities of the IAEA, the European Commission, the OECD Nuclear Energy Agency and the World Health Organization were presented. The evolution, under the aegis of the IAEA, of a de facto international radiation and nuclear safety regime was noted. In the area of radioactive waste safety, this regime consists of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, the body of international waste safety standards established by the IAEA and other international organizations, and the IAEA's mechanisms for providing for the application of those standards. The topics covered by the Conference were: Current international co-operative efforts; Recommendations from the International Commission on Radiological Protection; Recommendations from the International Nuclear Safety Advisory Group; Conclusions and recommendations of the International Symposium on the Restoration of Environments with Radioactive Residues; Siting of radioactive waste management facilities; Participation of interested parties; Legislative and general radiation safety aspects; Removal of material from regulatory control (exclusion, exemption and clearance); Predisposal management (dilution, recycling, transmutation, etc.); Near surface disposal; Residues from the mining and processing of radioactive ores; Long term institutional control; Geological disposal

  14. Aspects of nuclear safety in the management of the radioactive wastes

    International Nuclear Information System (INIS)

    Popescu, D.; Iliescu, E.

    1997-01-01

    The paper reviews aspects of nuclear safety which should be taken into account in the management of the radioactive wastes. The paper considers underlying criteria concerning the management, collecting, sorting transportation and treatment of radioactive wastes as well as safety engineering measures taken when designing a facility for the treatment of radioactive wastes. The paper also brings forward the removal radioactive wastes and some points on the policy of radioactive wastes management in Romania. (authors)

  15. Safety issues in established predisposal waste management practices

    International Nuclear Information System (INIS)

    Thomas, W.

    2000-01-01

    Radioactive wastes generated at various stages in the nuclear fuel cycle vary considerably in relation to volume, physical and chemical properties, and radioactivity. The management of these wastes prior to disposal has to be adapted to these conditions, which calls for suitable characterization and minimization, collection, interim storage and conditioning of the wastes. Experience gained over decades shows that current predisposal waste management practices are well advanced. Whereas problems related to inadequate waste management practices in the past have been encountered at several sites and need ongoing remedial actions, modern practices have good safety records. Considerable development and improvement of waste management practices have been achieved and as a consequence of delays in implementing repositories in several countries they remain important tasks. Decommissioning and dismantling of nuclear facilities also have to be taken into account. In most cases, these activities can be performed using existing technical means and practices. No significant safety concerns have been found for the long term storage of spent fuel and vitrified waste. Dry storage has reached technical maturity and appears to be attractive, especially for aged fuel. It has, however, to be stressed that long term storage is not the ultimate solution. Continued efforts to implement repositories are mandatory in order to maintain a credible and responsible strategy for waste management. (author)

  16. Predisposal management of radioactive waste. General safety requirements. Pt. 5

    International Nuclear Information System (INIS)

    2009-01-01

    The objective of this Safety Requirements publication is to establish, the requirements that must be satisfied in the predisposal management of radioactive waste. This publication sets out the objectives, criteria and requirements for the protection of human health and the environment that apply to the siting, design, construction, commissioning, operation and shutdown of facilities for the predisposal management of radioactive waste, and the requirements that must be met to ensure the safety of such facilities and activities. This Safety Requirements publication applies to the predisposal management of radioactive waste of all types and covers all the steps in its management from its generation up to its disposal, including its processing (pretreatment, treatment and conditioning), storage and transport. Such waste may arise from the commissioning, operation and decommissioning of nuclear facilities; the use of radionuclides in medicine, industry, agriculture, research and education; the processing of materials that contain naturally occurring radionuclides; and the remediation of contaminated areas. The introduction of the document (Section 1) informs about its objective, scope and structure. The protection of human health and the environment is considered in Section 2 of this publication. Section 3 establishes requirements for the responsibilities associated with the predisposal management of radioactive waste. Requirements for the principal approaches to and the elements of the predisposal management of radioactive waste are established in Section 4. Section 5 establishes requirements for the safe development and operation of predisposal radioactive waste management facilities and safe conduct of activities. The Annex presents a discussion of the consistency of the safety requirements established in this publication with the fundamental safety principles

  17. Methodology for Safety Assessment Applied to Predisposal Waste Management. Report of the Results of the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) 2004–2010)

    International Nuclear Information System (INIS)

    2015-12-01

    Report of the Results of the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) (2004–2010) The IAEA’s progamme on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) focused on approaches and mechanisms for application of safety assessment methodologies for the predisposal management of radioactive waste. The initial outcome of the SADRWMS Project was achieved through the development of flowcharts, which have since been incorporated into IAEA Safety Standards Series No. GSG-3, Safety Case and Safety Assessment for Predisposal Management of Radioactive Waste. In 2005, an initial specification was developed for the Safety Assessment Framework (SAFRAN) software tool to apply the SADRWMS flowcharts. In 2008, an in-depth application of the SAFRAN tool and the SADRWMS methodology was carried out on the predisposal management facilities of the Thailand Institute of Nuclear Technology Radioactive Waste Management Centre (TINT Facility). This publication summarizes the content and outcomes of the SADRWMS programme. The Chairman’s Report of the SADRWMS Project and the Report of the TINT test case are provided on the CD-ROM which accompanies this report

  18. The management and disposal of radioactive wastes - safety principles and guidelines

    International Nuclear Information System (INIS)

    Linsley, G.; Bell, M.; Saire, D.

    1991-01-01

    This paper describes the current plans for the establishment of the Radioactive Waste Safety Standards (RADWASS), a new series of IAEA documents in the Safety Series category intended to set out internationally agreed approaches to the safe management and disposal or radioactive waste. RADWASS is being implemented to document the harmonization which exists in the approaches to establishing safety in the field of radioactive waste management and disposal at the international level. (au)

  19. Achievements and Perspectives of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

    International Nuclear Information System (INIS)

    Louvat, D.; Lacoste, A.C.

    2006-01-01

    The Joint Convention on the Safety of Spent Fuel management and on the Safety of Radioactive Waste Management is the first legal instrument to directly address the safety of spent fuel and radioactive waste management on a global scale. The Joint Convention entered into force in 2001. This paper describes its process and its main achievements to date. The perspectives to establish of a Global Waste Safety Regime based on the Joint Convention are also discussed. (authors)

  20. The management system for the disposal of radioactive waste. Safety guide

    International Nuclear Information System (INIS)

    2008-01-01

    The objective of this Safety Guide is to provide recommendations on developing and implementing management systems for all phases of facilities for the disposal of radioactive waste and related activities. It covers the management systems for managing the different stages of waste disposal facilities, such as siting, design and construction, operation (i.e. the activities, which can extend over several decades, involving receipt of the waste product in its final packaging (if it is to be disposed of in packaged form), waste emplacement in the waste disposal facility, backfilling and sealing, and any subsequent period prior to closure), closure and the period of institutional control (i.e. either active control - monitoring, surveillance and remediation; or passive control - restricted land use). The management systems apply to various types of disposal facility for different categories of radioactive waste, such as: near surface (for low level waste), geological (for low, intermediate and/or high level waste), boreholes (for sealed sources), surface impoundment (for mining and milling waste) and landfill (for very low level waste). It also covers management systems for related processes and activities, such as extended monitoring and surveillance during the period of active institutional control in the post-closure phase, safety and performance assessments and development of the safety case for the waste disposal facility and regulatory authorization (e.g. licensing). This Safety Guide is intended to be used by organizations that are directly involved in, or that regulate, the facilities and activities described in paras 1.15 and 1.16, and by the suppliers of nuclear safety related products that are required to meet some or all of the requirements established in IAEA Safety Standards Series No. GS-R-3 'The Management System for Facilities and Activities'. It will also be useful to legislators and to members of the public and other parties interested in the nuclear

  1. 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.

  2. Regulatory safety aspects of nuclear waste management operations in India

    International Nuclear Information System (INIS)

    Sundararajan, A.R.

    2000-01-01

    The Department of Atomic Energy in India as part of its programme to harness the nuclear energy for generation of nuclear power has been operating a whole range of nuclear fuel cycle facilities including waste management plants for more than four decades. The waste management plants include three high level waste immobilisation plants, one in operation, one under commissioning and one more under construction. Atomic Energy Regulatory Board is mandated to review and authorise from the safety angle the siting, the design, the construction and the operation of the waste management plants. The regulatory procedures, which involve multi-tier review adopted for ensuring the safety of these facilities, are described in this paper. (author)

  3. Predisposal Management of Low and Intermediate Level Radioactive Waste. Safety Guide

    International Nuclear Information System (INIS)

    2009-01-01

    The objective of this Safety Guide is to provide regulatory bodies and the operators that generate and manage radioactive waste with recommendations on how to meet the principles and requirements established for the predisposal management of low and intermediate level waste. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Roles and responsibilities; 4. General safety considerations; 5. Safety features for the predisposal management of LILW; 6. Record keeping and reporting; 7. Safety assessment; 8. Quality assurance; Annex I: Nature and sources of LILW from nuclear facilities; Annex II: Development of specifications for waste packages; Annex III: Site conditions, processes and events for consideration in a safety assessment (external natural phenomena); Annex IV: Site conditions, processes and events for consideration in a safety assessment (external human induced phenomena); Annex V: Postulated initiating events for consideration in a safety assessment (internal phenomena).

  4. Safety assessment driving radioactive waste management solutions (SADRWMS Methodology) implemented in a software tool (SAFRAN)

    Energy Technology Data Exchange (ETDEWEB)

    Kinker, M., E-mail: M.Kinker@iaea.org [International Atomic Energy Agency (IAEA), Vienna (Austria); Avila, R.; Hofman, D., E-mail: rodolfo@facilia.se [FACILIA AB, Stockholm (Sweden); Jova Sed, L., E-mail: jovaluis@gmail.com [Centro Nacional de Seguridad Nuclear (CNSN), La Habana (Cuba); Ledroit, F., E-mail: frederic.ledroit@irsn.fr [IRSN PSN-EXP/SSRD/BTE, (France)

    2013-07-01

    In 2004, the International Atomic Energy Agency (IAEA) organized the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) to examine international approaches to safety assessment for predisposal management of radioactive waste. The initial outcome of the SADRWMS Project was achieved through the development of flowcharts which could be used to improve the mechanisms for applying safety assessment methodologies to predisposal management of radioactive waste. These flowcharts have since been incorporated into DS284 (General Safety Guide on the Safety Case and Safety Assessment for Predisposal Management of Radioactive Waste), and were also considered during the early development stages of the Safety Assessment Framework (SAFRAN) Tool. In 2009 the IAEA presented DS284 to the IAEA Waste Safety Standards Committee, during which it was proposed that the graded approach to safety case and safety assessment be illustrated through the development of Safety Reports for representative predisposal radioactive waste management facilities and activities. To oversee the development of these reports, it was agreed to establish the International Project on Complementary Safety Reports: Development and Application to Waste Management Facilities (CRAFT). The goal of the CRAFT project is to develop complementary reports by 2014, which the IAEA could then publish as IAEA Safety Reports. The present work describes how the DS284 methodology and SAFRAN Tool can be applied in the development and review of the safety case and safety assessment to a range of predisposal waste management facilities or activities within the Region. (author)

  5. Safety assessment driving radioactive waste management solutions (SADRWMS Methodology) implemented in a software tool (SAFRAN)

    International Nuclear Information System (INIS)

    Kinker, M.; Avila, R.; Hofman, D.; Jova Sed, L.; Ledroit, F.

    2013-01-01

    In 2004, the International Atomic Energy Agency (IAEA) organized the International Project on Safety Assessment Driving Radioactive Waste Management Solutions (SADRWMS) to examine international approaches to safety assessment for predisposal management of radioactive waste. The initial outcome of the SADRWMS Project was achieved through the development of flowcharts which could be used to improve the mechanisms for applying safety assessment methodologies to predisposal management of radioactive waste. These flowcharts have since been incorporated into DS284 (General Safety Guide on the Safety Case and Safety Assessment for Predisposal Management of Radioactive Waste), and were also considered during the early development stages of the Safety Assessment Framework (SAFRAN) Tool. In 2009 the IAEA presented DS284 to the IAEA Waste Safety Standards Committee, during which it was proposed that the graded approach to safety case and safety assessment be illustrated through the development of Safety Reports for representative predisposal radioactive waste management facilities and activities. To oversee the development of these reports, it was agreed to establish the International Project on Complementary Safety Reports: Development and Application to Waste Management Facilities (CRAFT). The goal of the CRAFT project is to develop complementary reports by 2014, which the IAEA could then publish as IAEA Safety Reports. The present work describes how the DS284 methodology and SAFRAN Tool can be applied in the development and review of the safety case and safety assessment to a range of predisposal waste management facilities or activities within the Region. (author)

  6. 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)

  7. Survey of systems safety analysis methods and their application to nuclear waste management systems

    International Nuclear Information System (INIS)

    Pelto, P.J.; Winegardner, W.K.; Gallucci, R.H.V.

    1981-11-01

    This report reviews system safety analysis methods and examines their application to nuclear waste management systems. The safety analysis methods examined include expert opinion, maximum credible accident approach, design basis accidents approach, hazard indices, preliminary hazards analysis, failure modes and effects analysis, fault trees, event trees, cause-consequence diagrams, G0 methodology, Markov modeling, and a general category of consequence analysis models. Previous and ongoing studies on the safety of waste management systems are discussed along with their limitations and potential improvements. The major safety methods and waste management safety related studies are surveyed. This survey provides information on what safety methods are available, what waste management safety areas have been analyzed, and what are potential areas for future study

  8. Survey of systems safety analysis methods and their application to nuclear waste management systems

    Energy Technology Data Exchange (ETDEWEB)

    Pelto, P.J.; Winegardner, W.K.; Gallucci, R.H.V.

    1981-11-01

    This report reviews system safety analysis methods and examines their application to nuclear waste management systems. The safety analysis methods examined include expert opinion, maximum credible accident approach, design basis accidents approach, hazard indices, preliminary hazards analysis, failure modes and effects analysis, fault trees, event trees, cause-consequence diagrams, G0 methodology, Markov modeling, and a general category of consequence analysis models. Previous and ongoing studies on the safety of waste management systems are discussed along with their limitations and potential improvements. The major safety methods and waste management safety related studies are surveyed. This survey provides information on what safety methods are available, what waste management safety areas have been analyzed, and what are potential areas for future study.

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

    International Nuclear Information System (INIS)

    2016-01-01

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

  10. Basic safety principles of INSAG and their application in radioactive waste management

    International Nuclear Information System (INIS)

    Baer, A.J.

    2000-01-01

    The International Nuclear Safety Advisory Group (INSAG) has, in INSAG-11, attempted to show what safety principles are common to all applications of all sources of radiation. It has been considered that these general principles should apply to all industrial activities. A comparison of INSAG-11 with Article 11 of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) shows that the management of radioactive waste is but a special case of industrial activity and follows the same safety rules. The importance of the Joint Convention comes, however, from the fact that it is a politically important document, requiring ratification by the parliaments of the contracting parties. The safe management of radioactive waste implies that five types of issue must be taken into consideration, not only technical and ethical ones, but also socio-political, economic and ecological ones. By comparison, sustainable development in its three dimensions (temporal, spatial and sectorial) has five components (ecology, economics, ethics, socio-politics and technology), just like the safe management of radioactive waste. The consequence of this is that if management is treated as a particular case of sustainable development, it will not be accepted by society. The conclusions are that technology alone can not ensure the safety of radioactive waste management and that society will always give priority to socio-political issues over technological ones. Furthermore, it is crucial that people involved in the management of radioactive waste learn to communicate better and to listen more attentively. Their efforts will only succeed when they incorporate all the components that determine the fabric of our society. (author)

  11. Increase of Technogenic Safety of a Waste Management Company

    Directory of Open Access Journals (Sweden)

    Cudečka-Puriņa Natālija

    2017-11-01

    Full Text Available Waste management is often recognised in the society as an activity sector possessing an extensive potential harm on technogenic safety. As most of the European Union countries have experienced at least theoretical shift from waste management to resource management, it is now extremely important to implement this shift in practice, moving from disposing waste or by-products to developing a cooperation network that allows different industries to use each other’s waste as resources. This shift will lead to saving of primary resources and raw materials and develop recycling and reuse, bringing them to a higher level.

  12. Safety assessment for Area 5 radioactive-waste-management site

    International Nuclear Information System (INIS)

    Hunter, P.H.; Card, D.H.; Horton, K.

    1982-09-01

    The Area 5 Radioactive Waste Management Safety Assessment Document contains evaluations of site characteristics, facilities, and operating practices that contribute to the safe handling, storage, and disposal of low-level radioactive wastes at the Nevada Test Site. Physical geography, cultural factors, climate and meteorology, geology, hydrology (with emphasis on radionuclide migration), ecology, natural phenomena, and natural resources are discussed and determined to be suitable for effective containment of radionuclides. A separate section considers facilities and operating practices such as monitoring, storage/disposal criteria, site maintenance, equipment, and support. The section also considers the transportation and waste handling requirements supporting the new Greater Confinement Disposal Facility (GCDF), GCDF demonstration project, and other requirements for the safe handling, storage, and disposal of low-level radioactive wastes. Finally, the document provides an analysis of releases and an assessment of the near-term operational impacts and dose commitments to operating personnel and the general public from normal operations and anticipated accidental occurrences. The conclusion of this report is that the Area 5 Radioactive Waste Management Site is suitable for low-level radioactive waste handling, storage, and disposal. Also, the new GCDF demonstration project will not affect the overall safety of the Area 5 Radioactive Waste Management Site

  13. Radioactive waste management services. Safety and technical advisory services available from the IAEA

    International Nuclear Information System (INIS)

    2000-09-01

    This brochure provides updated information about the services and assistance the International Atomic Energy Agency (IAEA) is able to render, upon request by Member States, in the area of radioactive waste management. The ultimate objective is to ensure that all wastes are managed safely and in a way which protects both individual and the environment, now and in the future. The IAEA is the sole global international organization with the statutory authority to establish safety standards for the protection of health against exposure to ionizing radiation. These include safety standards for radioactive waste management. A comprehensive set of such standards is being established, and continuously updated, under the Agency's aegis, which lay out the requirements for the safe management of all types of radioactive waste. The Agency has a further statutory obligation ro provide for the application of these standards at the request of States. The safety of radioactive waste management is not attainable through safety standards alone but requires special technology. An additional function of the IAEA is thus to foster the transfer of technology among States, including the specific technology needed to ensure safe radioactive waste management

  14. Legislation and regulatory infrastructure for the safety of radioactive waste management

    International Nuclear Information System (INIS)

    Hoegberg, L.

    2000-01-01

    The essential generic characteristics of a national legislative and regulatory system for the safety of radioactive waste management are defined and discussed. The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management as well as other relevant international legal instruments and guidelines are discussed. Special emphasis is given to the following characteristics of a national legislative and regulatory system: (i) definition of responsibilities, (ii) financing of future costs, (iii) nuclear and radiation safety requirements, (iv) siting and licensing procedures, (v) regulatory functions, and (vi) international co-operation. It is concluded that there exists an internationally endorsed basis for establishing effective national legislation and regulatory infrastructures for the safety of radioactive waste management. It is underlined that the continuing internationalization of the nuclear industry stresses the need for national legislation and regulatory infrastructure to be based on such internationally endorsed principles and standards. It is pointed out that regulators are accountable to the public and have to gain public trust by being active in the public arena, demonstrating their competence and integrity. Finally, prescriptive and goal-oriented international safety regimes are briefly discussed in the light of experience so far gained with the Convention on Nuclear Safety. (author)

  15. Radiation safety requirements for radioactive waste management in the framework of a quality management system

    International Nuclear Information System (INIS)

    Salgado, M.M.; Benitez, J.C.; Pernas, R.; Gonzalez, N.

    2007-01-01

    The Center for Radiation Protection and Hygiene (CPHR) is the institution responsible for the management of radioactive wastes generated from nuclear applications in medicine, industry and research in Cuba. Radioactive Waste Management Service is provided at a national level and it includes the collection and transportation of radioactive wastes to the Centralized Waste Management Facilities, where they are characterized, segregated, treated, conditioned and stored. A Quality Management System, according to the ISO 9001 Standard has been implemented for the RWM Service at CPHR. The Management System includes the radiation safety requirements established for RWM in national regulations and in the Licence's conditions. The role of the Regulatory Body and the Radiation Protection Officer in the Quality Management System, the authorization of practices, training and personal qualification, record keeping, inspections of the Regulatory Body and internal inspection of the Radiation Protection Officer, among other aspects, are described in this paper. The Quality Management System has shown to be an efficient tool to demonstrate that adequate measures are in place to ensure the safety in radioactive waste management activities and their continual improvement. (authors)

  16. International intercomparison and harmonization projects for demonstrating the safety of radioactive waste management, decommissioning and radioactive waste disposal

    International Nuclear Information System (INIS)

    Metcalf, Phil; O'Donnell, Patricio; Jova Sed, Luis; Batandjieva, Borislava; Rowat, John; Kinker, Monica

    2008-01-01

    Full text: The Joint Convention on the safety of spent fuel management and the safety of radioactive waste management and the international safety standards on radioactive waste management, decommissioning and radioactive waste disposal call for assessment and demonstration of the safety of facilities and activities; during siting, design and construction prior to operation, periodically during operation and at the end of lifetime or upon closure of a waste disposal facility. In addition, more recent revisions of the international safety standards require the development of a safety case for such facilities and activities, documentation presenting all the arguments supporting the safety of the facilities and activities covering site and engineering features, quantitative safety assessment and management systems. Guidance on meeting these safety requirements also indicates the need for a graded approach to safety assessment, with the extent and complexity of the assessment being proportional to the complexity of the activity or facility, and its propensity for radiation hazard. Safety assessment approaches and methodologies have evolved over several decades and international interest in these developments has been considerable as they can be complex and often subjective, which has led to international projects being established aimed at harmonization. The IAEA has sponsored a number of such initiatives, particularly in the area of disposal facility safety, but more recently in the areas of pre disposal waste management and decommissioning, including projects known as ISAM, ASAM, SADRWMS and DeSa. The projects have a number of common aspects including development of standardized methodological approaches, application on test cases and assessment review; they also have activity and facility specific elements. The paper presents an overview of the projects, the outcomes from the projects to date and their future direction aimed very much at practical application of

  17. Specifications of the International Atomic Energy Agency's international project on safety assessment driven radioactive waste management solutions

    International Nuclear Information System (INIS)

    Ghannadi, M.; Asgharizadeh, F.; Assadi, M. R.

    2008-01-01

    Radioactive waste is produced in the generation of nuclear power and the production and use of radioactive materials in the industry, research, and medicine. The nuclear waste management facilities need to perform a safety assessment in order to ensure the safety of a facility. Nuclear safety assessment is a structured and systematic way of examining a proposed facility, process, operation and activity. In nuclear waste management point of view, safety assessment is a process which is used to evaluate the safety of radioactive waste management and disposal facilities. In this regard the International Atomic Energy Agency is planed to implement an international project with cooperation of some member states. The Safety Assessment Driving Radioactive Waste Management Solutions Project is an international programme of work to examine international approaches to safety assessment in aspects of p redisposal r adioactive waste management, including waste conditioning and storage. This study is described the rationale, common aspects, scope, objectives, work plan and anticipated outcomes of the project with refer to International Atomic Energy Agency's documents, such as International Atomic Energy Agency's Safety Standards, as well as the Safety Assessment Driving Radioactive Waste Management Solutions project reports

  18. National report of the Slovak Republic - proposal. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Jun 2008

    International Nuclear Information System (INIS)

    Jurina, V.; Viktory, D.; Kobzova, D.; Petrik, T.; Sovcik, J.; Hekel, P.; Suess, J.; Tomek, J.; Lukacovic, J.; Hekel, P.; Ivan, J.; Ziakova, M.; Metke, E.; Pospisil, M.; Turner, M.; Homola, J.; Konecny, L.; Parimucha, F.; Vaclav, J.; Horvath, J.; Soos, F.; Betak, A.; Pospisil, P.; Mihaly, B.; Kubala, M.; Schmidtova, B.; Orihel, M.; Vasina, D.; Balaz, J.; Ehn, L.; Micovicova, D.; Vrtoch, M.; Mlcuch, L.; Granak, P.; Meleg, J.; Sedliak, D.; Bardy, M.; Gogoliak, J.; Prazska, M.; Burslova, J.

    2008-06-01

    A brief national safety report of the Slovak Republic compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management in 2008 is presented. This safety report consists of following chapters: (A) Introduction; (B) Spent nuclear fuel (SNF) and radioactive waste (RAW) management conception; (C) Scope of application; (D) Spent nuclear fuel (SNF) and radioactive waste (RAW) management; (E) Legislation and regulatory framework; (F) General safety provisions; (G) Safety of spent nuclear fuel management; (H) Safety of radioactive waste management; (I) Transboundary movement of spent nuclear fuel and radioactive waste; (J) Discussed sealed radioactive sources; (K) Planned measures to improve safety; (L) Annexes

  19. [Problems of safety regulation under radioactive waste management in Russia].

    Science.gov (United States)

    Monastyrskaia, S G; Kochetkov, O A; Barchukov, V G; Kuznetsova, L I

    2012-01-01

    Analysis of the requirements of Federal Law N 190 "About radioactive waste management and incorporation of changes into some legislative acts of the Russian Federation", as well as normative-legislative documents actual and planned to be published related to provision of radiation protection of the workers and the public have been done. Problems of safety regulation raised due to different approaches of Rospotrebnadzor, FMBA of Russia, Rostekhnadzor and Minprirody with respect to classification and categorization of the radioactive wastes, disposal, exemption from regulatory control, etc. have been discussed in the paper. Proposals regarding improvement of the system of safety regulation under radioactive waste management and of cooperation of various regulatory bodies have been formulated.

  20. Mixed Waste Management Facility Preliminary Safety Analysis Report. Chapters 1 to 20

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    This document provides information on waste management practices, occupational safety, and a site characterization of the Lawrence Livermore National Laboratory. A facility description, safety engineering analysis, mixed waste processing techniques, and auxiliary support systems are included.

  1. Mixed Waste Management Facility Preliminary Safety Analysis Report. Chapters 1 to 20

    International Nuclear Information System (INIS)

    1994-09-01

    This document provides information on waste management practices, occupational safety, and a site characterization of the Lawrence Livermore National Laboratory. A facility description, safety engineering analysis, mixed waste processing techniques, and auxiliary support systems are included

  2. The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

    International Nuclear Information System (INIS)

    Risoluti, P.

    2004-01-01

    The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management (the Joint Convention) is the only legally binding international treaty in the area of radioactive waste management. It was adopted by a Diplomatic Conference in September 1997 and opened for signature on 29 September 1997. The Convention entered into force on 18 June 1998, and to date (September 04) has been signed by 42 States, of which 34 have formally ratified, thus becoming Contracting Parties. The Joint Convention applies to spent fuel and radioactive waste resulting from civilian application. Its principal aim is to achieve and maintain a high degree of safety in their management worldwide. The Convention is an incentive instrument, not designed to ensure fulfillment of obligations through control and sanction, but by a peer pressure. The obligations of the Contracting Parties are mainly based on the international safety standards developed by the IAEA in past decades. The Convention is intended for all countries generating radioactive waste. Therefore it is relevant not only for those using nuclear power, but for any country where application of nuclear energy in medicine, conventional industry and research is currently used. Obligations of Contracting Parties include attending periodic Review Meetings and prepare National Reports for review by the other Contracting Parties. The National Reports should describe how the country is complying with the requirements of the Articles of the Convention. The first such meeting was held at the IAEA headquarters in November 2003. This paper will describe the origin of the Convention, present its content, the expected outcome for the worldwide safety, and the benefits for a country to be part of it

  3. International Conference on the Safety of Radioactive Waste Management. Book of Papers

    International Nuclear Information System (INIS)

    2016-01-01

    The purpose of the conference was to highlight the importance of an integrated long term approach to the management of radioactive waste and spent fuel. The objectives of the conference were: • To foster information exchange between Member States, • To provide inputs that will promote further harmonization of safety in the fields of predisposal management and disposal of radioactive waste, • To highlight progress made in the safety of all types of radioactive waste. The conference served as a forum for discussing past experiences and future challenges. Furthermore, it seeked to identify Member States’ needs in order to assist them — through specific activities under future IAEA programmes in this area — to develop and implement safe solutions for the management of their entire radioactive waste inventory. The conference addressed all aspects of predisposal management and disposal of radioactive waste and spent fuel, including waste arising from accidental situations. The management of radioactive waste and residues from mining activities, as well as the control of discharges from nuclear facilities and activities, were, however, outside of its scope.

  4. Environment, Safety, Health and Waste Management Plan

    International Nuclear Information System (INIS)

    1988-01-01

    The mission of the Feed Materials Production Center (FMPC) is the production of high qaulity uranium metal for use by the US Department of Energy (DOE) in Defense Programs. In order to accomplish this mission and to maintain the FMPC as a viable facility in the DOE production complex, the facility must be brought into full compliance with all federal and state regulations and industry standards for environmental protection and worker safety. Where past practices have resulted in environmental insult, a comprehensive program of remediation must be implemented. The purpose of this combined Environment, Safety, Health and Waste Management Plan is to provide a road map for achieving needed improvements. The plan is structured to provide a comprehensive projection from the current fiscal year (FY) through FY 1994 of the programs, projects and funding required to achieve compliance. To do this, the plan is subdivided into chapters which discuss the applicable regulations;project schedules and funding requirements;details of the various programs for environment, safety, health and waste management;details of the ongoing National Environmental Policy Act (NEPA);the quality assurance program and the environmental monitoring program. 14 refs., 30 figs., 29 tabs

  5. Knowledge, Attitude and Practice of Healthcare Managers to Medical Waste Management and Occupational Safety Practices: Findings from Southeast Nigeria.

    Science.gov (United States)

    Anozie, Okechukwu Bonaventure; Lawani, Lucky Osaheni; Eze, Justus Ndulue; Mamah, Emmanuel Johnbosco; Onoh, Robinson Chukwudi; Ogah, Emeka Onwe; Umezurike, Daniel Akuma; Anozie, Rita Onyinyechi

    2017-03-01

    Awareness of appropriate waste management procedures and occupational safety measures is fundamental to achieving a safe work environment, and ensuring patient and staff safety. This study was conducted to assess the attitude of healthcare managers to medical waste management and occupational safety practices. This was a cross-sectional study conducted among 54 hospital administrators in Ebonyi state. Semi-structured questionnaires were used for qualitative data collection and analyzed with SPSS statistics for windows (2011), version 20.0 statistical software (Armonk, NY: IBM Corp). Two-fifth (40%) of healthcare managers had received training on medical waste management and occupational safety. Standard operating procedure of waste disposal was practiced by only one hospital (1.9%), while 98.1% (53/54) practiced indiscriminate waste disposal. Injection safety boxes were widely available in all health facilities, nevertheless, the use of incinerators and waste treatment was practiced by 1.9% (1/54) facility. However, 40.7% (22/54) and 59.3% (32/54) of respondents trained their staff and organize safety orientation courses respectively. Staff insurance cover was offered by just one hospital (1.9%), while none of the hospitals had compensation package for occupational hazard victims. Over half (55.6%; 30/54) of the respondents provided both personal protective equipment and post exposure prophylaxis for HIV. There was high level of non-compliance to standard medical waste management procedures, and lack of training on occupational safety measures. Relevant regulating agencies should step up efforts at monitoring and regulation of healthcare activities and ensure staff training on safe handling and disposal of hospital waste.

  6. Safety and cost evaluation of nuclear waste management

    International Nuclear Information System (INIS)

    Vieno, T.; Hautojaervi, A.; Korhonen, R.

    1989-11-01

    The report introduces the results of the nuclear waste management safety and cost evaluation research carried out in the Nuclear Engineering Laboratory of the Technical Research Centre of Finland (VTT) during the years 1984-1988. The emphasis is on the description of the state-of-art of performance and cost evaluation methods. The report describes VTT's most important assessment models. Development, verification and validation of the models has largely taken place within international projects, including the Stripa, HYDROCOIN, INTRACOIN, INTRAVAL, PSACOIN and BIOMOVS projects. Furthermore, VTT's other laboratories are participating in the Natural Analogue Working Group,k the CHEMVAL project and the CoCo group. Resent safety analyses carried out in the Nuclear Engineering Laboratory include a concept feasibility study of spent fuel disposal, safety analyses for the Preliminary Safety Analysis Reports (PSAR's) of the repositories to be constructed for low and medium level operational reactor waste at the Olkiluoto and Loviisa power plants as well as safety analyses of disposal of decommissioning wastes. Appendix 1 contains a comprehensive list of the most important publications and technical reports produced. They present the content and results of the research in detail

  7. Norwegian national report. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management

    International Nuclear Information System (INIS)

    2011-11-01

    This report contains the national report from Norway to the fourth review meeting of the JointConvention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management to be held 14-23 May 2012. (Author)

  8. Comprehensive safety cases for radioactive waste management facilities

    International Nuclear Information System (INIS)

    Woollam, P.B.; Cameron, H.M.; Davies, A.R.; Hiscox, A.W.

    1995-01-01

    Probabilistic safety assessment methodology has been applied by Nuclear Electric plc (NE) to the development of comprehensive safety cases for the radioactive waste management processing and accumulation facilities associated with its 26 reactor systems. This paper describes the methodology and the safety case assessment criteria employed by NE. An overview of the results is presented, together with more detail of a specific safety analysis: storage of fuel element debris. No risk to the public greater than 10 -6 /y has been identified and the more significant risks arise from the potential for radioactive waste fires. There are no unacceptable risks from external hazards such as flooding, aircrash or seismic events. Some operations previously expected to have significant risks in fact have negligible risks, while the few faults with risks exceeding the assessment criteria were only identified as a result of this study

  9. Safety studies project on waste management. Final report. Chapters 2 and 3

    International Nuclear Information System (INIS)

    1985-01-01

    The report presents, in summary form, a mode of procedure for accident analysis in nuclear waste management facilities. New instruments for safety analysis have been developed and tested. The report describes exemplary safety analyses with the new instrumentation. The safety analyses were carried out in surface systems, i.e. reprocessing and waste treatment systems, and in underground nuclear waste storage road and rail transport of radioactive materials have been investigated. (EF) [de

  10. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management

    International Nuclear Information System (INIS)

    1997-01-01

    The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was adopted on 5 September 1997 by a Diplomatic Conference convened by the IAEA from 1 to 5 September 1997. The Joint Convention was opened for signature at Vienna on 29 September 1997 during the forty-first session of the General Conference of the IAEA. This document reproduces the text of the Convention

  11. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-24

    The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was adopted on 5 September 1997 by a Diplomatic Conference convened by the IAEA from 1 to 5 September 1997. The Joint Convention was opened for signature at Vienna on 29 September 1997 during the forty-first session of the General Conference of the IAEA. This document reproduces the text of the Convention.

  12. Comprehensive safety cases for radioactive waste management facilities

    International Nuclear Information System (INIS)

    Woollam, P.B.

    1993-01-01

    Probabilistic safety assessment methodology is being applied by Nuclear Electric plc (NE) to the development of comprehensive safety cases for the radioactive waste management processing and accumulation facilities associated with its 26 reactor systems. This paper describes the methodology and the safety case assessment criteria employed by NE. An overview of the results from facilities used by the first 16 reactors is presented, together with more detail of a specific safety analysis: storage of fuel element debris. No risk to the public greater than 10 -6 /y has been identified and the more significant risks arise from the potential for radioactive waste fires. There are no unacceptable risks from external hazards such as flooding, aircrash or seismic events. Some operations previously expected to have significant risks in fact have negligible risks, while the few faults with risks exceeding the assessment criteria were only identified as a result of this study

  13. Area 5 Radioactive Waste Management Site Safety Assessment Document

    International Nuclear Information System (INIS)

    Horton, K.K.; Kendall, E.W.; Brown, J.J.

    1980-02-01

    The Area 5 Radioactive Waste Management Safety Assessment Document evaluates site characteristics, facilities and operating practices which contribute to the safe handling and storage/disposal of radioactive wastes at the Nevada Test Site. Physical geography, cultural factors, climate and meteorology, geology, hydrology (with emphasis on radionuclide migration), ecology, natural phenomena, and natural resources are discussed and determined to be suitable for effective containment of radionuclides. Also considered, as a separate section, are facilities and operating practices such as monitoring; storage/disposal criteria; site maintenance, equipment, and support; transportation and waste handling; and others which are adequate for the safe handling and storage/disposal of radioactive wastes. In conclusion, the Area 5 Radioactive Waste Management Site is suitable for radioactive waste handling and storage/disposal for a maximum of twenty more years at the present rate of utilization

  14. Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. National Report from Norway

    International Nuclear Information System (INIS)

    2006-05-01

    This report is the Norwegian report to the second review meeting to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The comments, questions and remarks given to Norway's initial national report and Norway's presentation given at the first review meeting have been incorporated in this report. The second report is a full revision of the first report. This report concludes that Norway meets the obligations of the Joint Convention. However, Norwegian authorities will aim for development in the waste management policy and Norway will continue to improve its existing systems to further enhance safety, in line with the aims of the Joint Convention

  15. Institute of Energy and Climate Research IEK-6. Nuclear waste management and reactor safety report 2009/2010. Material science for nuclear waste management

    International Nuclear Information System (INIS)

    Klinkenberg, M.; Neumeier, S.; Bosbach, D.

    2011-01-01

    Due to the use of nuclear energy about 17.000 t (27.000 m 3 ) of high level waste and about 300.000 m 3 of low and intermediated level waste will have accumulated in Germany until 2022. Research in the Institute of Energy and Climate Research (IEK-6), Nuclear Waste Management and Reactor Safety Division focuses on fundamental and applied aspects of the safe management of nuclear waste - in particular the nuclear aspects. In principle, our research in Forschungszentrum Juelich is looking at the material science/solid state aspects of nuclear waste management. It is organized in several research areas: The long-term safety of nuclear waste disposal is a key issue when it comes to the final disposal of high level nuclear waste in a deep geological formation. We are contributing to the scientific basis for the safety case of a nuclear waste repository in Germany. In Juelich we are focusing on a fundamental understanding of near field processes within a waste repository system. The main research topics are spent fuel corrosion and the retention of radionuclides by secondary phases. In addition, innovative waste management strategies are investigated to facilitate a qualified decision on the best strategy for Germany. New ceramic waste forms for disposal in a deep geological formation are studied as well as the partitioning of long-lived actinides. These research areas are supported by our structure research group, which is using experimental and computational approaches to examine actinide containing compounds. Complementary to these basic science oriented activities, IEK-6 also works on rather applied aspects. The development of non-destructive methods for the characterisation of nuclear waste packages has a long tradition in Juelich. Current activities focus on improving the segmented gamma scanning technique and the prompt gamma neutron activation analysis. Furthermore, the waste treatment group is developing concepts for the safe management of nuclear graphite

  16. Institute of Energy and Climate Research IEK-6. Nuclear waste management and reactor safety report 2009/2010. Material science for nuclear waste management

    Energy Technology Data Exchange (ETDEWEB)

    Klinkenberg, M; Neumeier, S; Bosbach, D [eds.

    2011-07-01

    Due to the use of nuclear energy about 17.000 t (27.000 m{sup 3}) of high level waste and about 300.000 m{sup 3} of low and intermediated level waste will have accumulated in Germany until 2022. Research in the Institute of Energy and Climate Research (IEK-6), Nuclear Waste Management and Reactor Safety Division focuses on fundamental and applied aspects of the safe management of nuclear waste - in particular the nuclear aspects. In principle, our research in Forschungszentrum Juelich is looking at the material science/solid state aspects of nuclear waste management. It is organized in several research areas: The long-term safety of nuclear waste disposal is a key issue when it comes to the final disposal of high level nuclear waste in a deep geological formation. We are contributing to the scientific basis for the safety case of a nuclear waste repository in Germany. In Juelich we are focusing on a fundamental understanding of near field processes within a waste repository system. The main research topics are spent fuel corrosion and the retention of radionuclides by secondary phases. In addition, innovative waste management strategies are investigated to facilitate a qualified decision on the best strategy for Germany. New ceramic waste forms for disposal in a deep geological formation are studied as well as the partitioning of long-lived actinides. These research areas are supported by our structure research group, which is using experimental and computational approaches to examine actinide containing compounds. Complementary to these basic science oriented activities, IEK-6 also works on rather applied aspects. The development of non-destructive methods for the characterisation of nuclear waste packages has a long tradition in Juelich. Current activities focus on improving the segmented gamma scanning technique and the prompt gamma neutron activation analysis. Furthermore, the waste treatment group is developing concepts for the safe management of nuclear

  17. The safety concept of the Federal Government concerning waste management

    International Nuclear Information System (INIS)

    Pfaffelhuber, J.K.

    1976-01-01

    The safety concept of the FRG concerning waste management is based on the ultimate aim of having in operation until 1985 nuclear power plants with a capacity of approx. 45,000 MWe, i.e. 50 nuclear power plants with an annual fuel consumption of 1,500 tons. A critical survey shows that there is still a great number of questions to be solved, concerning the fuel cycle in particular in terms of industrial standards, and that various problems ought to be the subject of R and D activities. Activities in the field of waste management so far are concerned only with project studies and details of project definition studies. On the one hand, the principles of the safety concept for waste management are to make possible and to guarantee the operation of nuclear facilities, and on the other hand, they are to subject those facilities which serve the purpose of waste disposal to similar safety regulations as the nuclear power plants are subjected to. The integrated waste disposal system of the Federal government for CWRs until the mid eighties is described. R+D activities are still necessary, in particular concerning reprocessing techniques, techniques in the reprocessing of Pu, the conditioning of highly active wastes, testing final storage techniques, and in the field of retention of gaseous radioactive nuclides (iodine, krypton, tritium) and of safeguarding waste disposal parks against terrorists and sabotage. The legal basis for the protection of the citizen is the Atomic Energy Act and its ordinances, EURATOM basic standards, and ICRP recommendations, some of which were tightened up for the FRG. Some recommendations of the Strahlenschutzkommision - radiation exposure, storage and separation of 85 Kr, 129 J, 131 J, and 133 Xe - are dealt with in detail. (HPH/LN) [de

  18. Institute of Energy and Climate Research IEK-6. Nuclear waste management and reactor safety report 2009/2010. Material science for nuclear waste management

    Energy Technology Data Exchange (ETDEWEB)

    Klinkenberg, M.; Neumeier, S.; Bosbach, D. (eds.)

    2011-07-01

    Due to the use of nuclear energy about 17.000 t (27.000 m{sup 3}) of high level waste and about 300.000 m{sup 3} of low and intermediated level waste will have accumulated in Germany until 2022. Research in the Institute of Energy and Climate Research (IEK-6), Nuclear Waste Management and Reactor Safety Division focuses on fundamental and applied aspects of the safe management of nuclear waste - in particular the nuclear aspects. In principle, our research in Forschungszentrum Juelich is looking at the material science/solid state aspects of nuclear waste management. It is organized in several research areas: The long-term safety of nuclear waste disposal is a key issue when it comes to the final disposal of high level nuclear waste in a deep geological formation. We are contributing to the scientific basis for the safety case of a nuclear waste repository in Germany. In Juelich we are focusing on a fundamental understanding of near field processes within a waste repository system. The main research topics are spent fuel corrosion and the retention of radionuclides by secondary phases. In addition, innovative waste management strategies are investigated to facilitate a qualified decision on the best strategy for Germany. New ceramic waste forms for disposal in a deep geological formation are studied as well as the partitioning of long-lived actinides. These research areas are supported by our structure research group, which is using experimental and computational approaches to examine actinide containing compounds. Complementary to these basic science oriented activities, IEK-6 also works on rather applied aspects. The development of non-destructive methods for the characterisation of nuclear waste packages has a long tradition in Juelich. Current activities focus on improving the segmented gamma scanning technique and the prompt gamma neutron activation analysis. Furthermore, the waste treatment group is developing concepts for the safe management of nuclear

  19. Safety research activities on radioactive waste management in JNES

    International Nuclear Information System (INIS)

    Otsuka, Ichiro; Aoki, Hiroomi; Suko, Takeshi; Onishi, Yuko; Masuda, Yusuke; Kato, Masami

    2010-01-01

    Research activities in safety regulation of radioactive waste management are presented. Major activities are as follows. As for the geological disposal, major research areas are, developing 'safety indicators' to judge the adequacy of site investigation results presented by an implementer (NUMO), compiling basic requirements of safety design and safety assessment needed to make a safety review of the license application and developing an independent safety assessment methodology. In proceeding research, JNES, Japan Atomic Energy Agency (JAEA) and the National Institute of Advanced Industrial Science and Technology (AIST) signed an agreement of cooperative study on geological disposal in 2007. One of the ongoing joint studies under this agreement has been aimed at investigating regional-scale hydrogeological modeling using JAEA's Horonobe Underground Research Center. In the intermediate depth disposal, JNES conducted example analysis of reference facility and submitted the result to Nuclear Safety Commission of Japan (NSC). JNES is also listing issues to be addressed in the safety review of the license application and tries to make criteria of the review. Furthermore, JNES is developing analysis tool to evaluate long term safety of the facility and conducting an experiment to investigate long term behavior of engineered barrier system. In the near surface disposal of waste package, it must be confirmed by a regulatory inspector whether each package meets safety requirements. JNES continuously updates the confirmation methodology depending on new processing technologies. The clearance system was established in 2005. Two stages of regulatory involvement were adapted, 1) approval for measurement and judgment methods developed by the nuclear operator and 2) confirmation of measurement and judgment results based on approved methods. JNES is developing verification methodology for each stage. As for decommissioning, based on the regulatory needs and a research program

  20. Management of waste from the use of radioactive material in medicine, industry, agriculture, research and education safety guide

    CERN Document Server

    2005-01-01

    This Safety Guide provides recommendations and guidance on the > fulfilment of the safety requirements established in Safety Standards > Series No. WS-R-2, Predisposal Management of Radioactive Waste, > Including Decommissioning. It covers the roles and responsibilities of > different bodies involved in the predisposal management of radioactive > waste and in the handling and processing of radioactive material. It > is intended for organizations generating and handling radioactive > waste or handling such waste on a centralized basis for and the > regulatory body responsible for regulating such activities.  > Contents: 1. Introduction; 2. Protection of human health and the > environment; 3. Roles and responsibilities; 4. General safety > considerations; 5. Predisposal management of radioactive waste; 6. > Acceptance of radioactive waste in disposal facilities; 7. Record > keeping and reporting; 8. Management systems; Appendix I: Fault > schedule for safety assessment and environmental impact assessment; > Ap...

  1. Management of Radioactive Waste from the Mining and Milling of Ores. Safety Guide (Spanish ed.)

    International Nuclear Information System (INIS)

    2010-01-01

    This Safety Guide provides recommendations and guidance on the safe management of radioactive waste resulting from the mining and milling of ores, with the purpose of protecting workers, the public and the environment from the consequences of these activities. It supplements Safety Standards Series No. WS-R-1, Near Surface Disposal of Radioactive Waste. Contents: 1. Introduction; 2. Administrative, legal and regulatory framework; 3. Protection of human health and the environment; 4. Strategy for waste management; 5. Safety considerations in different phases of operations; 6. Safety assessment; 7. Quality assurance; 8. Monitoring and surveillance; 9. Institutional control for the post-closure phase.

  2. Tank waste remediation system nuclear criticality safety program management review

    International Nuclear Information System (INIS)

    BRADY RAAP, M.C.

    1999-01-01

    This document provides the results of an internal management review of the Tank Waste Remediation System (TWRS) criticality safety program, performed in advance of the DOE/RL assessment for closure of the TWRS Nuclear Criticality Safety Issue, March 1994. Resolution of the safety issue was identified as Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-40-12, due September 1999

  3. RADWASS update. Radioactive Waste Safety Standards Programme

    International Nuclear Information System (INIS)

    Delattre, D.

    2000-01-01

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

  4. The role of health and safety experts in the management of hazardous and toxic wastes in Indonesia

    Science.gov (United States)

    Supriyadi; Hadiyanto

    2018-02-01

    Occupational Safety and Health Experts in Indonesia have an important role in integrating environmental health and safety factors, including in this regard as human resources assigned to undertake hazardous waste management. Comprehensive knowledge and competence skills need to be carried out responsibly, as an inherent professional occupational safety and health profession. Management leaders should continue to provide training in external agencies responsible for science in the management of toxic waste to enable occupational safety and health experts to improve their performance in the hierarchy of control over the presence of hazardous materials. This paper provides an overview of what strategies and competencies the Occupational Safety and Health expert needs to have in embracing hazardous waste management practices.

  5. Introduction to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management and Canada's participation

    International Nuclear Information System (INIS)

    Mecke, J.L.

    2011-01-01

    The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) is the first and the only legally binding international instrument to address safety issues concerning the management of spent fuel and radioactive waste on a global scale. It entered into force on June 18, 2001. The Government of Canada strongly supported international efforts to bring into force the Joint Convention and was the second country to ratify it. The Joint Convention is an 'incentive instrument' that is based on peer review (similar in that respect to the Convention on Nuclear Safety) and devised to encourage countries that are Contracting Parties to report and to foster open and frank discussions on the safety of spent fuel and radioactive waste management. Being an incentive convention, it is not designed to mandate Contracting Parties to fulfill its obligation through control and sanction, but it is based on the common objectives of Contracting Parties to achieve and maintain a high level of safety in spent fuel and radioactive waste management, protect individuals, society and the environment from ionizing radiation and prevent accidents and if necessary mitigating the consequences of such accidents. The following paper will provide an introduction to the Joint Convention and provide a summary of Canada's peer review at the most recent Review Meeting which was held on May 11-20, 2009, at the International Atomic Energy Agency (IAEA) headquarters in Vienna, Austria. (author)

  6. Eurosafe 2006 radioactive waste management: long term safety requirements and societal expectations

    International Nuclear Information System (INIS)

    2006-01-01

    The EUROSAFE Forum is part of the EUROSAFE approach, which consists of two further elements: the EUROSAFE Tribune and the EUROSAFE web site. The general aim of EUROSAFE is to contribute to fostering the convergence of technical nuclear safety practices in a broad European context. This is done by providing technical safety and research organisations, safety authorities, power utilities, the rest of the industry and non-governmental organisations mainly from the European Union and East-European countries, and international organisations with a platform for the presentation of recent analyses and R and D in the field of nuclear safety, to share experiences, exchange technical and scientific opinions, and conduct debates on key issues in the fields of nuclear safety and radiation protection. The EUROSAFE Forum 2006 focuses on 'Radioactive Waste Management: Long Term Safety Requirements and Societal Expectations' from the point of view of the authorities, TSOs and industry and presents the latest work in nuclear installation safety and research, waste management, radiation safety as well as nuclear material and nuclear facilities security carried out by GRS, IRSN, AVN and their partners in the European Union, Switzerland and Eastern Europe. A high level of nuclear safety is a priority for Europe. The technical safety organisations play an important role in contributing to that objective through appropriate approaches to major safety issues as part of their assessments and research activities. The challenges to nuclear safety are international. Changes in underlying technologies such as instrumentation and control, the impact of electricity market deregulation, demands for improved safety and safety management, the ageing of nuclear facilities, waste management, maintaining and improving scientific and technical knowledge, and the need for greater transparency - these are all issues where the value of an international approach is gaining increasing recognition. This

  7. Eurosafe 2006 radioactive waste management: long term safety requirements and societal expectations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The EUROSAFE Forum is part of the EUROSAFE approach, which consists of two further elements: the EUROSAFE Tribune and the EUROSAFE web site. The general aim of EUROSAFE is to contribute to fostering the convergence of technical nuclear safety practices in a broad European context. This is done by providing technical safety and research organisations, safety authorities, power utilities, the rest of the industry and non-governmental organisations mainly from the European Union and East-European countries, and international organisations with a platform for the presentation of recent analyses and R and D in the field of nuclear safety, to share experiences, exchange technical and scientific opinions, and conduct debates on key issues in the fields of nuclear safety and radiation protection. The EUROSAFE Forum 2006 focuses on 'Radioactive Waste Management: Long Term Safety Requirements and Societal Expectations' from the point of view of the authorities, TSOs and industry and presents the latest work in nuclear installation safety and research, waste management, radiation safety as well as nuclear material and nuclear facilities security carried out by GRS, IRSN, AVN and their partners in the European Union, Switzerland and Eastern Europe. A high level of nuclear safety is a priority for Europe. The technical safety organisations play an important role in contributing to that objective through appropriate approaches to major safety issues as part of their assessments and research activities. The challenges to nuclear safety are international. Changes in underlying technologies such as instrumentation and control, the impact of electricity market deregulation, demands for improved safety and safety management, the ageing of nuclear facilities, waste management, maintaining and improving scientific and technical knowledge, and the need for greater transparency - these are all issues where the value of an international approach is gaining increasing recognition. This

  8. Eurosafe 2006 radioactive waste management: long term safety requirements and societal expectations

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The EUROSAFE Forum is part of the EUROSAFE approach, which consists of two further elements: the EUROSAFE Tribune and the EUROSAFE web site. The general aim of EUROSAFE is to contribute to fostering the convergence of technical nuclear safety practices in a broad European context. This is done by providing technical safety and research organisations, safety authorities, power utilities, the rest of the industry and non-governmental organisations mainly from the European Union and East-European countries, and international organisations with a platform for the presentation of recent analyses and R and D in the field of nuclear safety, to share experiences, exchange technical and scientific opinions, and conduct debates on key issues in the fields of nuclear safety and radiation protection. The EUROSAFE Forum 2006 focuses on 'Radioactive Waste Management: Long Term Safety Requirements and Societal Expectations' from the point of view of the authorities, TSOs and industry and presents the latest work in nuclear installation safety and research, waste management, radiation safety as well as nuclear material and nuclear facilities security carried out by GRS, IRSN, AVN and their partners in the European Union, Switzerland and Eastern Europe. A high level of nuclear safety is a priority for Europe. The technical safety organisations play an important role in contributing to that objective through appropriate approaches to major safety issues as part of their assessments and research activities. The challenges to nuclear safety are international. Changes in underlying technologies such as instrumentation and control, the impact of electricity market deregulation, demands for improved safety and safety management, the ageing of nuclear facilities, waste management, maintaining and improving scientific and technical knowledge, and the need for greater transparency - these are all issues where the value of an international approach is gaining increasing recognition

  9. Development of Legal and Regulatory Framework for Radioactive Waste Management Safety in the Russian Federation

    International Nuclear Information System (INIS)

    Kudryavtsev, E.

    2016-01-01

    Key RW management challenges in Russian Federation: - Full-scale implementation of legislation for radioactive waste management including administrative arrangements; - Transition from RW storage to RW conditioning and final disposal; - Construction of RW disposal facilities for accumulated waste; - Safety of waste management in connection with decommissioning and remediation activity; - Nuclear legacy liability: balanced approach to RW classification and management options in terms of “exceptional” and “retrievable” waste categories

  10. French regulations and waste management

    International Nuclear Information System (INIS)

    Sousselier, Y.

    1985-01-01

    The authors describe the organization and the role of safety authorities in France in matter of waste management. They precise the French policy in waste storage and treatment: basic objectives, optimization of waste management. The safety requirements are based upon the barrier principle. Safety requirements about waste conditioning and waste disposal are mentioned. In addition to the safety analysis and studies described above, the Protection and Nuclear Safety Institute assists the ministerial authorities in the drafting of ''basic safety rules (RFS)'', laying down safety objectives. Appendix 1 and Appendix 2 deal with safety aspects in spent fuel storage and in transportation of radioactive materials [fr

  11. Steps for safety. Radioactive waste management facilities and Y2K

    International Nuclear Information System (INIS)

    Warnecke, E.

    1999-01-01

    As part of the IAEA activities concerned with Year 2000 (Y2K) problem special attention is paid to operation of radioactive waste management facilities although, fortunately, in the management of radioactive materials the response of a process or activity to a failure would be slow in many instance, providing more time to resolve the issue before any radiological consequences occur. To facilitate greater cooperation, the IAEA organized an international workshop on the exchange of information concerning safety measure to address the Y2K issues on radioactive waste management and nuclear fuel cycle facilities

  12. Geological disposal of radioactive waste. Safety requirements

    International Nuclear Information System (INIS)

    2006-01-01

    This Safety Requirements publication is concerned with providing protection to people and the environment from the hazards associated with waste management activities related to disposal, i.e. hazards that could arise during the operating period and following closure. It sets out the protection objectives and criteria for geological disposal and establishes the requirements that must be met to ensure the safety of this disposal option, consistent with the established principles of safety for radioactive waste management. It is intended for use by those involved in radioactive waste management and in making decisions in relation to the development, operation and closure of geological disposal facilities, especially those concerned with the related regulatory aspects. This publication contains 1. Introduction; 2. Protection of human health and the environment; 3. The safety requirements for geological disposal; 4. Requirements for the development, operation and closure of geological disposal facilities; Appendix: Assurance of compliance with the safety objective and criteria; Annex I: Geological disposal and the principles of radioactive waste management; Annex II: Principles of radioactive waste management

  13. Alternatives for radioactive waste management

    International Nuclear Information System (INIS)

    Bartlett, J.W.

    1975-10-01

    The safety aspects of waste management alternatives are emphasized. The options for waste management, their safety characteristics, and the methods that might be used to evaluate the options and their safety are outlined

  14. Safety assessment for the above ground storage of Cadmium Safety and Control Rods at the Solid Waste Management Facility

    International Nuclear Information System (INIS)

    Shaw, K.W.

    1993-11-01

    The mission of the Savannah River Site is changing from radioisotope production to waste management and environmental restoration. As such, Reactor Engineering has recently developed a plan to transfer the safety and control rods from the C, K, L, and P reactor disassembly basin areas to the Transuranic (TRU) Waste Storage Pads for long-term, retrievable storage. The TRU pads are located within the Solid Waste Management Facilities at the Savannah River Site. An Unreviewed Safety Question (USQ) Safety Evaluation has been performed for the proposed disassembly basin operations phase of the Cadmium Safety and Control Rod Project. The USQ screening identified a required change to the authorization basis; however, the Proposed Activity does not involve a positive USQ Safety Evaluation. A Hazard Assessment for the Cadmium Safety and Control Rod Project determined that the above-ground storage of the cadmium rods results in no change in hazard level at the TRU pads. A Safety Assessment that specifically addresses the storage (at the TRU pads) phase of the Cadmium Safety and Control Rod Project has been performed. Results of the Safety Assessment support the conclusion that a positive USQ is not involved as a result of the Proposed Activity

  15. 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

  16. 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.

  17. 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

  18. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Report of the Federal Republic of Germany for the sixth review meeting in May 2018

    International Nuclear Information System (INIS)

    2017-08-01

    The joint convention on the safety of spent fuel management and on the safety of radioactive waste management covers the following topics: historical development and actual status of the civil use of nuclear power, politics and the spent fuel management, inventories and listing, legislation and executive systems, other safeguard regulations, safety during spent fuel handling, safety during radioactive waste processing, transport across national borders, disused enclosed radioactive sources, general regulations for safety enhancement.

  19. Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. National Report of the Kingdom of the Netherlands

    International Nuclear Information System (INIS)

    2005-10-01

    On 10 March 1999, the Netherlands signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, which was subsequently formally ratified on 26 April 2000 and entered into force on 18 June 2001. The Joint Convention obliges each contracting party to apply widely recognized principles and tools in order to achieve and maintain high standards of safety during management of spent fuel and radioactive waste. The Joint Convention also requires each party to report on the national implementation of these principles to review meetings of the parties to this Convention. This report describes the manner in which the Netherlands is fulfilling its obligations under the Joint Convention

  20. Environmental and safety problems of waste management in nuclear engineering

    International Nuclear Information System (INIS)

    Schwibach, J.; Jacobi, W.

    1976-01-01

    The environmental and safety problems which waste management in nuclear technology poses are discussed under the aspects of the disposal of radioactive waste by nuclear facilities and the safety of radioactive waste disposal. The release and global distribution of long-lived radionuclides such as tritium, Kr-85, C-14, I-129, and Pu-239 as well as the radiation exposure of the world population resulting thereof are investigated, the authors starting from a specific production rate of the nuclides released from nuclear facilities. Definitions of the terms 'dose commitment' and 'collective dose commitment' are given. Furthermore, local radiation exposure in reprocessing plants is investigated and compared with regional and global radiation exposure. A recommendation is made to take measures which would reduce the nuclides tritium, Kr-85, and C-14 in order to achieve considerably smaller collective doses. (HR/LN) [de

  1. Radiation Protection and Radioactive Waste Management in the Operation of Nuclear Power Plants. Safety Guide (Spanish Edition)

    International Nuclear Information System (INIS)

    2010-01-01

    The purpose of this Safety Guide is to provide recommendations to the regulatory body, focused on the operational aspects of radiation protection and radioactive waste management in nuclear power plants, and on how to ensure the fulfilment of the requirements established in the relevant Safety Requirements publications. It will also be useful for senior managers in licensee or contractor organizations who are responsible for establishing and managing programmes for radiation protection and for the management of radioactive waste. This Safety Guide gives general recommendations for the development of radiation protection programmes at nuclear power plants. The issues are then elaborated by defining the main elements of a radiation protection programme. Particular attention is paid to area classification, workplace monitoring and supervision, application of the principle of optimization of protection (also termed the 'as low as reasonably achievable' (ALARA) principle), and facilities and equipment. This Safety Guide covers all the safety related aspects of a programme for the management of radioactive waste at a nuclear power plant. Emphasis is placed on the minimization of waste in terms of both activity and volume. The various steps in predisposal waste management are covered, namely processing (pretreatment, treatment and conditioning), storage and transport. Releases of effluents, the application of authorized limits and reference levels are discussed, together with the main elements of an environmental monitoring programme

  2. Waste management to improve food safety and security for health advancement.

    Science.gov (United States)

    Lin, Angela Yu-Chen; Huang, Susana Tzy-Ying; Wahlqvist, Mark L

    2009-01-01

    Economic growth inevitably influences the food chain. Growing demand with changes in lifestyle and health consciousness encourage use of packaged and pre-prepared foods. The needs of environmental protection from waste generated are largely overlooked, and a lack of knowledge about the impact on the environment and its health effects constitute food security/safety problems. Food production and waste generation directly affect resource (i.e., energy and water) consumption and often contaminate the environment. More pressure on food production has inculcated the use of pesticides, herbicides, antibiotics and chemical fertilizers which add to current global pollution. At least half of food grown is discarded before and after it reaches consumers. It is estimated that one third to half of landfill waste comes from the food sector. This landfill releases green house gases (GHG) as well as leachate which worsen soil and water quality and safety. Pharmaceutical and chemical contaminations from residential, industrial and agricultural sources make their way into nearby water and soil and can eventually affect our food systems. Phthalates, PFOA, BPA, commonly used in plastics and personal care products, are found in unacceptable concentrations in Taiwanese waters. They, too, contribute to food contamination and long-term health risk. Existing waste management strategies warrant more stringent norms for waste reduction at source. Awareness through education could reduce food waste and its consequences. This review encompasses impacts of food production systems on the environment, pollution which results from food waste, costs and economic advantages in food waste management, and health consequences of waste.

  3. The IAEA radioactive waste safety standards programme

    International Nuclear Information System (INIS)

    Tourtellotte, James R.

    1995-01-01

    The IAEA is currently reviewing more than thirty publications in its Safety Series with a view toward consolidating and organizing information pertaining to radioactive waste. the effort is entitled Radioactive Waste Safety Standards programme (RADWASS). RADWASS is a significant undertaking and may have far reaching effects on radioactive waste management both in the international nuclear community and in individual nuclear States. This is because IAEA envisions the development of a consensus on the final document. In this circumstance, the product of RADWASS may ultimately be regarded as an international norm against which future actions of Member States may be measured. This program is organized in five subjects: planning, pre-disposal, disposal, uranium and thorium waste management and decommissioning, which has four levels: safety fundamentals, safety standards, safety guides and safety practices. (author)

  4. The safety and environmental impact of nuclear wastes

    International Nuclear Information System (INIS)

    Luo Shanggeng

    2001-01-01

    Radioactive matters were discovered in 1989. Exploitation and using of nuclear energy and nuclear technologies bring mankind huge benefits, but the disposal of radioactive wastes is becoming one of the safety and environmental problems. The author describes six issues related to nuclear wastes. They are as follows: (1) The origin and characteristics of the nuclear wastes; (2) The principles of management of nuclear wastes established by the International Atomic Energy Agency (IAEA) as well as the Chinese '40 words principles' and the major tasks of Chinese nuclear waste management; (3) The treatment and disposal technologies of nuclear wastes and the emphasis on new technologies, waste minimization and exemption and clean release; (4) The safety management of spent radiation sources including technical and administrative measures; (5) The safety management of spent nuclear fuel and the emphasis on high level radioactive wastes to be safety disposed of; (6) The environmental impact of nuclear waste. The author takes the Qinshan Nuclear Power Plant and the Daya bay Nuclear Power Plant I, China, as two examples to prove that nuclear wastes can be safely controlled and managed to ensure environmental safety. The Chinese north-west disposal land of nuclear wastes under operation recently is also discussed. It is believed that the suggested disposal land can ensure the isolation of radioactive wastes and the surrounding environment according to the present standards. The north-west disposal land and the Beilong disposal land, Guangdong province, China, are built according to the international standard and advanced technologies

  5. Management of waste from the use of radioactive material in medicine, industry, agriculture, research and education. Safety guide

    International Nuclear Information System (INIS)

    2009-01-01

    Radioactive waste is generated in a broad range of activities involving the use of radioactive material in medicine, industry, agriculture, research and education. The amounts of waste generated from these activities are often limited in volume and activity. However, they have to be managed as radioactive waste. While the principles and safety requirements are the same for managing any amount of radioactive waste, a number of issues have to be considered specifically in organizations conducting activities in which only small amounts of waste are generated. This is the case in particular in respect of spent and disused sealed radioactive sources. For activities involving the generation and management of small amounts of radioactive waste, the types of facilities concerned and the arrangements for waste management vary considerably. Furthermore, the types of radioactive waste differ from facility to facility. The safe management of small amounts of radioactive waste should therefore be given specific consideration. The nature of the radioactive waste generated in the various activities under consideration also varies greatly. It may be in the form of discrete sealed or unsealed radiation sources or process materials or consumable materials. Waste arises as a result of many activities, including: diagnostic, therapeutic and research applications in medicine. Process control and measurement in industry. And numerous uses of radioactive material in agriculture, geological exploration, construction and other fields. The radioactive waste under consideration can be in solid, liquid or gaseous form. Solid waste can include: spent or disused sealed sources. Contaminated equipment, glassware, gloves and paper. And animal carcasses, excreta and other biological waste. Liquid waste can include: aqueous and organic solutions resulting from research and production processes. Excreta. Liquids arising from the decontamination of laboratory equipment or facilities. And liquids from

  6. Management of waste from the use of radioactive material in medicine, industry, agriculture, research and education. Safety guide

    International Nuclear Information System (INIS)

    2006-01-01

    Radioactive waste is generated in a broad range of activities involving the use of radioactive material in medicine, industry, agriculture, research and education. The amounts of waste generated from these activities are often limited in volume and activity. However, they have to be managed as radioactive waste. While the principles and safety requirements are the same for managing any amount of radioactive waste, a number of issues have to be considered specifically in organizations conducting activities in which only small amounts of waste are generated. This is the case in particular in respect of spent and disused sealed radioactive sources. For activities involving the generation and management of small amounts of radioactive waste, the types of facilities concerned and the arrangements for waste management vary considerably. Furthermore, the types of radioactive waste differ from facility to facility. The safe management of small amounts of radioactive waste should therefore be given specific consideration. The nature of the radioactive waste generated in the various activities under consideration also varies greatly. It may be in the form of discrete sealed or unsealed radiation sources or process materials or consumable materials. Waste arises as a result of many activities, including: diagnostic, therapeutic and research applications in medicine. Process control and measurement in industry. And numerous uses of radioactive material in agriculture, geological exploration, construction and other fields. The radioactive waste under consideration can be in solid, liquid or gaseous form. Solid waste can include: spent or disused sealed sources. Contaminated equipment, glassware, gloves and paper. And animal carcasses, excreta and other biological waste. Liquid waste can include: aqueous and organic solutions resulting from research and production processes. Excreta. Liquids arising from the decontamination of laboratory equipment or facilities. And liquids from

  7. The Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. An instrument to achieve a global safety

    International Nuclear Information System (INIS)

    Risoluti, P.

    2006-01-01

    The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management (the Joint Convention) is the first legally binding international treaty in the area of radioactive material management. It was adopted by a Diplomatic Conference in September 1997 and opened for signature on 29 September 1997. The Convention entered into force on 18 June 1998, and to date (May 2006) has been ratified by 41 countries. The Joint Convention applies to spent fuel and radioactive waste resulting from civilian application. Its principal aim is to achieve and maintain a high degree of safety in their management worldwide. The Convention is an incentive instrument, not designed to ensure fulfilment of obligations through control and sanction, but by a volunteer peer review mechanism. The obligations of the Contracting Parties are mainly based on the international safety standards developed by the IAEA in past decades. The Convention is of interest of all countries generating radioactive waste. Therefore it is relevant not only for those using nuclear power, but for any country where application of nuclear energy in education, agriculture, medicine and industry is currently used. Obligations of Contracting Parties include attending a Review Meeting held every three years and prepare National Reports for review by the other Contracting Parties. In the National Reports basic information on inventory and facilities for management of radioactive materials has to be provided. Countries with small nuclear power and/or research programs or countries having radioactive materials only from nuclear application on medicine, agriculture or conventional industry, can benefit from the exchange of information and the technical knowledge gained by the reporting procedure set up by the Convention. The second Review Meeting is to be held at IAEA headquarters from 15 to 26 May 2006. This paper presents the objectives and the implementation status of the Convention, the

  8. OCRWM [Office of Civilian Radioactive Waste Management] Safety Plan

    International Nuclear Information System (INIS)

    1986-12-01

    The OCRWM Safety Plan sets forth management policies and general requirements for the safety of the public and of personnel associated with the Civilian Radioactive Waste Management Program (hereinafter called the ''Program''). It is applicable to all individuals and organizational elements of the Program, including all facilities and activities controlled by the Program pursuant to the Act, and to all phases of the Program. The plan defines the responsibilities assigned by the Director of the OCRWM to the various OCRWM line organizations, and to the contractors and the projects. It discusses the means by which safety policies and requirements will be communicated, and summarizes the applicable DOE Orders, and the procedures for reviewing, reporting, and evaluating safety problems. In addition, the OCRWM Safety Plan addresses DOE Orders applicable to occupational health and safety, worker protection, and public health and safety. OCRWM believes that it has an equally high level of commitment to both public safety and worker safety. The Plan also summarizes applicable NRC criteria and regulations that will be imposed through the formal licensing proceedings. While the Safety Plan sets forth OCRWM policy, it is not intended to be prescriptive in the details of implementation. Each OCRWM program element must develop and control its own set of detailed requirements for the protection of its workers and the public based on the principles set forth herein

  9. Principles and objective of radioactive waste management

    International Nuclear Information System (INIS)

    Warnecke, E.

    1995-01-01

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

  10. Nuclear Facility Isotopic Content (NFIC) Waste Management System to provide input for safety envelope definition

    International Nuclear Information System (INIS)

    Genser, J.R.

    1992-01-01

    The Westinghouse Savannah River Company (WSRC) is aggressively applying environmental remediation and radioactive waste management activities at the US Department of Energy's Savannah River Site (SRS) to ensure compliance with today's challenging governmental laws and regulatory requirements. This report discusses a computer-based Nuclear Facility Isotopic Content (NFIC) Waste Management System developed to provide input for the safety envelope definition and assessment of site-wide facilities. Information was formulated describing the SRS ''Nuclear Facilities'' and their respective bounding inventories of nuclear materials and radioactive waste using the NFIC Waste Management System

  11. Institute of Energy and Climate Research IEK-6 : nuclear waste management & reactor safety report 2009/2010 ; material science for nuclear waste management

    OpenAIRE

    Klinkenberg, M.; Neumeier, S.; Bosbach, D. (Editors)

    2011-01-01

    This is the first issue of a new series of bi-annual reports intended to provide an overview of research activities for the safe management of nuclear waste in the Institute of Energy and Climate Research (IEK-6), Nuclear Waste Management and Reactor Safety devision in Jülich. The report gives a thematic overview of the research in 2009 and 2010 by short papers of five to eight pages. Some papers are discussing the work within different projects with intensive overlap, such as ...

  12. Proceedings of the research conference on post-accident waste management safety (RCWM2016) and the technical seminar on safety research for radioactive waste storage

    International Nuclear Information System (INIS)

    Motooka, Takafumi; Yamagishi, Isao

    2017-03-01

    Collaborative Laboratories for Advanced Decommissioning Science (CLADS) is responsible to promote international cooperation in the R and D activities on the decommissioning of Fukushima Daiichi Nuclear Power Station and to develop the necessary human resources. CLADS held the Research Conference on Post-accident Waste Management Safety (RCWM2016) on 7th November, 2016 and the Technical Seminar on Safety Research for Radioactive Waste Storage on 8th November, 2016. This report compiles the abstracts and the presentation materials in the above conference and seminar. (author)

  13. The comparative analysis of 'Regulations on safety of radioactive waste management' of China and federal law 'On the management of radioactive waste' of Russian

    International Nuclear Information System (INIS)

    Yang Lili; Zhang Qiao'e; Fan Yun; Liu Ting; Gao Siqi

    2012-01-01

    In this article, the 'Regulations on safety of radioactive waste management' of China and Federal Law 'On the management of radioactive waste' of Russian were compared, from three aspects: overall legislative ideas, respective unique place and difference of common parts. Refining summed up should learn the contents of the Federal Law 'On the management of radioactive waste' of Russian, for the learning exchanges. (authors)

  14. The Net Enabled Waste Management Database as an international source of radioactive waste management information

    International Nuclear Information System (INIS)

    Csullog, G.W.; Friedrich, V.; Miaw, S.T.W.; Tonkay, D.; Petoe, A.

    2002-01-01

    The IAEA's Net Enabled Waste Management Database (NEWMDB) is an integral part of the IAEA's policies and strategy related to the collection and dissemination of information, both internal to the IAEA in support of its activities and external to the IAEA (publicly available). The paper highlights the NEWMDB's role in relation to the routine reporting of status and trends in radioactive waste management, in assessing the development and implementation of national systems for radioactive waste management, in support of a newly developed indicator of sustainable development for radioactive waste management, in support of reporting requirements for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, in support of IAEA activities related to the harmonization of waste management information at the national and international levels and in relation to the management of spent/disused sealed radioactive sources. (author)

  15. Safety measures to address the year 2000 issue at radioactive waste management facilities

    International Nuclear Information System (INIS)

    1999-03-01

    This report evaluates eventual impacts of the date problem in computer-based systems, referred to as year 2000 or Y2K problem, on the safety of radioactive waste management. It addresses the various types of waste, their processing, storage and disposal, decommissioning activities and sealed sources in terms of the approach to the Y2K problem, eventual remediation or contingencies and regulatory considerations. It assesses also typical processes involved in radioactive waste management for their potential of being affected by the Y2K problem. It addresses also eventual impacts on records and data as well as instruments and measurements

  16. Progress report on safety research of high-level waste management for the period April 1986 to March 1987

    International Nuclear Information System (INIS)

    Nakamura, Haruto; Tashiro, Shingo

    1987-08-01

    Researches on high-level waste management at the High Level Waste Management Laboratory and the Waste Safety Testing Facility Operation Division of the Japan Atomic Energy Research Institute in the fiscal year of 1986 are reviewed in the report. Topics in the three sections are as follows: 1) Non-radioactive research has been continued on Synroc irradiation and modellings of waste form leaching. 2) Research results are described in the section of Safety Evaluation for Geological Disposal on engineered barriers, field tests, safety assessment models, migration, natural analogue, seabed disposal and conceptual design of a repository. 3) Adsorption behaviour of plutonium on leach-containers and migration of leached cesium in a rock column are described in the section of Safety Examination of Vitrified Forms in the Hot Cells of WASTEF. (author)

  17. Progress report on safety research of high-level waste management for the period April, 1981 to March, 1982

    International Nuclear Information System (INIS)

    Tashiro, Shingo

    1982-10-01

    Main results obtained on Safety Research of High-Level Waste Management in 1981 were edited. The research tjeme are following. (1) Characterization of vitrified waste. (2) Alternative waste form development. (3) Durability tests for HLW storage facility. (4) Safety evaluation of geologic disposal. (5) Preparation for hot test. (author)

  18. Factors Influencing Attitude, Safety Behavior, and Knowledge regarding Household Waste Management in Guinea: A Cross-Sectional Study

    Directory of Open Access Journals (Sweden)

    Keita Mamady

    2016-01-01

    Full Text Available Waste indiscriminate disposal is recognized as an important cause of environmental pollution and is associated with health problems. Safe management and disposal of household waste are an important problem to the capital city of Guinea (Conakry. The objective of this study was to identify socioeconomic and demographic factors associated with practice, knowledge, and safety behavior of family members regarding household waste management and to produce a remedial action plan. I found that no education background, income, and female individuals were independently associated with indiscriminate waste disposal. Unplanned residential area was an additional factor associated with indiscriminate waste disposal. I also found that the community residents had poor knowledge and unsafe behavior in relation to waste management. The promotion of environmental information and public education and implementation of community action programs on disease prevention and health promotion will enhance environmental friendliness and safety of the community.

  19. Evolution of safety standards for the long-term management of nuclear waste, and their application in Ontario Power Generation

    International Nuclear Information System (INIS)

    Kempe, T.F.

    2006-01-01

    This paper examines the need to develop current radiation protection methodologies further in order to take account of the special features of long-term waste management. The need to expand the scope and nature of regulatory submissions is also addressed. It is concluded that an international consensus is emerging as to requirements for a safety case for long-term waste management, and on safety assessment approaches and criteria to be applied in the regulation of long-term waste management facilities. The application of some of this methodology in preliminary concept assessments carried out by OPG for long-term waste management facilities is described. (author)

  20. Integrating the radioactive waste management system into other management systems

    International Nuclear Information System (INIS)

    Silva, Ana Cristina Lourenco da; Nunes Neto, Carlos Antonio

    2007-01-01

    Radioactive waste management is to be included in the Integrated Management System (IMS) which pursues the continuous improvement of the company's quality, occupational safety and health, and environment protection processes. Radioactive waste management is based on the following aspects: optimization of human and material resources for execution of tasks, including the provision of a radiation protection supervisor to watch over the management of radioactive waste; improved documentation (management plan and procedures); optimization of operational levels for waste classification and release; maintenance of generation records and history through a database that facilitates traceability of information; implementation of radioactive waste segregation at source (source identification, monitoring and decontamination) activities intended to reduce the amount of radioactive waste; licensing of initial storage site for radioactive waste control and storage; employee awareness training on radioactive waste generation; identification and evaluation of emergency situations and response planning; implementation of preventive maintenance program for safety related items; development and application of new, advanced treatment methodologies or systems. These aspects are inherent in the concepts underlying quality management (establishment of administrative controls and performance indicators), environment protection (establishment of operational levels and controls for release), occupational health and safety (establishment of operational controls for exposure in emergency and routine situations and compliance with strict legal requirements and standards). It is noted that optimizing the addressed aspects of a radioactive waste management system further enhances the efficiency of the Integrated Management System for Quality, Environment, and Occupational Safety and Health. (author)

  1. Environmental Management Waste Management Facility (EMWMF) Site-Specific Health and Safety Plan, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Flynn, N.C. Bechtel Jacobs

    2008-04-21

    The Bechtel Jacobs Company LLC (BJC) policy is to provide a safe and healthy workplace for all employees and subcontractors. The implementation of this policy requires that operations of the Environmental Management Waste Management Facility (EMWMF), located one-half mile west of the U.S. Department of Energy (DOE) Y-12 National Security Complex, be guided by an overall plan and consistent proactive approach to environment, safety and health (ES&H) issues. The BJC governing document for worker safety and health, BJC/OR-1745, 'Worker Safety and Health Program', describes the key elements of the BJC Safety and Industrial Hygiene (IH) programs, which includes the requirement for development and implementation of a site-specific Health and Safety Plan (HASP) where required by regulation (refer also to BJC-EH-1012, 'Development and Approval of Safety and Health Plans'). BJC/OR-1745, 'Worker Safety and Health Program', implements the requirements for worker protection contained in Title 10 Code of Federal Regulations (CFR) Part 851. The EMWMF site-specific HASP requirements identifies safe operating procedures, work controls, personal protective equipment, roles and responsibilities, potential site hazards and control measures, site access requirements, frequency and types of monitoring, site work areas, decontamination procedures, and outlines emergency response actions. This HASP will be available on site for use by all workers, management and supervisors, oversight personnel and visitors. All EMWMF assigned personnel will be briefed on the contents of this HASP and will be required to follow the procedures and protocols as specified. The policies and procedures referenced in this HASP apply to all EMWMF operations activities. In addition the HASP establishes ES&H criteria for the day-to-day activities to prevent or minimize any adverse effect on the environment and personnel safety and health and to meet standards that define acceptable

  2. 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)

  3. International conference on the safety of radioactive waste management. Contributed papers

    International Nuclear Information System (INIS)

    2000-03-01

    This book contains 104 contributed papers submitted on issues falling within the thematic scope of the Conference. The papers present technical and regulatory approaches and practices on safety in spent nuclear fuel and radioactive waste management including storage, processing and final disposal. Each of the papers was individually indexed and provided with an abstract

  4. International conference on the safety of radioactive waste management. Contributed papers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-03-01

    This book contains 104 contributed papers submitted on issues falling within the thematic scope of the Conference. The papers present technical and regulatory approaches and practices on safety in spent nuclear fuel and radioactive waste management including storage, processing and final disposal. Each of the papers was individually indexed and provided with an abstract.

  5. Waste predisposal management

    International Nuclear Information System (INIS)

    2005-01-01

    All Member States have to a large or small extent nuclear activities that generate radioactive wastes. Hospitals, research in biomedicine or in agriculture, and some industrial applications, beside other large nuclear activities such as Nuclear Power Plants and Nuclear Research, generate unconditioned liquid or solid radioactive wastes that have to be treated, conditioned and stored prior final disposal. Countries with small nuclear activities require of organizations and infrastructure as to be able to manage, in a safe manner, the wastes that they generate. Predisposal management of radioactive waste is any step carried out to convert raw waste into a stable form suitable for the safe disposal, such as pre-treatment, treatment, storage and relevant transport. Transport of radioactive waste do not differ, in general, from other radioactive material and so are not considered within the scope of this fact sheet (Nevertheless the Agency, within the Nuclear Safety Department, has created a special Unit that might give advise Member States in this area). Predisposal management is comprised of a set of activities whose implementation may take some time. In most of the cases, safety issues and strategic and economical considerations have to be solved prior the main decisions are taken. The International Atomic Energy Agency provides assistance for the management of radioactive waste at national and operating level, in the definition and/or implementation of the projects. The services could include, but are not limited to guidance in the definition of national waste management strategy and its implementation, definition of the most adequate equipment and practices taking into account specific Member State conditions, as well as assisting in the procurement, technical expertise for the evaluation of current status of operating facilities and practical guidance for the implementation of corrective actions, assistance in the definition of waste acceptance criteria for

  6. French regulation and waste management

    International Nuclear Information System (INIS)

    1984-08-01

    The organization and the role played by French safety authorities for waste management are described. The French policy for storage and conditioning: basic objectives and waste management optimization are specified. Safety requirements are based on the barrier principle, they are mentioned for packaging and storage. The ''Institut de Protection et Surete Nucleaire'' deals not only with safety analysis but also help the ''autorites ministerielles'' for the development of fundamental safety rules. Examples for spent fuel storage and radioactive materials transport are treated in appendixes [fr

  7. The IAEA's role in safe radioactive waste management

    International Nuclear Information System (INIS)

    Flory, D.; Bruno, G.

    2011-01-01

    In accordance with its statute, IAEA is authorized to develop and maintain safety standards. This mission is reflected in the main programme of the IAEA on nuclear safety and security. In the field of the safety of radioactive waste management the IAEA is responsible for the delineation of a global safety regime to protect the public and the environment from harmful effects of ionizing radiation. This delineation is established on the basis of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, as well as on the development of safety standards for the management of all radioactive waste. The safety standards are the fruit of an international consensus on a high level of safety for the protection of people and environment. Safety guides are edited by IAEA, 7 volumes concern general safety requirements and 6 volumes deal with specific safety requirements (for instance for research reactors or for radioactive waste disposal facilities). Furthermore the IAEA assists Member States in the implementation of the safety standards and provides related services

  8. Research reactor utilization, safety, decommissioning, fuel and waste management. Posters of an international conference

    International Nuclear Information System (INIS)

    2005-01-01

    For more than 50 years research reactors have played an important role in the development of nuclear science and technology. They have made significant contributions to a large number of disciplines as well as to the educational and research programmes of about 70 countries world wide. About 675 research reactors have been built to date, of which some 278 are now operating in 59 countries (86 of them in 38 developing Member States). Altogether over 13,000 reactor-years of cumulative operational experience has been gained during this remarkable period. The objective of this conference was to foster the exchange of information on current research reactor concerns related to safety, operation, utilization, decommissioning and to provide a forum for reactor operators, designers, managers, users and regulators to share experience, exchange opinions and to discuss options and priorities. The topical areas covered were: a) Utilization, including new trends and directions for utilization of research reactors. Effective management of research reactors and associated facilities. Engineering considerations and experience related to refurbishment and modifications. Strategic planning and marketing. Classical applications (nuclear activation analysis, isotope production, neutron beam applications, industrial irradiations, medical applications). Training for operators. Educational programmes using a reactor. Current developments in design and fabrication of experimental facilities. Irradiation facilities. Projects for regional uses of facilities. Core management and calculation tools. Future trends for reactors. Use of simulators for training and educational programmes. b) Safety, including experience with the preparation and review of safety analysis reports. Human factors in safety analysis. Management of extended shutdown periods. Modifications: safety analysis, regulatory aspects, commissioning programmes. Engineering safety features. Safety culture. Safety peer reviews and

  9. Study on Safety Assessment for TINT- Pre disposal Radioactive Waste Management Facilities by the Application of SAFRAN Software

    International Nuclear Information System (INIS)

    Ya-anant, Nanthavan

    2011-06-01

    Full text: The Radioactive Waste Management Center, Thailand Institute of Nuclear Technology (TINT) provides a centralized radioactive waste management (RWM) service in the country. The pre disposal RWM facilities are composed of low and intermediate level waste treatment and storage facilities. The benefits of this study are (1) to improve the safety of pre disposal RWM facilities (2) to experience with the SAFRAN software tool for the safety assessment of pre disposal RWM facilities, which has been developed following to the methodology from International Atomic Energy Agency (IAEA). The work was performed on collecting all waste management data, the diagram of facilities, buildings, location, procedure, waste classification, waste form, radiological/chemical/physical properties including scenarios in normal and accidental conditions. The result of normal condition is that the effective dose per year of worker and public is less than 20 mSv and 1 mSv respectively. So the TINT-RWM operation is safe, as referred to the regulation

  10. Progress report on safety research of high-level waste management for the period April 1987 to March 1988

    International Nuclear Information System (INIS)

    Nakamura, Haruto; Tashiro, Shingo

    1988-10-01

    Researches on high-level waste management at the High Level Waste Management Laboratory and the Waste Safety Testing Facility Operation Division of the Japan Atomic Energy Research Institute in the fiscal year of 1987 are reviewed in the three sections of the report. The topics are as follows: 1) On performance and durability of waste forms and engineered barrier materials, accelerated alpha radiation stability of glass form and Synroc has been investigated and stress corrosion cracking of canister materials was examined under simulated conditions. 2) Sorption of 237 Np on granite samples and behavior of iron during weathering of granites were studied with respect to safety evaluation for geological disposal. 3) Actual waste was transported from the Tokai Reprocessing Plant and hot operation using the actual waste was initiated at WASTEF. (author)

  11. 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.)

  12. Norwegian national report. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management. [National report from Norway, fourth review meeting, 14-23 May 2012

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-11-15

    This report contains the national report from Norway to the fourth review meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management to be held 14 to 23 May 2012. (Author)

  13. Design of an integrated information management system for safe management of radioactive waste

    International Nuclear Information System (INIS)

    Son, Dong Chan; Hong, Suk Young; An, Kyoung Il

    2003-05-01

    An integrated data management system for the safe management of radioactive waste and spent fuel in Korea is developed to collect basic information, provide the framework for national regulation, and improve national competition and efficiency in the management of radioactive waste and spent fuel. This system can also provide public access to information such as a statistical graphs and integrated data from various waste generators to meet increased public needs and interests. Objectives can be summarized as: the five principles (independence, openness, clearance, efficiency and reliance) of safety regulation can be realized. Public understanding and reliance on the safety of spent fuel and radioactive waste management can be promoted by providing reliable information. Ensure an openness within the international nuclear community and efficiently support international agreements among contracting parties by operating safe and efficient management of spent fuel and radioactive waste (IAEA joint convention on the safety of spent fuel management and on the safety of radioactive waste management). The system can compensate for the imperfections in safe regulation of radioactive waste and spent fuel management related to waste generation, storage and disposal, and make it possible to holistic control. Re-organize the basic framework of KINS's intermediate and long term research organization and trends, regarding waste management policy is to integrate safe management and unit safe disposal

  14. Design of an integrated information management system for safe management of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Son, Dong Chan; Hong, Suk Young; An, Kyoung Il [Daesang Information Technology Co., Ltd., Seoul (Korea, Republic of)] (and others)

    2003-05-15

    An integrated data management system for the safe management of radioactive waste and spent fuel in Korea is developed to collect basic information, provide the framework for national regulation, and improve national competition and efficiency in the management of radioactive waste and spent fuel. This system can also provide public access to information such as a statistical graphs and integrated data from various waste generators to meet increased public needs and interests. Objectives can be summarized as: the five principles (independence, openness, clearance, efficiency and reliance) of safety regulation can be realized. Public understanding and reliance on the safety of spent fuel and radioactive waste management can be promoted by providing reliable information. Ensure an openness within the international nuclear community and efficiently support international agreements among contracting parties by operating safe and efficient management of spent fuel and radioactive waste (IAEA joint convention on the safety of spent fuel management and on the safety of radioactive waste management). The system can compensate for the imperfections in safe regulation of radioactive waste and spent fuel management related to waste generation, storage and disposal, and make it possible to holistic control. Re-organize the basic framework of KINS's intermediate and long term research organization and trends, regarding waste management policy is to integrate safe management and unit safe disposal.

  15. Safety Aspects of Radioactive Waste Management in Different Nuclear Fuel Cycle Policies, a Comparative Study

    International Nuclear Information System (INIS)

    Gad Allah, A.A.

    2009-01-01

    With the increasing demand of energy worldwide, and due to the depletion of conventional natural energy resources, energy policies in many countries have been devoted to nuclear energy option. On the other hand, adopting a safe and reliable nuclear fuel cycle concept guarantees future nuclear energy sustain ability is a vital request from environmental and economic point of views. The safety aspects of radioactive waste management in the nuclear fuel cycle is a topic of great importance relevant to public acceptance of nuclear energy and the development of nuclear technology. As a part of nuclear fuel cycle safety evaluation studies in the department of nuclear fuel cycle safety, National Center for Nuclear Safety and Radiation Control (NCNSRC), this study evaluates the radioactive waste management policies and radiological safety aspects of three different nuclear fuel cycle policies. The once-through fuel cycle (OT- fuel cycle) or the direct spent fuel disposal concept for both pressurized light water reactor ( PWR) and pressurized heavy water reactor (PHWR or CANDU) systems and the s elf-generated o r recycling fuel cycle concept in PWR have been considered in the assessment. The environmental radiological safety aspects of different nuclear fuel cycle options have been evaluated and discussed throughout the estimation of radioactive waste generated from spent fuel from these fuel cycle options. The decay heat stored in the spent fuel was estimated and a comparative safety study between the three fuel cycle policies has been implemented

  16. Preliminary safety analysis report for the Waste Characterization Facility

    International Nuclear Information System (INIS)

    1994-10-01

    This safety analysis report outlines the safety concerns associated with the Waste Characterization Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are to: define and document a safety basis for the Waste Characterization Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume. 142 refs., 38 figs., 39 tabs

  17. ILK statement about the proposed EU directives on nuclear safety and the management of radioactive waste

    International Nuclear Information System (INIS)

    2003-01-01

    In November 2002, the European Commission proposed a package of measures for a community concept of the EU on nuclear safety. It includes a proposed directive on the safety of nuclear installations during operating and decommissioning, and a proposed directive on the management of radioactive waste. In the opinion of the International Nuclear Committee (ILK), the competences and obligations of the member states and their safety authorities must be preserved in the future. Primary responsibility for plant safety rests with the operator. This objective is served by transparent, harmonized EU-wide safety standards. New standards and definitions are not generally required. Harmonized safety standards to be developed should initially be limited to nuclear power plants because of the fundamental differences in design of nuclear facilities. The Commission should obtain the technical competence required to perform the duties arising from the application of the proposed directive. Formal inspections by the Commission of the national regulatory authorities are not necessary. Instead, a peer review process will be the better solution. A reporting system at three-year intervals is generally regarded as the most effective approach. The ILK considers the tight schedule for final storage, especially of high-level waste, problematic. Joint repository projects, also for countries with low waste arisings, are suitable approaches. The envisaged reports about the state of radioactive waste management should be integrated into the reporting systems under other international agreements. The Commission's intention to intensify cooperation in the field of research is welcomed. (orig.) [de

  18. Waste management in NUCEF

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Y.; Maeda, A.; Sugikawa, S.; Takeshita, I. [Japan Atomic Energy Research Institute, Dept. of Safety Research Technical Support, Tokai-Mura, Naka-Gun, Ibaraki-Ken (Japan)

    2000-07-01

    In the NUCEF, the researches on criticality safety have been performed at two critical experiment facilities, STACY and TRACY in addition to the researches on fuel cycle such as advanced reprocessing and partitioning in alpha-gamma concrete cells and glove boxes. Many kinds of radioactive wastes have been generated through the research activities. Furthermore, the waste treatment itself may produce some secondary wastes. In addition, the separation and purification of plutonium of several tens-kg from MOX powder are scheduled in order to supply plutonium nitrate solution fuel for critical experiments at STACY. A large amount of wastes containing plutonium and americium will be generated from the plutonium fuel treatment. From the viewpoint of safety, the proper waste management is one of important works in NUCEF. Many efforts, therefore, have been made for the development of advanced waste treatment techniques to improve the waste management in NUCEF. Especially the reduction of alpha-contaminated wastes is a major interest. For example, the separation of americium is planned from the liquid waste evolved alter plutonium purification by application of tannin gel as an adsorbent of actinide elements. The waste management and the relating technological development in NUCEF are briefly described in this paper. (authors)

  19. Waste management in NUCEF

    International Nuclear Information System (INIS)

    Suzuki, Y.; Maeda, A.; Sugikawa, S.; Takeshita, I.

    2000-01-01

    In the NUCEF, the researches on criticality safety have been performed at two critical experiment facilities, STACY and TRACY in addition to the researches on fuel cycle such as advanced reprocessing and partitioning in alpha-gamma concrete cells and glove boxes. Many kinds of radioactive wastes have been generated through the research activities. Furthermore, the waste treatment itself may produce some secondary wastes. In addition, the separation and purification of plutonium of several tens-kg from MOX powder are scheduled in order to supply plutonium nitrate solution fuel for critical experiments at STACY. A large amount of wastes containing plutonium and americium will be generated from the plutonium fuel treatment. From the viewpoint of safety, the proper waste management is one of important works in NUCEF. Many efforts, therefore, have been made for the development of advanced waste treatment techniques to improve the waste management in NUCEF. Especially the reduction of alpha-contaminated wastes is a major interest. For example, the separation of americium is planned from the liquid waste evolved alter plutonium purification by application of tannin gel as an adsorbent of actinide elements. The waste management and the relating technological development in NUCEF are briefly described in this paper. (authors)

  20. The announcement of the Ministry of Foreign Affairs of the Slovak Republic about Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management

    International Nuclear Information System (INIS)

    2002-01-01

    The Ministry of Foreign Affairs of the Slovak Republic amends that in 30 September 1997 in Vienna was undersigned the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. This Joint Convention came into force on June 18, 2001

  1. Prospects of nuclear waste management and radioactive waste management

    International Nuclear Information System (INIS)

    Koprda, V.

    2015-01-01

    The policy of radioactive waste management in the Slovak Republic is based on the principles defined by law on the National Nuclear Fund (NJF) and sets basic objectives: 1 Safe and reliable nuclear decommissioning; 2 The minimization of radioactive waste; 3. Selection of a suitable fuel cycle; 4 Safe storage of radioactive waste (RAW) 5 Security chain management of radioactive waste and spent nuclear fuel (SNF); 6 Nuclear safety; 7 The application of a graduated approach; 8 Respect of the principle 'a polluter pays'; 9 Objective decision-making process; 10 Responsibility. In connection with the above objectives, it appears necessary to build required facilities that are listed in this article.

  2. Existing and future international standards for the safety of radioactive waste disposal

    International Nuclear Information System (INIS)

    Linsley, G.

    1999-01-01

    In this paper the essential features of the current international safety standards are summarised and the issues being raised for inclusion in future standards are discussed. The safety standards of the IAEA are used as the basis for the review and discussion. The IAEA has established a process for establishing international standards of safety for radioactive waste management through its Radioactive Waste Safety Standards (RADWASS) programme. The RADWASS documents are approved by a comprehensive process involving regulatory and other experts from all concerned IAEA Member States. A system of committees for approving the IAEAs safety standards has been established. For radioactive waste safety the committee for review and approval is the Waste Safety Standards Advisory Committee (WASSAC). In 1995 the IAEA published 'The Principles of Radioactive Waste Management' as the top level document in the RADWASS programme. The report sets out the basis principles which most experts believe are fundamental to the safe management of radioactive wastes

  3. 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)

  4. Law on the management of radioactive waste

    International Nuclear Information System (INIS)

    1999-01-01

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

  5. Safety analysis report for the Waste Storage Facility. Revision 2

    Energy Technology Data Exchange (ETDEWEB)

    Bengston, S.J.

    1994-05-01

    This safety analysis report outlines the safety concerns associated with the Waste Storage Facility located in the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The three main objectives of the report are: define and document a safety basis for the Waste Storage Facility activities; demonstrate how the activities will be carried out to adequately protect the workers, public, and environment; and provide a basis for review and acceptance of the identified risk that the managers, operators, and owners will assume.

  6. Radioactive waste management: the contribution of expert assessments to the implementation of safe management channels

    International Nuclear Information System (INIS)

    Besnus, F.; Jouve, A.C.

    2011-01-01

    The national Radioactive Materials and Waste Management (PNGMDR) sets objectives and defines waste management channels for all radioactive wastes produced in France. Within this framework, IRSN (Institute for Radioprotection and Nuclear Safety) expertise aims at assessing the consistency and robustness of the technical solutions set in place by the plan. As a result of this assessment, the main safety issues and priorities for upgrading the safety of the various facilities that will receive and treat waste are identified on the one hand, while possible foreseen weaknesses in terms of storage or treatment capacities are put into light on the other hand. To carry out such assessment, IRSN backs on its 'in depth' knowledge of facilities, acquired through the examination of each major step of waste management facility life (creation, commissioning, re-examination of safety...). This knowledge feeds in turn the examination of the waste management strategies implemented by operators. In addition, special attention is given to the achievement of waste packages of favourable properties as well as to the conditions for their safe disposal, since these two aspects are most often key factors for optimizing the safety of the whole management channel. By its capacity to overlook all steps of waste management channels, from production to final disposal, IRSN intends to contribute to the objective of enhancing the global safety of the management of radioactive waste. (authors)

  7. Safety evaluation report of the Waste Isolation Pilot Plant safety analysis report: Contact-handled transuranic waste disposal operations

    International Nuclear Information System (INIS)

    1997-02-01

    DOE 5480.23, Nuclear Safety Analysis Reports, requires that the US Department of Energy conduct an independent, defensible, review in order to approve a Safety Analysis Report (SAR). That review and the SAR approval basis is documented in this formal Safety Evaluation Report (SER). This SER documents the DOE's review of the Waste Isolation Pilot Plant SAR and provides the Carlsbad Area Office Manager, the WIPP SAR approval authority, with the basis for approving the safety document. It concludes that the safety basis documented in the WIPP SAR is comprehensive, correct, and commensurate with hazards associated with planned waste disposal operations

  8. The fourth country report on agreement of safety supervision on radiation waste and management of spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-10-15

    This report covered the agreement of safety supervision on radiation waste and management of spent fuel. It listed the stipulation, the common law, the coverage and the amount of stock on spent fuel. Also, it indicated law and regulations and restriction on the related the agency, general safety regulations, policy on guarantee of quality, emergency method, dismantling, management of safety control on spent fuel including a process of establishment and safety requirements, regulations of conveyance between countries and improvement of safety of spent fuel.

  9. Environmental restoration and waste management

    International Nuclear Information System (INIS)

    Middleman, L.I.

    1989-01-01

    The purpose of this Five-Year Plan is to establish an agenda for compliance and cleanup against which progress will be measured. DOE is committed to an open and participatory process for developing a national priority system for expenditure of funds. This system will be based on scientific principles and risk reduction in terms that are understandable to the public. The Plan will be revised annually, with a five-year planning horizon. For FY 1991--1995, this Plan encompasses total program activities and costs for DOE Corrective Activities, Environmental Restoration, Waste Management Operations, and Applied R ampersand D. It addresses hazardous wastes, radioactive wastes, mixed wastes (radioactive and hazardous), and sanitary wastes. It also addresses facilities and sites contaminated with or used in the management of those wastes. The Plan does not include the Safety and Health Program (Office of the Assistant Secretary for Environment, Safety, and Health) or programs of the Office of Civilian Radioactive Waste Management. It does include the annual Defense Programs contribution to the Nuclear Waste Fund for disposal of defense high-level waste and research toward characterizing the defense waste form for repository disposal

  10. 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)

  11. Safe waste management practices in beryllium facilities

    International Nuclear Information System (INIS)

    Bhat, P.N.; Soundararajan, S.; Sharma, D.N.

    2012-01-01

    Beryllium, an element with the atomic symbol Be, atomic number 4, has very high stiffness to weight ratio and low density. It has good electrical conductive properties with low coefficient of thermal expansion. These properties make the metal beryllium very useful in varied technological endeavours, However, beryllium is recognised as one of the most toxic metals. Revelation of toxic effects of beryllium resulted in institution of stringent health and safety practices in beryllium handling facilities. The waste generated in such facilities may contain traces of beryllium. Any such waste should be treated as toxic waste and suitable safe waste management practices should be adopted. By instituting appropriate waste management practice and through a meticulously incorporated safety measures and continuous surveillance exercised in such facilities, total safety can be ensured. This paper broadly discusses health hazards posed by beryllium and safe methods of management of beryllium bearing wastes. (author)

  12. Healthcare waste management practices and safety indicators in Nigeria.

    Science.gov (United States)

    Oyekale, Abayomi Samuel; Oyekale, Tolulope Olayemi

    2017-09-25

    risky/safe medical waste disposal (p management. It was recommended that possession of HCW management guidelines, staff training on HCW disposal and provision of requisite equipment for proper treatment of HCW would promote environmental safety in HCW disposal.

  13. Healthcare waste management practices and safety indicators in Nigeria

    Directory of Open Access Journals (Sweden)

    Abayomi Samuel Oyekale

    2017-09-01

    rural areas significantly influenced indices of risky/safe medical waste disposal (p < 0.05. Conclusion The study concluded that there was low compliance with standard HCW management. It was recommended that possession of HCW management guidelines, staff training on HCW disposal and provision of requisite equipment for proper treatment of HCW would promote environmental safety in HCW disposal.

  14. Quality assurance for safety in the radioactive waste management: a quality assurance system in Novi Han radioactive waste repository

    International Nuclear Information System (INIS)

    Petrova, A.; Kolev, I.

    2000-01-01

    Novi Han Radioactive Waste Repository (RWR) is still the only place in Bulgaria for storage of low and intermediate level radioactive waste. It is necessary to establish and maintain a Quality Assurance (QA) system to ensure that the RWR can be operated safely with regard to the health and safety of the general public and site personnel. A QA system has to establish the basic requirements for quality assurance in order to enhance nuclear safety by continuously improving the methods employed to achieve quality. It is envisaged that the QA system for the Novi Han RWR will cover the operation and maintenance of the radioactive waste disposal facilities, the radiation protection and monitoring of the site, as well as the scientific and technology development aspects. The functions of the Novi Han RWR presume the availability of an environmental management system. It is appropriate to establish a QA system based on the requirements of the ISO Standards 9001 and 14000, using the recommendations of the IAEA (Quality assurance for safety in NPPs and other nuclear installations, code and safety guides Q1-Q14). (authors)

  15. Safety assurance in radioactive waste management at nuclear power plants of the Northwest region of Russia

    Energy Technology Data Exchange (ETDEWEB)

    Safonov, Igor

    1999-07-01

    This presentation describes the two large operating nuclear power plants (NPP) in Northwest Russia, the Kola NPP and the Leningrad NPP. The four units at Kola are tank-type pressurised water reactors of 440 MW (electric) while the four Leningrad reactors are 1000 MW (electric) of RBMK type. Gosatomnadzor of Russia regularly conducts so-called target inspections on safety assurance for radioactive waste management at NNP. Among the many items checked during such inspections are the existence and realisation of an action plan for waste reduction, the technical state of equipment and the compliance with previous directions. The management of liquid, solid and gaseous radioactive wastes is described in some detail, and so are the violations revealed at both sites. There is also some discussion of modernisation plans for waste management. It is stated that the ecological impact of the plants is negligible and there is no hazard to people or environment. The presentation concludes with some suggestions for improving the licensing requirements for waste management.

  16. Safety assurance in radioactive waste management at nuclear power plants of the Northwest region of Russia

    International Nuclear Information System (INIS)

    Safonov, Igor

    1999-01-01

    This presentation describes the two large operating nuclear power plants (NPP) in Northwest Russia, the Kola NPP and the Leningrad NPP. The four units at Kola are tank-type pressurised water reactors of 440 MW (electric) while the four Leningrad reactors are 1000 MW (electric) of RBMK type. Gosatomnadzor of Russia regularly conducts so-called target inspections on safety assurance for radioactive waste management at NNP. Among the many items checked during such inspections are the existence and realisation of an action plan for waste reduction, the technical state of equipment and the compliance with previous directions. The management of liquid, solid and gaseous radioactive wastes is described in some detail, and so are the violations revealed at both sites. There is also some discussion of modernisation plans for waste management. It is stated that the ecological impact of the plants is negligible and there is no hazard to people or environment. The presentation concludes with some suggestions for improving the licensing requirements for waste management

  17. The evolution and future direction of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management

    International Nuclear Information System (INIS)

    Siraky, Gabriela

    2008-01-01

    Full text: The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, namely the Joint Convention, had been established in 1997. The objective of the Convention is to achieve and maintain a high level of safety worldwide in that fields to ensure that there are effective defenses against potential hazards so that individuals, society and the environment are protected from the harmful effects of ionizing radiation and to prevent accidents with radiological consequences and to mitigate their consequences. The Parties to the Convention intend to achieve this objective by international cooperation, peer reviews of each other's performance, assistance when needed for states with less developed programmes and capabilities and the use of internationally accepted standards of safety. The Joint Convention is rooted in the discussions held previously to the establishment of the Convention of the Nuclear Safety that had taken place in the period 1993-1994. The idea of a Convention on the Safety of waste management evolved since then, getting its final status in November 1997 after seven meetings of a specially appointed working group of outstanding specialists on the subject. After that, it was needed three years more until the number of the ratifying States, that then became Contracting Parties, to get the condition that let the Convention to enter into force: ninety days after the date of deposit with the Depository of the twenty-fifth instrument of ratification, acceptance or approval, including the instruments of fifteen States having an operational nuclear power plant. The First Review Meeting was held three years after it entered into force, in November 2003, with the attendance of 33 Parties that presented their National Reports. The second review meeting was held in May 2006. Forty-one Contracting Parties participated in the Second Review Meeting. There is then, a constant evolution in the number of Contracting Parties

  18. Central waste complex interim safety basis

    International Nuclear Information System (INIS)

    Cain, F.G.

    1995-01-01

    This interim safety basis provides the necessary information to conclude that hazards at the Central Waste Complex are controlled and that current and planned activities at the CWC can be conducted safely. CWC is a multi-facility complex within the Solid Waste Management Complex that receives and stores most of the solid wastes generated and received at the Hanford Site. The solid wastes that will be handled at CWC include both currently stored and newly generated low-level waste, low-level mixed waste, contact-handled transuranic, and contact-handled TRU mixed waste

  19. National report of the Slovak Republic. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. 2005

    International Nuclear Information System (INIS)

    Hekel, P.; Ivan, J.; Lukacovic, K.; Parimucha, F.; Suss, J; Tomek, J.; Jurina, V.; Kobzova, D.; Konecny, L.; Homola, J.; Zavazanova, A.; Metke, E.; Turner, M.; Vaclav, J.; Ziakova, M.; Pospisil, M.; Petrik, T.

    2005-09-01

    The National Report (Compiled in terms of the Joint Convention - September 2005) contains information how each of the obligations of the Joint Convention have been implemented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) and other Slovak organisations are presented. These activities are reported under the headings: (A) Introduction; (B) Spent fuel and radioactive waste management; C) Scope of application; (D) Inventories and lists; (E) Legislation and regulation; (F) Other general safety provisions; (G) Safety of spent fuel management; (H) Safety of RAW management; (I) Transboundary movement of SF and RAW; (J) Disused sealed sources; (K) planned activiries to improve safety; (L) Annexes

  20. The International Atomic Energy Agency (IAEA) standards and recommendations on radioactive waste and transport safety

    International Nuclear Information System (INIS)

    Warnecke, E.; Rawl, R.

    1996-01-01

    The International Atomic Energy Agency (IAEA) publishes standards and recommendations on all aspects of nuclear safety in its Safety Series, which includes radioactive waste management and transport of radioactive materials. Safety Series documents may be adopted by a State into its national legal framework. Most of the States used the IAEA transport regulations (Safety Series No. 6) as a basis for their national regulation. The two highest ranking documents of the Radioactive Waste Safety Standards (RADWASS) programme, the Safety Fundamentals and the Safety Standard on the national waste management system, have been published. Both provide impetus into the waste management safety convention, a legally binding document for signatory states, which is being drafted. The already existing Convention on Nuclear Safety covers the management of radioactive waste at land-based civil nuclear power plants. (author) 1 fig., 18 refs

  1. Waste classification: a management approach

    International Nuclear Information System (INIS)

    Wickham, L.E.

    1984-01-01

    A waste classification system designed to quantify the total hazard of a waste has been developed by the Low-Level Waste Management Program. As originally conceived, the system was designed to deal with mixed radioactive waste. The methodology has been developed and successfully applied to radiological and chemical wastes, both individually and mixed together. Management options to help evaluate the financial and safety trade-offs between waste segregation, waste treatment, container types, and site factors are described. Using the system provides a very simple and cost effective way of making quick assessments of a site's capabilities to contain waste materials. 3 references

  2. Development and design of an integrated information management system for safe management of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Son, Dong Chan; Hong, Suk Young; An, Kyoung Il [Daesang Information Technology Co., Ltd., Seoul (Korea, Republic of)

    2004-05-15

    An integrated data management system for the safe management of radioactive waste and spent fuel in Korea is developed to collect basic information, provide the framework for national regulation, and improve national competition and efficiency in the management of radioactive waste and spent fuel. This system can also provide public access to information such as a statistical graphs and integrated data from various waste generators to meet increased public needs and interests. Objectives can be summarized as; the five principles (independence, openness, clearance, efficiency and reliance) of safety regulation can be realized. Public understanding and reliance on the safety of spent fuel and radioactive waste management can be promoted by providing reliable information. Ensure an openness within the international nuclear community and efficiently support international agreements among contracting parties by operating safe and efficient management of spent fuel and radioactive waste (IAEA joint convention on the safety of spent fuel management and on the safety of radioactive waste management). The system can compensate for the imperfections In safe regulation of radioactive waste and spent fuel management related to waste generation, storage and disposal, and make it possible to holistic control. Re-organize the basic framework of KINS's intermediate and long term research organization and trends, regarding waste management policy is to integrate safe management and unit safe disposal.

  3. Development and design of an integrated information management system for safe management of radioactive waste

    International Nuclear Information System (INIS)

    Son, Dong Chan; Hong, Suk Young; An, Kyoung Il

    2004-05-01

    An integrated data management system for the safe management of radioactive waste and spent fuel in Korea is developed to collect basic information, provide the framework for national regulation, and improve national competition and efficiency in the management of radioactive waste and spent fuel. This system can also provide public access to information such as a statistical graphs and integrated data from various waste generators to meet increased public needs and interests. Objectives can be summarized as; the five principles (independence, openness, clearance, efficiency and reliance) of safety regulation can be realized. Public understanding and reliance on the safety of spent fuel and radioactive waste management can be promoted by providing reliable information. Ensure an openness within the international nuclear community and efficiently support international agreements among contracting parties by operating safe and efficient management of spent fuel and radioactive waste (IAEA joint convention on the safety of spent fuel management and on the safety of radioactive waste management). The system can compensate for the imperfections In safe regulation of radioactive waste and spent fuel management related to waste generation, storage and disposal, and make it possible to holistic control. Re-organize the basic framework of KINS's intermediate and long term research organization and trends, regarding waste management policy is to integrate safe management and unit safe disposal

  4. Radioactive Waste Management Program Activities in Croatia

    International Nuclear Information System (INIS)

    Matanic, R.

    2000-01-01

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

  5. National report of the Slovak Republic compiled in terms of the Join on the safety of spent fuel management and on the safety of radwaste management

    International Nuclear Information System (INIS)

    Jurina, V.; Viktory, D.; Petrik, T.; Sovcik, J.; Suess, J.; Tomek, J.; Lukacovic, J.; Ivan, J.; Ziakova, M.; Metke, E.; Pospisil, M.; Turner, M.; Homola, J.; Vaclav, J.; Bystricka, S.; Barbaric, M.; Horvath, J.; Betak, J.; Mihaly, B.; Adamovsky, V.; Baloghova, A.; Orihel, M.; Vasina, D.; Balaz, J.; Misovicova, D.; Vrtoch, M.; Mlcuch, J.; Granak, P.; Meleg, J.; Bardy, M.; Gogoliak, J.

    2011-08-01

    The National safety report of the Slovak Republic on the safety of spent fuel management and on the safety of radwaste management in 2011 is presented. These activities in the safety of spent fuel management and radioactive waste management in the Slovak Republic are reported under the headings: (A) Introduction; B) Concept for spent nuclear fuel management (SNF) and radwaste management (RAW); (C) Scope of application of the convention; (D) Spent fuel management and radioactive waste (RAW) management facilities; (E) Legislation and regulation; (F) General safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste (RAW) management; (I) Transboundary movement of spent nuclear fuel and radioactive waste; (J) Disused sealed sources; (K) Planned measures to improve safety; (L) Communication with the public; (M) Annexes. Annexes consists of following parts: I. List of nuclear facilities for spent fuel and RAW management. II. Limits of radioactive material discharges into atmosphere and hydrosphere. III. List of nuclear installations in decommissioning. IV. Inventory of stored spent nuclear fuel. V. Inventory of stored RAW. VI. List of national laws, decrees and guidelines. VII. List of international expert reports (including safety reports). VIII. List of authors.

  6. Radioactive waste engineering and management

    CERN Document Server

    Nakayama, Shinichi

    2015-01-01

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

  7. Nuclear safety requirements for upgrading the National Repository for Radioactive Wastes-Baita Bihor

    International Nuclear Information System (INIS)

    Vladescu, Gabriela; Necula, Daniela

    2000-01-01

    The upgrading project of National Repository for Radioactive Wastes-Baita Bihor is based on the integrated concept of nuclear safety. Its ingredients are the following: A. The principles of nuclear safety regarding the management of radioactive wastes and radioprotection; B. Safety objectives for final disposal of low- and intermediate-level radioactive wastes; C. Safety criteria for final disposal of low- and intermediate-level radioactive wastes; D. Assessment of safety criteria fulfillment for final disposal of low- and intermediate-level radioactive wastes. Concerning the nuclear safety in radioactive waste management the following issues are considered: population health protection, preventing transfrontier contamination, future generation radiation protection, national legislation, control of radioactive waste production, interplay between radioactive waste production and management, radioactive waste repository safety. The safety criteria of final disposal of low- and intermediate-level radioactive wastes are discussed by taking into account the geological and hydrogeological configuration, the physico-chemical and geochemical characteristics, the tectonics and seismicity conditions, extreme climatic potential events at the mine location. Concerning the requirements upon the repository, the following aspects are analyzed: the impact on environment, the safety system reliability, the criticality control, the filling composition to prevent radioactive leakage, the repository final sealing, the surveillance. Concerning the radioactive waste, specific criteria taken into account are the radionuclide content, the chemical composition and stability, waste material endurance to heat and radiation. The waste packaging criteria discussed are the mechanical endurance, materials toughness and types as related to deterioration caused by handling, transportation, storing or accidents. Fulfillment of safety criteria is assessed by scenarios analyses and analyses of

  8. National report of the Slovak Republic compiled in terms of the join convention on the safety of spent fuel management and on the safety of radwaste management

    International Nuclear Information System (INIS)

    Jurina, V.; Viktory, D.; Petrik, T.; Sovcik, J.; Suess, J.; Tomek, J.; Lukacovic, J.; Ivan, J.; Ziakova, M.; Metke, E.; Pospisil, M.; Turner, M.; Homola, J.; Vaclav, J.; Bystricka, S.; Barbaric, M.; Horvath, J.; Betak, J.; Mihaly, B.; Adamovsky, V.; Baloghova, A.; Orihel, M.; Vasina, D.; Balaz, J.; Misovicova, D.; Vrtoch, M.; Mlcuch, J.; Granak, P.; Meleg, J.; Bardy, M.; Gogoliak, J.

    2011-08-01

    The National safety report of the Slovak Republic on the safety of spent fuel management and on the safety of radwaste management in 2011 is presented. These activities in the safety of spent fuel management and radioactive waste management in the Slovak Republic are reported under the headings: (A) Introduction; B) Concept for spent nuclear fuel management (SNF) and radwaste management (RAW); (C) Scope of application of the convention; (D) Spent fuel management and radioactive waste (RAW) management facilities; (E) Legislation and regulation; (F) General safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste (RAW) management; (I) Transboundary movement of spent nuclear fuel and radioactive waste; (J) Disused sealed sources; (K) Planned measures to improve safety; (L) Communication with the public; (M) Annexes. Annexes consists of following parts: I. List of nuclear facilities for spent fuel and RAW management. II. Limits of radioactive material discharges into atmosphere and hydrosphere. III. List of nuclear installations in decommissioning. IV. Inventory of stored spent nuclear fuel. V. Inventory of stored RAW. VI. List of national laws, decrees and guidelines. VII. List of international expert reports (including safety reports). VIII. List of authors.

  9. Progress report on safety research of high-level waste management for the period April, 1982 to March, 1983

    International Nuclear Information System (INIS)

    Nakamura, Haruto; Tashiro, Shingo

    1983-06-01

    Main results obtained on Safety Research of High-Level waste Management in 1982 were editted. 1) The leaching mechanisms of the vitrified waste were studied to estimate the leach rate in disposal condition. 2) For the safety assessment of storage and disposal of the returning waste resulted from overseas reprocessing, properties of the glass simulating the composition by COGEMA are being measured. 3) In order to assess the integrity of the repository, influence of heat on the characteristics of rock mass and buffer materials was studied in underground drift. And also the retardation mechanism of the leached elements by rock mass was discussed. 4) The construction of Waste Safety Testing Facility (WASTEF) was completed, and vitrification test and near-field test using large radiation sources were initiated. (author)

  10. 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)

  11. Safety Assessment Approach for Decision Making Related to Remedial Measures and Radioactive Waste Management

    International Nuclear Information System (INIS)

    Rybalka, Nataliia; Kondratyev, Sergiy; Alekseeva, Zoya

    2016-01-01

    Conclusions: At each particular case of “legacy” radioactive waste management facilities the optimized remedial measures should be justified taken into account: • results of facility investigations; • site status and characteristics; • safety assessment; • economical reasons; • societal factors; • timeframes; • available technologies and techniques

  12. Discussions about safety criteria and guidelines for radioactive waste management.

    Science.gov (United States)

    Yamamoto, Masafumi

    2011-07-01

    In Japan, the clearance levels for uranium-bearing waste have been established by the Nuclear Safety Commission (NSC). The criteria for uranium-bearing waste disposal are also necessary; however, the NSC has not concluded the discussion on this subject. Meanwhile, the General Administrative Group of the Radiation Council has concluded the revision of its former recommendation 'Regulatory exemption dose for radioactive solid waste disposal', the dose criteria after the institutional control period for a repository. The Standardization Committee on Radiation Protection in the Japan Health Physics Society (The Committee) also has developed the relevant safety criteria and guidelines for existing exposure situations, which are potentially applicable to uranium-bearing waste disposal. A new working group established by The Committee was initially aimed at developing criteria and guidelines specifically for uranium-bearing waste disposal; however, the aim has been shifted to broader criteria applicable to any radioactive wastes.

  13. 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

  14. Nuclear and radiological safety nuclear power nuclear fuel cycle and waste management

    International Nuclear Information System (INIS)

    1997-05-01

    This catalogue lists all sales publications of the International Atomic Energy Agency dealing with Nuclear and Radiological Safety, Nuclear Power and Nuclear Fuel Cycle and Waste Management and issued during the period of 1995-1996. Most publications are in English. Proceedings of conferences, symposia and panels of experts may contain some papers in languages other than English (Arabic, Chinese, French, Russian or Spanish), but all these papers have abstracts in English

  15. Establishment of database system for management of KAERI wastes

    International Nuclear Information System (INIS)

    Shon, J. S.; Kim, K. J.; Ahn, S. J.

    2004-07-01

    Radioactive wastes generated by KAERI has various types, nuclides and characteristics. To manage and control these kinds of radioactive wastes, it comes to need systematic management of their records, efficient research and quick statistics. Getting information about radioactive waste generated and stored by KAERI is the basic factor to construct the rapid information system for national cooperation management of radioactive waste. In this study, Radioactive Waste Management Integration System (RAWMIS) was developed. It is is aimed at management of record of radioactive wastes, uplifting the efficiency of management and support WACID(Waste Comprehensive Integration Database System) which is a national radioactive waste integrated safety management system of Korea. The major information of RAWMIS supported by user's requirements is generation, gathering, transfer, treatment, and storage information for solid waste, liquid waste, gas waste and waste related to spent fuel. RAWMIS is composed of database, software (interface between user and database), and software for a manager and it was designed with Client/Server structure. RAWMIS will be a useful tool to analyze radioactive waste management and radiation safety management. Also, this system is developed to share information with associated companies. Moreover, it can be expected to support the technology of research and development for radioactive waste treatment

  16. Progress report on safety research on radioactive waste management for the period April 1995 to March 1996

    International Nuclear Information System (INIS)

    Sekine, Keiichi; Muraoka, Susumu; Banba, Tsunetaka

    1997-03-01

    This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Natural Barrier Laboratory and Environmental Geochemistry Laboratory of the Department of Environmental Safety Research during the fiscal year of 1995 (April 1, 1995 - March 31, 1996). The topics are as follows: 1) As for waste forms and engineered barrier material, performance assessment studies were carried out on various waste forms. 2) In the safety evaluation study for shallow land disposal, migration behavior of radionuclides in a soil layer was studied. 3) In the safety evaluation study for geological disposal, chemical behavior of radionuclides in water, nuclide migration in geosphere and groundwater flow system were studied. Migration of uranium series nuclides in uranium ore deposit was studied as a part of natural analog study. (author)

  17. Multi-criteria analysis for evaluating the radiological and ecological safety measures in radioactive waste management

    International Nuclear Information System (INIS)

    Sazykina, T.G.; Kryshev, I.I.

    2006-01-01

    A methodological approach is presented for multicriterial evaluating the effectiveness of radiation ecological safety measures during radioactive waste management. The approach is based on multicriterial analysis with consideration of radiological, ecological, social, economical consequences of various safety measures. The application of the multicriterial approach is demonstrated taking as an example of decision-making on the most effective actions for rehabilitation of a water subject, contaminated with radionuclides [ru

  18. 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

  19. On safety of radioactive waste carrier

    International Nuclear Information System (INIS)

    Kondo, Toshikazu

    1995-01-01

    The waste generated by reprocessing the spent fuel from Japanese nuclear power stations in France and U.K. is to be returned to Japan. The first return transport was carried out from February to April when the waste management facility in Rokkasho, Aomori Prefecture, was completed. Most of this return transport was the sea transport using the exclusively used carrier, Pacific Pintail, from Cherbourg, France, to Mutsu Ogawara, Japan. Ministry of Transport carried out the examination on the safety of this method of transport including the safety of the carrier based on the rule for the sea transport and storage of dangerous substances. The international rule on the sea transport of high level radioactive waste, the course of adopting the INF code and its outline, and the Japanese safety standard for the carriers exclusively used for high level radioactive waste are explained. The Pacific Pintail is the ship of 5087 GT, which was built in 1987 as the carrier exclusively used for radioactive substances, owned by Pacific Nuclear Transport Ltd. of U.K. The main features related to the safety of the Pacific Pintail are explained, and the sufficient countermeasures are taken. (K.I.)

  20. Progress report on safety research on radioactive waste management for the period April 1993 to March 1995

    Energy Technology Data Exchange (ETDEWEB)

    Sekine, Keiichi; Muraoka, Susumu; Banba, Tsunetaka [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [eds.

    1996-03-01

    This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Natural Barrier Laboratory and Environmental Geochemistry Laboratory of the Department of Environmental Safety Research during the fiscal years of 1993 and 1994 (April 1, 1993 - March 31, 1995). The topics are as follows: (1) As for waste forms and engineered barrier material, performance assessment studies were carried out on various waste forms, buffer materials and mortar. (2) In the safety evaluation study for shallow land disposal, migration behaviour of nuclides in the soil layer was studied. (3) In the safety evaluation study for geological disposal, chemical behaviour of radionuclides in water, nuclide migration in geosphere and groundwater flow system were studied. Migration of uranium series nuclides in uranium ore deposit was studied as a part of natural analogue study. (author).

  1. Progress report on safety research on radioactive waste management for the period April 1993 to March 1995

    International Nuclear Information System (INIS)

    Sekine, Keiichi; Muraoka, Susumu; Banba, Tsunetaka

    1996-03-01

    This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Natural Barrier Laboratory and Environmental Geochemistry Laboratory of the Department of Environmental Safety Research during the fiscal years of 1993 and 1994 (April 1, 1993 - March 31, 1995). The topics are as follows: 1) As for waste forms and engineered barrier material, performance assessment studies were carried out on various waste forms, buffer materials and mortar. 2) In the safety evaluation study for shallow land disposal, migration behaviour of nuclides in the soil layer was studied. 3) In the safety evaluation study for geological disposal, chemical behaviour of radionuclides in water, nuclide migration in geosphere and groundwater flow system were studied. Migration of uranium series nuclides in uranium ore deposit was studied as a part of natural analogue study. (author)

  2. Progress report on safety research on radioactive waste management for the period April 1992 to March 1993

    International Nuclear Information System (INIS)

    Muraoka, Susumu; Senoo, Muneaki; Sekine, Keiichi

    1994-03-01

    This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Shallow Land Migration Laboratory, Environmental Geochemistry Laboratory and Environmental Radiochemistry Laboratory of the Department of Environmental Safety Research during the fiscal year of 1992 (April 1, 1992-March 31, 1993). The topics are as follows: 1) As for waste forms and engineered barrier material, performance assessment studies were carried out on various waste forms, buffer materials and mortar. 2) In the safety evaluation study for shallow land disposal, migration behavior in the soil layer were studied. 3) In the safety evaluation study for geological disposal, chemical behavior of nuclide in water, nuclide migration and fixation in geosphere were studied. 4) Distribution of uranium and migration of uranium series nuclide in uranium ore were examined as a natural analogue study. (author)

  3. Environmental Assessment: Waste Tank Safety Program, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1994-02-01

    The US Department of Energy (DOE) needs to take action in the near-term, to accelerate resolution of waste tank safety issues at the Hanford Site near the City of Richland, Washington, and reduce the risks associated with operations and management of the waste tanks. The DOE has conducted nuclear waste management operations at the Hanford Site for nearly 50 years. Operations have included storage of high-level nuclear waste in 177 underground storage tanks (UST), both in single-shell tank (SST) and double-shell tank configurations. Many of the tanks, and the equipment needed to operate them, are deteriorated. Sixty-seven SSTs are presumed to have leaked a total approximately 3,800,000 liters (1 million gallons) of radioactive waste to the soil. Safety issues associated with the waste have been identified, and include (1) flammable gas generation and episodic release; (2) ferrocyanide-containing wastes; (3) a floating organic solvent layer in Tank 241-C-103; (4) nuclear criticality; (5) toxic vapors; (6) infrastructure upgrades; and (7) interim stabilization of SSTs. Initial actions have been taken in all of these areas; however, much work remains before a full understanding of the tank waste behavior is achieved. The DOE needs to accelerate the resolution of tank safety concerns to reduce the risk of an unanticipated radioactive or chemical release to the environment, while continuing to manage the wastes safely

  4. Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2009

    International Nuclear Information System (INIS)

    2009-01-01

    In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2009 are published

  5. Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2011

    International Nuclear Information System (INIS)

    2011-04-01

    In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2011 are published.

  6. Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2012

    International Nuclear Information System (INIS)

    2012-04-01

    In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2011 are published.

  7. Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2011

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-04-15

    In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2011 are published.

  8. Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2014

    International Nuclear Information System (INIS)

    2014-04-01

    In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2014 are published.

  9. 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

  10. Management of long-lived radioactive waste: stakes and ASN actions

    International Nuclear Information System (INIS)

    Dandrieux, G.

    2011-01-01

    Due to the length of time it takes to decay, long-lived radioactive waste will remain a hazard on a timescale beyond the length of a human life, and even of several generations. In the case of this waste, long-term management solutions must be implemented to protect human health and the environment without requiring human intervention. In accordance with requirements under the Law, ANDRA (national agency for the management of radioactive waste) is carrying out research on disposal solutions in deep or subsurface geological formations. Nonetheless, until such repositories become available, ASN (authority for nuclear safety) has a duty to ensure safety at current and future interim storage facilities, as well as the safety of operations to retrieve and package this type of waste. To this end, ASN acts on several levels: it is involved in drawing up regulations and reference texts, at national and international level, it examines safety analysis reports related to radioactive waste management at basic nuclear installations, by means of inspections that it performs at every step in radioactive waste management. In its capacity as joint coordinator of the national plan for the management of nuclear waste and materials (PNGMDR) working group, ASN also plays a very active role in drawing up the provisions of the PNGMDR aimed at improving and optimising radioactive waste management. (author)

  11. Radioactive wastes. Commune convention about the safety of spent fuel management and about the radioactive waste management

    International Nuclear Information System (INIS)

    Anon.

    1997-01-01

    This common convention do not give detailed safety standards but general obligations whom objective is the development of a safety culture in the world. It concerns the spent fuels (valuable and valued by the reprocessing) and radioactive wastes (matter without any later use). (N.C.)

  12. High Level Radioactive Waste Management

    International Nuclear Information System (INIS)

    1991-01-01

    The proceedings of the second annual international conference on High Level Radioactive Waste Management, held on April 28--May 3, 1991, Las Vegas, Nevada, provides information on the current technical issue related to international high level radioactive waste management activities and how they relate to society as a whole. Besides discussing such technical topics as the best form of the waste, the integrity of storage containers, design and construction of a repository, the broader social aspects of these issues are explored in papers on such subjects as conformance to regulations, transportation safety, and public education. By providing this wider perspective of high level radioactive waste management, it becomes apparent that the various disciplines involved in this field are interrelated and that they should work to integrate their waste management activities. Individual records are processed separately for the data bases

  13. The ANSTO waste management action plan

    International Nuclear Information System (INIS)

    Levins, D.

    1997-01-01

    ANSTO's Waste Management Action Plan is a five-year program which addresses legacy issues that have arisen from the accumulation of radioactive wastes at Lucas Heights over the last forty years. Following an extensive review of waste management practices, a detailed Action Plan was prepared involving seventeen projects in the areas of solid wastes, liquid wastes, control of effluents and emissions, spent reactor fuel and organisational issues. The first year of the Waste Management Action Plan has resulted in significant achievements, especially in the areas of improved storage of solid wastes, stabilisation of uranium scrap, commissioning and operation of a scanning system for low-level waste drums, treatment of intermediate-level liquid wastes and improvements in the methods for monitoring of spent fuel storage facilities. The main goal of the Waste Management Action Plan is to achieve consistency, by the year 2000, with best practice as identified in the Radioactive Waste Safety Standards and Guidelines currently under development by the IAEA

  14. Radioactive waste management in perspective

    International Nuclear Information System (INIS)

    1996-01-01

    This report drafted by the Nuclear Energy Agency (NEA) deals with the basic principles and the main stages of radioactive waste management. The review more precisely focuses on what relates to environment protection, safety assessment, financing, social issues, public concerns and international co-operation. An annex finally summarises the radioactive waste management programs that are implemented in 15 of the NEA countries. (TEC). figs

  15. Fernald waste management and disposition

    International Nuclear Information System (INIS)

    West, M.L.; Fisher, L.A.; Frost, M.L.; Rast, D.M.

    1995-01-01

    Historically waste management within the Department of Energy complex has evolved around the operating principle of packaging waste generated and storing until a later date. In many cases wastes were delivered to onsite waste management organizations with little or no traceability to origin of generation. Sites then stored their waste for later disposition offsite or onsite burial. While the wastes were stored, sites incurred additional labor costs for maintaining, inspecting and repackaging containers and capital costs for storage warehouses. Increased costs, combined with the inherent safety hazards associated with storage of hazardous material make these practices less attractive. This paper will describe the methods used at the Department of Energy's Fernald site by the Waste Programs Management Division to integrate with other site divisions to plan in situ waste characterization prior to removal. This information was utilized to evaluate and select disposal options and then to package and ship removed wastes without storage

  16. Radioactive waste management: a utility view

    International Nuclear Information System (INIS)

    Draper, E.L.

    1982-01-01

    The management of radioactive waste continues to be a matter of public concern and discussion. There is broad agreement among members of the technical community that the various types of waste radioactive species can be managed without jeopardizing public health and safety. Despite this consensus, one of the major reasons cited by opponents of commercial nuclear power for their opposition is the lack of a fully deployed waste management program. Such a program has been suggested but implementation is not yet complete. It is essential that a program be undertaken so as to dispel the impression that past inaction on waste disposal represents an inability to deal safely with wastes

  17. Radioactive waste management in Slovenia

    International Nuclear Information System (INIS)

    Fink, K.

    1992-01-01

    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 political marketing tool, make things even more complex. Public involvement in planning and development of radioactive waste management program must be perceived as essential for the success of the program. Education is a precursor to public comprehension and confidence which lead to adequate waste management decisions that will protect the public health, safety and environment without jeopardizing further progress and development. (author) [sl

  18. Waste Management Technical Manual

    Energy Technology Data Exchange (ETDEWEB)

    Buckingham, J.S. [ed.

    1967-08-31

    This Manual has been prepared to provide a documented compendium of the technical bases and general physical features of Isochem Incorporated`s Waste Management Program. The manual is intended to be used as a means of training and as a reference handbook for use by personnel responsible for executing the Waste Management Program. The material in this manual was assembled by members of Isochem`s Chemical Processing Division, Battelle Northwest Laboratory, and Hanford Engineering Services between September 1965 and March 1967. The manual is divided into the following parts: Introduction, contains a summary of the overall Waste Management Program. It is written to provide the reader with a synoptic view and as an aid in understanding the subsequent parts; Feed Material, contains detailed discussion of the type and sources of feed material used in the Waste Management Program, including a chapter on nuclear reactions and the formation of fission products; Waste Fractionization Plant Processing, contains detailed discussions of the processes used in the Waste Fractionization Plant with supporting data and documentation of the technology employed; Waste Fractionization Plant Product and Waste Effluent Handling, contains detailed discussions of the methods of handling the product and waste material generated by the Waste Fractionization Plant; Plant and Equipment, describes the layout of the Waste Management facilities, arrangement of equipment, and individual equipment pieces; Process Control, describes the instruments and analytical methods used for process control; and Safety describes process hazards and the methods used to safeguard against them.

  19. Radioactive waste management in France: safety demonstration fundamentals.

    Science.gov (United States)

    Ouzounian, G; Voinis, S; Boissier, F

    2012-01-01

    The main challenge in development of the safety case for deep geological disposal is associated with the long periods of time over which high- and intermediate-level long-lived wastes remain hazardous. A wide range of events and processes may occur over hundreds of thousands of years. These events and processes are characterised by specific timescales. For example, the timescale for heat generation is much shorter than any geological timescale. Therefore, to reach a high level of reliability in the safety case, it is essential to have a thorough understanding of the sequence of events and processes likely to occur over the lifetime of the repository. It then becomes possible to assess the capability of the repository to fulfil its safety functions. However, due to the long periods of time and the complexity of the events and processes likely to occur, uncertainties related to all processes, data, and models need to be understood and addressed. Assessment is required over the lifetime of the radionuclides contained in the radioactive waste. Copyright © 2012. Published by Elsevier Ltd.

  20. Extended storage for radioactive wastes: relevant aspects related to the safety

    International Nuclear Information System (INIS)

    Castillo, Reinaldo G.; Peralta V, José L.P.; Estevez, Gema G. F.

    2013-01-01

    The safe management of radioactive waste is an issue of great relevance globally linked to the issue of the peaceful use of nuclear energy. Among the steps in the management of this waste, the safe storage is one of the most important. Given the high costs and uncertainties existing among other aspects of the variants of disposal of radioactive waste, the prolonged storage of these wastes for periods exceeding 50 years is an option that different countries more and more value. One of the fundamental problems to take into account is the safety of the stores, so in this work are evaluated different safety components associated with these facilities through a safety analysis methodology. Elements such as human intrusion, the construction site, the design of the facility, among others are identified as some of the key aspects to take into account when evaluating the safety of these types of facilities. Periods of activities planned for a long-term storage of radioactive waste exceed, in general, the useful life of existing storage facilities. This work identified new challenges to overcome in order to meet the requirements for the achievement of a safe management of radioactive waste without negative impacts on the environment and man

  1. 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)

  2. 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

  3. Nuclear waste management at DOE

    International Nuclear Information System (INIS)

    Perge, A.F.

    1979-01-01

    DOE is responsible for interim storage for some radioactive wastes and for the disposal for most of them. Of the wastes that have to be managed a significant part are a result of treatment systems and devices for cleaning gases. The long term waste management objectives place minimal reliance on surveillance and maintenance. Thus, the concerns about the chemical, thermal, and radiolytic degradation of wastes require technology for converting the wastes to forms acceptable for long term isolation. The strategy of the DOE airborne radioactive waste management program is to increase the service life and reliability of filters; to reduce filter wastes; and in anticipation of regulatory actions that would require further reductions in airborne radioactive releases from defense program facilities, to develop improved technology for additional collection, fixation, and long-term management of gaseous wastes. Available technology and practices are adequate to meet current health and safety standards. The program is aimed primarily at cost effective improvements, quality assurance, and the addition of new capability in areas where more restrictive standards seem likely to apply in the future

  4. National report of the Slovak Republic. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2003

    International Nuclear Information System (INIS)

    Burclova, J.; Ivan, J.; Jurina, V.

    2003-04-01

    A brief national safety report of the Slovak Republic in 2003 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (A) Introduction; (B) Policies and practices; (C) Scope of application; (D) Inventories and lists; (E) Legislation and regulation; (F) Other general safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste management; (I) Transboundary movement; (J) Disused sealed sources; (K) Planned activities to improve safety; (L) Annexes: (I and II) List of SF and RAW management nuclear facilities; (III) List of nuclear facilities subject to decommissioning; (IV) Inventory of stored SF (t HM); (V) Inventory of disposed of and stored RAW; (VI) List of selected national laws, regulations and guidelines; (VII) List of international expert reports and safety analysis reports; (VIII) List of authors

  5. National report of the Slovak Republic. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2003

    Energy Technology Data Exchange (ETDEWEB)

    Burclova, J [Nuclear Regulatory Authority of the Slovak Republic, Bratislava (Slovakia); Ivan, J [Slovenske elektrarne, a.s., Bratislava (Slovakia); Jurina, V [Health Ministry of the Slovak Republic, Bratislava (Slovakia); and others

    2003-04-01

    A brief national safety report of the Slovak Republic in 2003 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (A) Introduction; (B) Policies and practices; (C) Scope of application; (D) Inventories and lists; (E) Legislation and regulation; (F) Other general safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste management; (I) Transboundary movement; (J) Disused sealed sources; (K) Planned activities to improve safety; (L) Annexes: (I and II) List of SF and RAW management nuclear facilities; (III) List of nuclear facilities subject to decommissioning; (IV) Inventory of stored SF (t HM); (V) Inventory of disposed of and stored RAW; (VI) List of selected national laws, regulations and guidelines; (VII) List of international expert reports and safety analysis reports; (VIII) List of authors.

  6. Croatian radioactive waste management program: Current status

    International Nuclear Information System (INIS)

    Matanic, R.; Lebegner, J.

    2001-01-01

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

  7. Post-Accident Waste Management in Ukraine : Challenges and Steps Needed to Resolve the Accident Waste Problem

    International Nuclear Information System (INIS)

    Kilochytska, T.; Zinkevich, L.; Shybetskyi, I.; Krone, J.

    2016-01-01

    Conclusions: • Solving the problem of management of “Chernobyl waste” requires: - a systematic review of the existing norms and regulations with respect to best international practice of radioactive waste management; - improvement of the existing classification / characterization of radioactive waste with a focus on disposal; - improvement of the safety assessment approaches for licensing the disposal of accident waste, taking into account relevant safety features and site specific conditions; - involving of international experience and support to plan and perform safety related activity on the Shelter Object transformation

  8. Biomedical waste management: Incineration vs. environmental safety

    Directory of Open Access Journals (Sweden)

    Gautam V

    2010-01-01

    Full Text Available Public concerns about incinerator emissions, as well as the creation of federal regulations for medical waste incinerators, are causing many health care facilities to rethink their choices in medical waste treatment. As stated by Health Care Without Harm, non-incineration treatment technologies are a growing and developing field. Most medical waste is incinerated, a practice that is short-lived because of environmental considerations. The burning of solid and regulated medical waste generated by health care creates many problems. Medical waste incinerators emit toxic air pollutants and toxic ash residues that are the major source of dioxins in the environment. International Agency for Research on Cancer, an arm of WHO, acknowledged dioxins cancer causing potential and classified it as human carcinogen. Development of waste management policies, careful waste segregation and training programs, as well as attention to materials purchased, are essential in minimizing the environmental and health impacts of any technology.

  9. Activities of the IAEA in the area of radioactive waste management

    International Nuclear Information System (INIS)

    Efremenkov, V.M.

    1998-01-01

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

  10. Hospital waste management in developing countries: A mini review.

    Science.gov (United States)

    Ali, Mustafa; Wang, Wenping; Chaudhry, Nawaz; Geng, Yong

    2017-06-01

    Health care activities can generate different kinds of hazardous wastes. Mismanagement of these wastes can result in environmental and occupational health risks. Developing countries are resource-constrained when it comes to safe management of hospital wastes. This study summarizes the main issues faced in hospital waste management in developing countries. A review of the existing literature suggests that regulations and legislations focusing on hospital waste management are recent accomplishments in many of these countries. Implementation of these rules varies from one hospital to another. Moreover, wide variations exist in waste generation rates within as well as across these countries. This is mainly attributable to a lack of an agreement on the definitions and the methodology among the researchers to measure such wastes. Furthermore, hospitals in these countries suffer from poor waste segregation, collection, storage, transportation and disposal practices, which can lead to occupational and environmental risks. Knowledge and awareness regarding proper waste management remain low in the absence of training for hospital staff. Moreover, hospital sanitary workers, and scavengers, operate without the provision of safety equipment or immunization. Unsegregated waste is illegally recycled, leading to further safety risks. Overall, hospital waste management in developing countries faces several challenges. Sustainable waste management practices can go a long way in reducing the harmful effects of hospital wastes.

  11. Nuclear power plants waste management practices in France

    International Nuclear Information System (INIS)

    Matsuda, Fumio

    1998-01-01

    This survey offers a complete review concerning the nuclear power plants waste management in France from generation to disposal, as well as future evolutions. Fundamental Safety Rule specified by the government defines safety objectives, design bases for surface disposals and preliminary terms for acceptance of waste packages on the surface disposal site. A governmental decree authorizes the creation of CSA (Centre de Stockage de l'Aude; French surface repository), and defines the limits of radiological inventory of the disposal facility. The national waste agency ANDRA was established in 1979 by government (turned into public in 1991), and ANDRA defines the technical specifications involving acceptance criteria of the waste packages. The main feature of the French management includes; Comprehensive quality assurance program that encompasses all area of the management. Centralized installation for the melting of contaminated scrap metals and incineration of low level technological wastes. Mobile unit for common treatment of ion exchange resin. Concrete package assuring the long term containment. Complete tracking system of wastes from generation to disposal. This survey would be useful in the consideration of Japanese waste management including miscellaneous wastes, high βγ wastes, large metallic wastes, etc. (author)

  12. Institute of Energy and Climate Research IEK-6. Nuclear Waste Management report 2011/2012. Material science for nuclear waste management

    International Nuclear Information System (INIS)

    Klinkenberg, M.; Neumeier, S.; Bosbach, D.

    2013-01-01

    The nuclear waste management section of the Institute of Energy and Climate Research IEK-6 in Juelich is focused on research on radiochemistry aspects/materials science relevant for the long-term safety of nuclear waste storage and disposal. Studies on innovative waste management strategies include partitioning o actinides and the development of ceramic waste forms. Structural research is covering solid state chemistry, crystallography and computational science to model actinide containing compounds. With respect to waste management concepts nondestructive essay techniques, waste treatment procedures and product quality control strategies were developed.

  13. Sweden's first national report under the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Swedish implementation of the obligations of the Joint Convention

    International Nuclear Information System (INIS)

    2003-01-01

    This report is issued according to Article 32 of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. Sweden signed the Joint Convention September 29, 1997 and the Joint Convention entered into force on June 18, 2001. The areas covered by the Joint Convention have been incorporated in the Swedish system for spent fuel and radioactive waste management for a long time. The Swedish Government considered at the time of signing of the Joint Convention that the safety philosophy, legislation and the safety work conducted by the licensees and the authorities in Sweden complied with the obligations of the Convention. This is confirmed in the present report. The Swedish Government directed the Swedish Nuclear Power Inspectorate (SKI) to prepare this report in co-operation with the Swedish Radiation Protection Authority (SSI). A working group of five persons, with representatives from SKI, SSI and the Swedish Nuclear Fuel and Waste Management Co. (SKB), has prepared this report. The report has been discussed in the boards of SKI and SSI. The Swedish Government adopted the report in April 2003. Section A of this report provides an overview of the Swedish nuclear waste programme, including a brief historical review, in order to give the reader a background to the current programme for the management of spent fuel and radioactive waste. Sections B to J provide information on which the conclusions are drawn about the compliance with the obligations of the Joint Convention. By necessity this information is rather brief and strongly focused on those aspects which are addressed in the articles. Too many details and additional information would over-load the report and make the review process difficult. The goal has been to provide enough details to make the Swedish practices understandable. Data that might be missing will be added on request as a part of the review process. Article 32 of the Joint Convention calls for a self

  14. Current issues and regulatory infrastructure aspects on radioactive waste management in Romania

    International Nuclear Information System (INIS)

    Vieru, G.

    2002-01-01

    The nuclear facilities that exist throughout Romania perform a broad range of missions from research to nuclear materials production to radioactive waste management, and to deactivation and decommissioning. As a consequence, there is a broad array of external regulations and internal requirements that potentially applies to a facility or activity. Therefore, the management of radioactive waste occurs within a larger context of managing hazards, both radiological and industrial, at these facilities. At the same time, concern for upgrading existing facilities used for radioactive waste management, as called for in Article 12, fits into a larger framework of safety management. The primary objective of the Romanian Nuclear Regulatory Body-CNCAN on legislation and regulatory infrastructure for the safety of radioactive waste management is to protect human health and the environment now and in the future. It is unanimously recognized that a well developed regulated system for the management and disposal of radioactive waste is a prerequisite for both public and market acceptance of nuclear energy. It is to underline that the continuing internationalization of the nuclear industry following terrorist attacks of 11 September 2001 stresses the need for national legislation and regulatory infrastructure to be based on internationally endorsed principles and safety standards. The paper presents some aspects of the Romanian experience on the national legislative and regulatory system related to the followings aspects of the safety aspects of radioactive waste management: definition of responsibilities; nuclear and radiation safety requirements; siting and licensing procedures; regulatory functions; international co-operation and coherence on strategies and criteria in the area of safety of radioactive waste management. Finally, prescriptive and goal oriented national as well international regimes in the field of the safety of radioactive waste management are briefly commented

  15. Aspects of the state safety regulation dealing with management of radioactive wastes from nuclear vessels

    International Nuclear Information System (INIS)

    Markarov, Valentin G.

    1999-01-01

    According to this presentation, the Constitution of the Russian Federation states that nuclear power engineering and fissile materials are under the jurisdiction of the Russian Federation. But there is no federal law with detailed directions for radioactive waste (RW) management, which thus comes under the Federal law ''On Use of Atomic Energy''. This law defines the legal basis and principles of regulating the relations occurring during RW management and sets some general requirements. RW management safety is regulated by the federal norms and rules (1) Radiation Safety Norms (NRB-96), Basic Sanitary Rules (OSP-72, 87) and (3) Sanitary Rules for RW Management (SPORO-85), etc. A number of normative documents on RW management will be put in force in 1999. For work in the field of RW management, licence must in general be obtained from Gozatomnazdor of Russia. The conditions for receiving a license for the management of RW from vessels are presented

  16. Radioactive waste management in a hospital.

    Science.gov (United States)

    Khan, Shoukat; Syed, At; Ahmad, Reyaz; Rather, Tanveer A; Ajaz, M; Jan, Fa

    2010-01-01

    Most of the tertiary care hospitals use radioisotopes for diagnostic and therapeutic applications. Safe disposal of the radioactive waste is a vital component of the overall management of the hospital waste. An important objective in radioactive waste management is to ensure that the radiation exposure to an individual (Public, Radiation worker, Patient) and the environment does not exceed the prescribed safe limits. Disposal of Radioactive waste in public domain is undertaken in accordance with the Atomic Energy (Safe disposal of radioactive waste) rules of 1987 promulgated by the Indian Central Government Atomic Energy Act 1962. Any prospective plan of a hospital that intends using radioisotopes for diagnostic and therapeutic procedures needs to have sufficient infrastructural and manpower resources to keep its ambient radiation levels within specified safe limits. Regular monitoring of hospital area and radiation workers is mandatory to assess the quality of radiation safety. Records should be maintained to identify the quality and quantity of radioactive waste generated and the mode of its disposal. Radiation Safety officer plays a key role in the waste disposal operations.

  17. Radioactive Waste Management in A Hospital

    Science.gov (United States)

    Khan, Shoukat; Syed, AT; Ahmad, Reyaz; Rather, Tanveer A.; Ajaz, M; Jan, FA

    2010-01-01

    Most of the tertiary care hospitals use radioisotopes for diagnostic and therapeutic applications. Safe disposal of the radioactive waste is a vital component of the overall management of the hospital waste. An important objective in radioactive waste management is to ensure that the radiation exposure to an individual (Public, Radiation worker, Patient) and the environment does not exceed the prescribed safe limits. Disposal of Radioactive waste in public domain is undertaken in accordance with the Atomic Energy (Safe disposal of radioactive waste) rules of 1987 promulgated by the Indian Central Government Atomic Energy Act 1962. Any prospective plan of a hospital that intends using radioisotopes for diagnostic and therapeutic procedures needs to have sufficient infrastructural and manpower resources to keep its ambient radiation levels within specified safe limits. Regular monitoring of hospital area and radiation workers is mandatory to assess the quality of radiation safety. Records should be maintained to identify the quality and quantity of radioactive waste generated and the mode of its disposal. Radiation Safety officer plays a key role in the waste disposal operations. PMID:21475524

  18. Radioactive waste management in an Australian state - IAEA style

    International Nuclear Information System (INIS)

    Shields, B.; Newbery, S.M.

    1999-01-01

    The IAEA have produced a series of publications within the RADWASS programme. These publications are comprehensive in their coverage and are applicable to all aspects of radioactive waste management - from the individual user level to State and National level. Adherence to the principles contained in these publications is advocated in the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The publications provide a useful check list against which to determine the current status of radioactive management, at various levels (individual level, State, National) and also provide a basis for planning future waste management requirements. In Tasmania, these publications have been utilised to assess the current radioactive waste management system and to determine future management requirements, particularly for storage of radioactive waste. This paper illustrates the application of the publications for auditing individual users' waste management status and for determining future State storage requirements for radioactive waste. A brief outline of the process used and the main issues identified as a result, will be presented. These issues include some requiring a National approach for their resolution. Copyright (1999) Australasian Radiation Protection Society Inc

  19. Screening criteria for siting waste management facilities: Regional Management Plan

    International Nuclear Information System (INIS)

    1986-01-01

    The Midwest Interstate Low-Level Radioactive Waste Commission (Midwest Compact) seeks to define and place into operation a system for low-level waste management that will protect the public health and safety and the environment from the time the waste leaves its point of origin. Once the system is defined it will be necessary to find suitable sites for the components of that waste management system. The procedure for siting waste management facilities that have been chosen by the compact is one in which a host state is chosen for each facility. The host state is then given the freedom to select the site. Sites will be needed of low-level waste disposal facilities. Depending on the nature of the waste management system chosen by the host state, sites may also be needed for regional waste treatment facilities, such as compactors or incinerators. This report provides example criteria for use in selecting sites for low-level radioactive waste treatment and disposal facilities. 14 refs

  20. Waste management

    International Nuclear Information System (INIS)

    Dworschak, H.; Mannone, F.; Rocco, P.

    1995-01-01

    The presence of tritium in tritium-burning devices to be built for large scale research on thermonuclear fusion poses many problems especially in terms of occupational and environmental safety. One of these problems derives from the production of tritiated wastes in gaseous, liquid and solid forms. All these wastes need to be adequately processed and conditioned to minimize tritium releases to an acceptably low occupational and environmental level and consequently to protect workers and the public against the risks of unacceptable doses from exposure to tritium. Since all experimental thermonuclear fusion devices of the Tokomak type to be built and operated in the near future as well as all experimental activities undertaken in tritium laboratories like ETHEL will generate tritiated wastes, current strategies and practices to be applied for the routine management of these wastes need to be defined. Adequate background information is provided through an exhaustive literature survey. In this frame alternative tritiated waste management options so far investigated or currently applied to this end in Europe, USA and Canada have been assessed. The relevance of tritium in waste containing gamma-emitters, originated by the neutron activation of structural materials is assessed in relation to potential final disposal options. Particular importance has been attached to the tritium retention efficiency achievable by the various waste immobilization options. 19 refs., 2 figs., 1 tab

  1. 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

  2. Human factors in waste management - potential and reality

    International Nuclear Information System (INIS)

    Thompson, J.S.

    1996-01-01

    There is enormous potential for human factors contributions in the realm of waste management. The reality, however, is very different from the potential. This is particularly true for low-level and low-level mixed-waste management. The hazards are less severe; therefore, health and safety requirements (including human factors) are not as rigorous as for high-level waste. High-level waste management presents its own unique challenges and opportunities. Waste management is strongly driven by regulatory compliance. When regulations are flexible and open to interpretation and the environment is driven so strongly by regulatory compliance, standard practice is to drop open-quotes nice to haveclose quotes features, like a human factors program, to save money for complying with other requirements. The challenge is to convince decision makers that human factors can help make operations efficient and cost-effective, as well as improving safety and complying with regulations. A human factors program should not be viewed as competing with compliance efforts; in fact, it should complement them and provide additional cost-effective means of achieving compliance with other regulations. Achieving this synergy of human factors with ongoing waste management operations requires educating program and facility managers and other technical specialists about human factors and demonstrating its value open-quotes through the back doorclose quotes on existing efforts. This paper describes ongoing projects at Los Alamos National Laboratory (LANL) in support of their waste management groups. It includes lessons learned from hazard and risk analyses, safety analysis reports, job and task analyses, operating procedure development, personnel qualification/certification program development, and facility- and job-specific training program and course development

  3. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management. First national report on the implementation by France of the obligations of the Convention

    International Nuclear Information System (INIS)

    2003-03-01

    The Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management is supplementing the Convention of Nuclear Safety. it was approved by France on february 22, 2000 and it entered into force on June 18,2001. Article 32 obliges each contracting Party to present at the review meetings (every three years) a report on the way in which it implements the obligations of the Convention (full text of the Convention and additional information on the web site of the IAEA, its director General being the depository of the Convention. (author)

  4. Public sector's research programme on nuclear waste management

    International Nuclear Information System (INIS)

    Vuori, S.

    2000-06-01

    According to the Finnish nuclear energy legislation, each producer of nuclear waste is responsible for the safe handling, management and disposal of the waste as well as for the arising costs. Authorities supervise and control the implementation of the national waste management programme and set the necessary safety and other requirements. In these tasks the authorities are supported by a research programme on nuclear waste management that is independent of the implementing organisations and power companies. The main objective of the research programme has been to provide the authorities with information and research results relevant for the safety of nuclear waste management. The main emphasis in this research programme has been devoted to the final disposal of spent fuel. The whole area of the research programme has been subdivided into the following main topic areas: (1) Behaviour of bedrock (2) Geohydrology and geochemistry, (3) Release of radionuclides from repository and subsequent transport in bedrock, (4) Engineered safety barriers of the repository, system, (5) Performance and safety assessment of spent fuel disposal facilities, (6) Waste management technology and costs (7) Evaluation of the contents and scope of and observation of the realisation of the environmental impact assessment procedure for the siting of spent nuclear fuel disposal facility, and research on other societal and sociopolitical issues, and (8) Public information, attitude, and image issues for waste management facilities. The research programme has generated considerably increased information on the behaviour of the natural and technical release barriers of the disposal system and thereby contributed to building of confidence on the long-term safety of geological disposal of spent fuel. Furthermore, increased confidence among the public in the affected candidate municipalities has probably been achieved by the complementary studies conducted within the research programme on topics

  5. Health care waste management practice in a hospital.

    Science.gov (United States)

    Paudel, R; Pradhan, B

    2010-10-01

    Health-care waste is a by-product of health care. Its poor management exposes health-care workers, waste handlers and the community to infections, toxic effects and injuries including damage of the environment. It also creates opportunities for the collection of disposable medical equipment, its re-sale and potential re-use without sterilization, which causes an important burden of disease worldwide. The purpose of this study was to find out health care waste management practice in hospital. A cross-sectional study was conducted in Narayani Sub-Regional Hospital, Birgunj from May to October 2006 using both qualitative and quantitative methods. Study population was four different departments of the hospital (Medical/Paediatric, Surgical/Ortho, Gynae/Obstetric and Emergency), Medical Superintendent, In-charges of four different departments and all sweepers. Data was collected using interview, group discussion, observation and measurement by weight and volume. Total health-care waste generated was 128.4 kg per day while 0.8 kg per patient per day. The composition of health care waste was found to be 96.8 kg (75.4%) general waste, 24.1 kg (8.8%) hazardous waste and 7.5 kg (5.8%) sharps per day by weight. Health staffs and sweepers were not practicing the waste segregation. Occupational health and safety was not given due attention. Majority of the sweepers were unaware of waste management and need of safety measures to protect their own health. Health care waste management practice in the hospital was unsatisfactory because of the lack of waste management plan and carelessness of patients, visitors and staffs. Therefore the hospital should develop the waste management plan and strictly follow the National Health Care Waste Management Guideline.

  6. Design of Radioactive Waste Management Systems at Nuclear Power Plants

    International Nuclear Information System (INIS)

    1986-01-01

    This Safety Guide is addressed to the administrative and technical authorities and specialists dealing with the design, construction and operation of nuclear power plants, and in particular waste management facilities at nuclear power plants. This Guide has been prepared as part of the IAEA Waste Handling, Treatment and Storage programme. It is a follow-up document to the Code of Practice on Management of Radioactive Wastes from Nuclear Power Plants published in 1985 in the IAEA Safety Standards, Safety Series No. 69, in which basic principles for management of radioactive wastes at nuclear power plants are set out. The IAEA has established wide ranging programmes to provide Member States with guidance on different aspects of safety and technology related to thermal neutron power reactors and associated nuclear fuel cycle operations, including those for management of radioactive wastes. There are many IAEA publications related to various technical and safety aspects of different nuclear energy applications. All these publications are issued by the Agency for the use of Member States in connection with their own nuclear technological safety requirements. They are based on national experience contributed by experts from different countries and relate to common features in approaches to the problems discussed. However, the final decision and legal responsibility in any regulatory procedure always rest with the Member State. This particular Guide aims to provide general and detailed principles for the design of waste management facilities at nuclear power plants. It emphasizes what and how specific safety requirements for the management of radioactive wastes from nuclear power plants can be met in the design and construction stage. The safety requirements for operation of such facilities will be considered in the Agency's next Safety Series publication, Safety Guide 50-SG-011, Operational Management for Radioactive Effluents and Wastes Arising in Nuclear Power Plants

  7. Radioactive waste management - a safe solution

    International Nuclear Information System (INIS)

    1993-01-01

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

  8. Integrated data management system for radioactive waste and spent fuel in Korea

    International Nuclear Information System (INIS)

    Shin, Young Ho

    2001-03-01

    An integrated data management system for the safe management of radioactive waste and spent fuel in Korea is developed to collect basic information, provide the framework for national regulation, and improve national competition and efficiency in the management of radioactive waste and spent fuel. This system can also provide public access to information such as a statistical graphs and integrated data from various waste generators to meet increased public needs and interests. So through the system, the five principles (independence, openness, clearance, efficiency and reliance) of safety regulation can be realized, and public understanding and reliance on the safety of spent fuel and radioactive waste management can be promoted by providing reliable information, it can ensure an openness within the international nuclear community and efficiently support international agreements among contracting parties by operating safe and efficient management of spent fuel and radioactive waste (IAEA joint convention on the safety of spent fuel management and on the safety of radioactive waste management), the system can compensate for the imperfections in safe regulation of radioactive waste and spent fuel management related to waste generation, storage and disposal, and make it possible to holistic control and finally re-organize the basic framework of KINS's intermediate and long term research organization and trends, regarding waste management policy is to integrate safe management and unit safe disposal. For this objectives, benchmark study was performed on similar data base system worldwide and data specification with major input/output data during the first phase of this project

  9. Integrated data management system for radioactive waste and spent fuel in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Park, Yong Taek [Korea Power Engineering Co., Inc., Yongin (Korea, Republic of)

    2002-05-15

    An integrated data management system for the safe management of radioactive waste and spent fuel in Korea is developed to collect basic information, provide the framework for national regulation and improve national competition and efficiency in the management of radioactive waste and spent fuel. This system can also provide public access to information such as a statistical graphs and integrated data from various waste generators to meet increased public needs and interests. Through the system, the five principles(independence, openness, clearance, efficiency and reliance) of safety regulation can be realized and public understanding and reliance on the safety of spent fuel and radioactive waste management can be promoted. By providing reliable information and openness within the international nuclear community can be ensured and efficient support of international agreements among contracting parties can be ensured. By operating safe and efficient management of spent fuel and radioactive waste (IAEA joint convention on the safety of spent fuel management and on the safety of radioactive waste management), the system can compensate for the imperfections in safe regulation of radioactive waste and spent fuel management related to waste generation, storage and disposal, and make it possible for holistic control and reorganization of the basic framework of KINS's intermediate and long term research organization and trends, regarding waste management policy so as to integrate safe management and unit safe disposal. To meet this objectives, design of the database system structure and the study of input/output data validation and verification methodology was performed during the second phase of this project.

  10. Radioactive waste management in France

    International Nuclear Information System (INIS)

    Antonioli, S.; Manet, M.

    1985-01-01

    The experience acquired over forty years through an extensive nuclear power program has enabled France to develop a corresponding comprehensive waste management policy, covering rules and regulations, health and safety aspects for both the short and the long term, technologies from the design of installations to their decommissioning and the conditioning, transport and disposal of the entailed wastes. The various partners, their role and responsibilities, specially those involved in industrial activities, are briefly introduced. The principles and objectives of French waste management policy, the techniques adopted and the long term disposal program are then presented [fr

  11. Radioactive waste management in France

    International Nuclear Information System (INIS)

    Lefevre, J.; Brignon, P.

    1986-01-01

    The experience acquired over forty years through an extensive nuclear power program has enabled FRANCE to develop a corresponding comprehensive waste management policy, covering rules and regulations, health and safety aspects for both the short and the long term, technologies from the design of installations to their decommissioning, and the conditioning, transport and disposal of the entailed wastes. The various partners, their role and responsabilities, specially those involved in industrial activities, are briefly introduced. The principles and objectives of French waste management policy, the techniques adopted and the long term disposal program are then presented [fr

  12. Managing nuclear wastes: an overview of the issues

    International Nuclear Information System (INIS)

    Cummings, R.G.; Utton, A.E.

    1981-01-01

    The issues involving nuclear waste management are reviewed. The author points out the need for a critical overview of research priorities concerning nuclear waste management (NWM), and he discusses the uncertainties surrounding the scope of the problem (i.e., the controversy concerning the extent of dangers to public health and safety associated with the transport and storage of nuclear wastes). This article, intended as a introdution to the other nuclear waste management papers in the journal, also briefly discusses the papers

  13. Battery collection in municipal waste management in Japan: challenges for hazardous substance control and safety.

    Science.gov (United States)

    Terazono, Atsushi; Oguchi, Masahiro; Iino, Shigenori; Mogi, Satoshi

    2015-05-01

    To clarify current collection rules of waste batteries in municipal waste management in Japan and to examine future challenges for hazardous substance control and safety, we reviewed collection rules of waste batteries in the Tokyo Metropolitan Area. We also conducted a field survey of waste batteries collected at various battery and small waste electric and electronic equipment (WEEE) collection sites in Tokyo. The different types of batteries are not collected in a uniform way in the Tokyo area, so consumers need to pay attention to the specific collection rules for each type of battery in each municipality. In areas where small WEEE recycling schemes are being operated after the enforcement of the Act on Promotion of Recycling of Small Waste Electrical and Electronic Equipment in Japan in 2013, consumers may be confused about the need for separating batteries from small WEEE (especially mobile phones). Our field survey of collected waste batteries indicated that 6-10% of zinc carbon and alkaline batteries discarded in Japan currently could be regarded as containing mercury. More than 26% of zinc carbon dry batteries currently being discarded may have a lead content above the labelling threshold of the EU Batteries Directive (2006/66/EC). In terms of safety, despite announcements by producers and municipalities about using insulation (tape) on waste batteries to prevent fires, only 2.0% of discarded cylindrical dry batteries were insulated. Our field study of small WEEE showed that batteries made up an average of 4.6% of the total collected small WEEE on a weight basis. Exchangeable batteries were used in almost all of mobile phones, digital cameras, radios, and remote controls, but the removal rate was as low as 22% for mobile phones. Given the safety issues and the rapid changes occurring with mobile phones or other types of small WEEE, discussion is needed among stakeholders to determine how to safely collect and recycle WEEE and waste batteries. Copyright

  14. 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)

  15. LOGISTICS OF WASTE MANAGEMENT IN HEALTHCARE INSTITUTIONS

    Directory of Open Access Journals (Sweden)

    Halina Marczak

    2016-07-01

    Full Text Available The waste management system in health care is a tool that allows to conduct reasonable steps to reduce their amount, collection, storage and transport, and provide a high level of utilization or disposal. Logistics solutions in waste management are intended to make full use of the infrastructure and technical resources, optimize costs, ensure the safety and health at work and meet legal requirements. The article discusses the elements of the logistics system of waste management in hospital, necessary to ensure the smooth flow of waste from its origin to landfilling. The following criteria were characterized: technical and technological, ecological and economic that can be used in the analysis and evaluation of solutions in waste management in the hospital. Finally, solutions to improve waste management system in the hospital on the example of the real object have been presented.

  16. Solid waste accident analysis in support of the Savannah River Waste Management Environmental Impact Statement

    International Nuclear Information System (INIS)

    Copeland, W.J.; Crumm, A.T.; Kearnaghan, D.P.; Rabin, M.S.; Rossi, D.E.

    1994-07-01

    The potential for facility accidents and the magnitude of their impacts are important factors in the evaluation of the solid waste management addressed in the Environmental Impact Statement. The purpose of this document is to address the potential solid waste management facility accidents for comparative use in support of the Environmental Impact Statement. This document must not be construed as an Authorization Basis document for any of the SRS waste management facilities. Because of the time constraints placed on preparing this accident impact analysis, all accident information was derived from existing safety documentation that has been prepared for SRS waste management facilities. A list of facilities to include in the accident impact analysis was provided as input by the Savannah River Technology Section. The accident impact analyses include existing SRS waste management facilities as well as proposed facilities. Safety documentation exists for all existing and many of the proposed facilities. Information was extracted from this existing documentation for this impact analysis. There are a few proposed facilities for which safety analyses have not been prepared. However, these facilities have similar processes to existing facilities and will treat, store, or dispose of the same type of material that is in existing facilities; therefore, the accidents can be expected to be similar

  17. China's status and strategy of radioactive waste management

    International Nuclear Information System (INIS)

    Bi Decai

    2001-01-01

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

  18. Implementation of the obligations of the joint Convention on the safety of spent fuel management and on the safety of radioactive waste management - Sixth national report of Switzerland in accordance with article 32 of the Convention

    International Nuclear Information System (INIS)

    2017-10-01

    This comprehensive, illustrated Sixth Swiss National Report in accordance with Article 32 of the Convention on Nuclear Safety reports on Swiss policies and practices with respect to the management of various categories of radioactive waste. The scope of application is looked at. This includes reprocessing and the processing of naturally occurring radioactive materials. Further sections of the report present notes on inventories and lists, along with a review of legislative and regulatory systems. Other general safety provisions discussed include the responsibility of licence holders, human and financial resources, quality assurance, operational radiation protection, emergency preparedness and decommissioning. Safety aspects of spent fuel management and the design, location and operation of disposal facilities are discussed. General efforts to improve safety are looked at, as is the global transport of wastes. An annex provides information on national laws, regulations and associated guidelines

  19. Waste Management Program. Technical progress report, October-December 1982

    International Nuclear Information System (INIS)

    1983-07-01

    This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant and offplant participants. The studies on environmental and safety assessments, in situ storage or disposal, waste from development and characterization, process and equipment development, and low-level waste management are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities

  20. Waste Management Program: Technical progress report, July-December 1985

    International Nuclear Information System (INIS)

    1987-12-01

    This report provides information on operations and development programs relating to the management of radioactive wastes at the Savannah River Plant. Information on environmental and safety assessments, waste form development, and process and equipment development are reported for long-term waste management. 13 refs., 20 figs., 16 tabs

  1. Waste Management Program: Technical progress report, January-June 1985

    International Nuclear Information System (INIS)

    1987-12-01

    This report provides information on operations and development programs relating to the management of radioactive wastes at the Savannah River Plant. Information on environmental and safety assessments, waste form development, and process and equipment development are reported for long-term waste management. 35 refs., 12 figs., 8 tabs

  2. Technical Safety Requirements for the Waste Storage Facilities May 2014

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2014-04-16

    This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

  3. Technical Safety Requirements for the Waste Storage Facilities May 2014

    International Nuclear Information System (INIS)

    Laycak, D. T.

    2014-01-01

    This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

  4. Database basic design for safe management radioactive waste

    International Nuclear Information System (INIS)

    Son, D. C.; Ahn, K. I.; Jung, D. J.; Cho, Y. B.

    2003-01-01

    As the amount of radioactive waste and related information to be managed are increasing, some organizations are trying or planning to computerize the management on radioactive waste. When we consider that information on safe management of radioactive waste should be used in association with national radioactive waste management project, standardization of data form and its protocol is required, Korea Institute of Nuclear Safety(KINS) will establish and operate nationwide integrated database in order to effectively manage a large amount of information on national radioactive waste. This database allows not only to trace and manage the trend of radioactive waste occurrence and in storage but also to produce reliable analysis results for the quantity accumulated. Consequently, we can provide necessary information for national radioactive waste management policy and related industry's planing. This study explains the database design which is the essential element for information management

  5. JYT - Publicly financed nuclear waste management research programme

    International Nuclear Information System (INIS)

    Vuori, S.

    1992-07-01

    The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

  6. JYT - Publicly financed nuclear waste management research programme

    International Nuclear Information System (INIS)

    Vuori, S.

    1993-06-01

    The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

  7. JYT - Publicly financed nuclear waste management research programme

    International Nuclear Information System (INIS)

    Vuori, S.

    1991-07-01

    The nuclear waste management research in Finland is funded both by the state and the utilities (represented in cooperation by the Nuclear Waste Commission of the Finnish power companies). A coordinated research programme (JYT) comprising the publicly financed waste management studies was started in 1989 and continues until 1993. The utilities continue to carry out a parallel research programme according to their main financial and operational responsibility for nuclear waste management. The research programme covers the following main topic areas: (1) Bedrock characteristics, groundwater and repository, (2) Release and transport of radionuclides, (3) Performance and safety assessment of repositories, and (4) Waste management technology and costs

  8. Radioactive waste management and disposal

    International Nuclear Information System (INIS)

    Simon, R.; Orlowski, S.

    1980-01-01

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

  9. The safe management of radioactive waste from mining and milling activities

    International Nuclear Information System (INIS)

    Reisenweaver, D.W.

    2002-01-01

    The IAEA is developing a Safety Guide for the management of radioactive waste from the mining and milling of uranium and thorium ores. This new Safety Guide will provide information that has been requested by Member States concerning the safe management of these wastes. The guide includes some new concepts, but they are intended to be reasonable and provide appropriate safety conditions for the workers, general public and the environment. The Regulatory Authorities of individual countries are responsible for establishing and implementing the regulatory framework through the development of appropriate rules, criteria and guidelines and establishing a licensing framework. The IAEA has issued a number of publications that provide requirements and guidance for the protection of workers, public and the environment. The overall objective and subsidiary principles developed explicitly for the management of radioactive waste should emphasize that the protection of the public from the beginning of operation to post-closure should be considered in its entity from the beginning of the design of the facility. The Safety Guide acknowledges that mining and milling wastes will contain non radiological hazards, in addition to the radiological hazards. The development of the waste management strategy is usually a complex process that aims to achieve a reasonable balance between the often conflicting goals - maximizing risk reduction versus minimizing financial expenditures. The evaluation criteria and procedures used to select the preferred option/and or development of the waste management strategy should be clearly defined and acceptable for the different parties interested in the project. This includes the public. A safety assessment should be performed to indicate how the design of the waste management facilities provides the optimum protection for the workers, public and environment using safety-type indicators. (author)

  10. Nuclear waste management policy in France

    International Nuclear Information System (INIS)

    Lefevre, J.F.

    1983-01-01

    The object of the nuclear waste management policy in France has always been to protect the worker and the public from unacceptable risks. The means and the structures developed to reach this objective, however, have evolved with time. One fact has come out ever more clearly over the years: Nuclear waste problems cannot be considered in a piecemeal fashion. The French nuclear waste management structure and policy aim at just this global approach. Responsibilities have been distributed between the main partners: the waste producers and conditioners, the research teams, the safety authorities, and the long-term waste manager, National Radioactive Waste Management Agency. The main technical options adopted for waste forms are embedding in hydraulic binders, bitumen, or thermosetting resins for low-level waste (LLW) and medium-level waste (MLW), and vitrification for high-level, liquid wastes. One shallow land disposal site for LLW and MLW has been in operation since 1969, the Centre of La Manche. Alpha-bearing and high-level waste will be disposed of by deep geological storage, possibly in granite formations. Further RandD aims mainly at improving present-day practices, developing more durable, long-term, alpha-bearing waste for all solid waste forms and going into all aspects of deep geological disposal characterization

  11. Waste Management Program. Technical progress report, Aporil-June 1983

    Energy Technology Data Exchange (ETDEWEB)

    None

    1984-02-01

    This quarterly report provides current information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant. The studies on environmental and safety assessments, process and equipment development, TRU waste, and low-level waste are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations Program: surveillance and maintenance, waste concentration, low-level effluent waste, tank replacement/waste transfer, and solid waste storage and related activities.

  12. Waste management from reprocessing: a stringent regulatory requirements for high quality conditioned residues

    International Nuclear Information System (INIS)

    Bordier, J. C.; Greneche, D.; Devezeaux, J. G.; Dalcorso, J.

    2000-01-01

    Nuclear waste production and management in France is governed by safety requirements imposed to all operators. French nuclear safety relies on two basic principles: · Responsibility of the nuclear operator, which expands to waste generated, · Safety basic objectives issued by national Safety Authority. For a long time the regulatory framework for waste production and management has been satisfactorily applied and has benefited to each actor of the process. LLW/MLW and HLW nuclear waste are currently conditioned in safe matrices or packages either likely to be disposed in surface repositories or designed with the intention to be disposed underground according to their radioactive content. France is looking into the case of VLLW and has already carried out a design for future disposal, the design being in the pipe. Other types of waste (i. e. radium bearing waste, graphite, and tritium content waste) are also considered in the whole framework of French waste management. (author)

  13. Environmental development plan. LWR commercial waste management

    International Nuclear Information System (INIS)

    1980-08-01

    This Environmental Development Plan (EDP) identifies the planning and managerial requirements and schedules needed to evaluate and assess the environmental, health and safety (EH and S) aspects of the Commercial Waste Management Program (CWM). Environment is defined in its broadest sense to include environmental, health (occupational and public), safety, socioeconomic, legal and institutional aspects. This plan addresses certain present and potential Federal responsibilities for the storage, treatment, transfer and disposal of radioactive waste materials produced by the nuclear power industry. The handling and disposal of LWR spent fuel and processed high-level waste (in the event reprocessing occurs) are included in this plan. Defense waste management activities, which are addressed in detail in a separate EDP, are considered only to the extent that such activities are common to the commercial waste management program. This EDP addresses three principal elements associated with the disposal of radioactive waste materials from the commercial nuclear power industry, namely Terminal Isolation Research and Development, Spent Fuel Storage and Waste Treatment Technology. The major specific concerns and requirements addressed are assurance that (1) radioactivity will be contained during waste transport, interim storage or while the waste is considered as retrievable from a repository facility, (2) the interim storage facilities will adequately isolate the radioactive material from the biosphere, (3) the terminal isolation facility will isolate the wastes from the biosphere over a time period allowing the radioactivity to decay to innocuous levels, (4) the terminal isolation mode for the waste will abbreviate the need for surveillance and institutional control by future generations, and (5) the public will accept the basic waste management strategy and geographical sites when needed

  14. Answers to questions on National Report of the Slovak Republic. Compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. October 2003

    International Nuclear Information System (INIS)

    2003-10-01

    Slovakia is pleased to present to the State Parties of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management the Answers to questions received on the National Report of the Slovak Republic compiled according to the terms of the Joint Convention (April 2003). Slovakia is ready to provide additional explanations to these Answers during the 1 st Review Meeting. In the Annexes the 254/1994 Coll. LL. Act of the National Council of the Slovak Republic of 25 August 1994 on State Fund of Decommissioning of Nuclear Installations and Handling of Spent Nuclear Fuels and Nuclear Wastes is included

  15. The IAEA's high level radioactive waste management programme

    International Nuclear Information System (INIS)

    Saire, D.E.

    1994-01-01

    This paper presents the different activities that are performed under the International Atomic Energy Agency's (IAEA) high level radioactive waste management programme. The Agency's programme is composed of five main activities (information exchange, international safety standards, R ampersand D activities, advisory services and special projects) which are described in the paper. Special emphasis is placed on the RADioactive WAste Safety Standards (RADWASS) programme which was implemented in 1991 to document international consensus that exists on the safe management of radioactive waste. The paper also raises the question about the need for regional repositories to serve certain countries that do not have the resources or infrastructure to construct a national repository

  16. The radioactive waste management conference

    International Nuclear Information System (INIS)

    Fareeduddin, S.; Hirling, J.

    1983-01-01

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

  17. 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.)

  18. DOE guidelines for management of radioactive waste - historical perspectives

    International Nuclear Information System (INIS)

    Kluk, A.F.; Neal, R.M.

    1996-01-01

    From the beginning of the Manhattan Project in 1942 through the signing of the Atomic Energy Act (AEA) in 1946 and its reenactment in 1954, new policies and techniques began to evolve for managing waste produced in the manufacture of nuclear weapons. Even in the early days of war-time urgency, public health and safety were the major considerations in managing waste from this new technology. The Atomic Energy Commission (AEC), which took over from the Manhattan Engineer District (MED) in 1947, established initial waste category management guidelines (high level waste stored in tanks, solid low level waste disposed of primarily in trenches, and liquid waste released to ponds, cribs, and pits) based on the management concepts developed by the MED. The AEC and its successor agencies managed radioactive waste in a manner consistent with existing industrial health and safety requirements of that era. With the formation of the Department of Energy (DOE) in September 1977, techniques and internal requirements were already in place or being established that, in some cases, were more protective of human health and the environment than existing legislation and environmental standards. With the transition to environmental cleanup of former DOE weapons production facilities, new and revised guidelines were created to address hazardous and radioactive mixed waste, waste minimization, and recycling. This paper reviews the waste management guidelines as they have evolved from the MED through the resent time

  19. Development of a quality assurance safety assessment database for near surface radioactive waste disposal

    International Nuclear Information System (INIS)

    Park, J. W.; Kim, C. L.; Park, J. B.; Lee, E. Y.; Lee, Y. M.; Kang, C. H.; Zhou, W.; Kozak, M. W.

    2003-01-01

    A quality assurance safety assessment database, called QUARK (QUality Assurance program for Radioactive waste management in Korea), has been developed to manage both analysis information and parameter database for safety assessment of Low- and Intermediate-Level radioactive Waste (LILW) disposal facility in Korea. QUARK is such a tool that serves QA purposes for managing safety assessment information properly and securely. In QUARK, the information is organized and linked to maximize the integrity of information and traceability. QUARK provides guidance to conduct safety assessment analysis, from scenario generation to result analysis, and provides a window to inspect and trace previous safety assessment analysis and parameter values. QUARK also provides default database for safety assessment staff who construct input data files using SAGE(Safety Assessment Groundwater Evaluation), a safety assessment computer code

  20. Establishing a national system for radioactive waste management. A publication within the RADWASS programme

    International Nuclear Information System (INIS)

    1995-09-01

    This Safety Standard is intended to cover the requirements for establishing a national system for safe management of radioactive wastes especially, for solid, liquid and airborne radioactive waste resulting from the nuclear fuel cycle. The main text of the Safety Standard is organized as follows: (a) Section 2 sets out the main objective for radioactive waste management and the principle on which radioactive waste management policy and strategies should be based; (b) Section 3 presents the basic components of a national framework for radioactive waste management; (c) Section 4 outlines the responsibilities of the Member State, the regulatory body and the waste generators and operators of radioactive waste management facilities; and (d) Section 5 describes important features of radioactive waste management

  1. Radioactive waste computerized management

    International Nuclear Information System (INIS)

    Communaux, M.; Lantes, B.

    1993-01-01

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

  2. Waste management/waste certification plan for the Oak Ridge National Laboratory Environmental Restoration Program

    International Nuclear Information System (INIS)

    Clark, C. Jr.; Hunt-Davenport, L.D.; Cofer, G.H.

    1995-03-01

    This Waste Management/Waste Certification (C) Plan, written for the Environmental Restoration (ER) Program at Oak Ridge National Laboratory (ORNL), outlines the criteria and methodologies to be used in the management of waste generated during ORNL ER field activities. Other agreed upon methods may be used in the management of waste with consultation with ER and Waste Management Organization. The intent of this plan is to provide information for the minimization, handling, and disposal of waste generated by ER activities. This plan contains provisions for the safe and effective management of waste consistent with the U.S. Environmental Protection Agency's (EPA's) guidance. Components of this plan have been designed to protect the environment and the health and safety of workers and the public. It, therefore, stresses that investigation derived waste (IDW) and other waste be managed to ensure that (1) all efforts be made to minimize the amount of waste generated; (2) costs associated with sampling storage, analysis, transportation, and disposal are minimized; (3) the potential for public and worker exposure is not increased; and (4) additional contaminated areas are not created

  3. The management of radioactive wastes; La gestion des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    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.)

  4. Sweden's fourth national report under the Joint Convention on the safety of spent fuel management and the safety of radioactive waste management. Swedish implementation of the obligations of the Joint Convention

    International Nuclear Information System (INIS)

    2011-01-01

    Sweden signed Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) September 29, 1997. Sweden ratified the Joint Convention about two years later and is a Contracting Party to the Joint Convention since July 29, 1999. The Joint Convention entered into force on June 18, 2001. Each member nation having ratified the Joint Convention (Contracting Party) is obligated to prepare a National Report covering the scope of the Joint Convention and subject it to review by other Contracting Parties at Review Meetings held in Vienna, Austria. Sweden participated in the First Review Meeting in November 2003, the Second Review Meeting in May 2006 and the Third Review Meeting in May 2009. This report is the fourth Swedish National Report under the Joint Convention. This report satisfies the requirements of the Joint Convention for reporting on the status of safety at spent fuel and radioactive waste management facilities within Sweden. It constitutes an updated document with basically the same structure as the previous national reports under the terms of the Joint Convention and reflects developments in Sweden through December 2010. It will be subject to review at the Fourth Review Meeting of the Contracting Parties in Vienna, Austria, in May 2012

  5. System approach for the management of radioactive waste

    International Nuclear Information System (INIS)

    Fearnley, I.G.

    1997-01-01

    An integrated approach to Waste Management and Decommissioning, which takes account of the lifetime implications (safety, dose uptake, discharges and cost) is an important strategic process in forward planning. This type of approach is particularly relevant when making decisions concerning waste minimisation and segregation, packaging and surface storage of high and intermediate level waste in advance of the existence of disposal facilities. Such a systematic approach forms an integral part of a process which enable progress to be assessed and plans to be updated in response to changing demands upon business operations and can continually be applied to waste management policy and to optimise the detailed waste management plans. (author)

  6. Some points in legal regulation of radioactive waste management

    International Nuclear Information System (INIS)

    Tikhankin, Anatoly; Levin, Alexander

    1999-01-01

    In Russia, the system of the legal acts regulating radioactive waste management is now in progress. Development of the federal norms and regulations on the use of atomic energy is a responsibility of Gosatomnazdor. This presentation describes in detail the work done by Gosatomnadzor in 1997/1998 on the development of the legal documents regulating the management of radioactive waste and spent nuclear material. A document of special importance is ''Burial of Radioactive Wastes. Principles, Criteria and Basic Safety Requirements''. This is discussed in some detail. For all stages of radioactive waste management, safety criteria for population and personnel are set up in strict analogy with current legislation for any other type of radiological hazard. A combined, or hybrid, safety criterion is suggested for estimation of long-term safety of radioactive waste repository systems, for the period upon termination of the established administrative monitoring after closing the repository. A dose criterion is accepted for normal radiation exposure and a risk criterion for potential radiation exposure. The safety of radioactive waste repository should be ensured by means of graded safeguard throughout the entire period of burial. Graded safeguard is based on independent barriers on the way of ionising radiation and emission of radioactive substances into the environment and protection and maintenance of these barriers. Examples show how the provisions of the document are applied in practice in the permafrost area of Russia. Permafrost soil has low water permeability, which is significant because underground water is the main transport medium in case of a leakage from a repository

  7. Progress towards a convention on the safe management of radioactive waste

    International Nuclear Information System (INIS)

    Webb, G.A.M.; Jankowitsch, O.

    1996-01-01

    The Convention on Nuclear Safety was prepared during the period 1992 to 1994 and after consideration by a diplomatic conference in June 1994 was opened for signature at the general conference of the IAEA in September 1994. The matter of the safety of radioactive waste was discussed many times during the development of the convention but it was eventually decided to restrict the coverage to matters concerned with nuclear safety of land-based civil nuclear power plants and those aspects of radioactive waste management directly connected with and carried out on the same site as the power plant. In the preamble to the convention, however, item (ix) affirms 'the need to begin promptly the development of an international convention on the safety of radioactive waste management as soon as the ongoing process to develop waste management safety fundamentals has resulted in broad international agreement'. In September 1994, the general conference of the IAEA also passed a resolution inviting the board of governors and the director general to commence preparations for a convention on the safety of radioactive waste management. The director general therefore organized a preparatory meeting of experts from member states to discuss the basic concepts and the possible scope of such a convention and to examine working methods and the procedures for its preparation. This meeting which took place in February 1995 prepared a paper entitled 'Inventory of Issues Raised' and proposed that the appropriate mechanism would be the setting up of an open-ended group of legal and technical experts to prepare the convention. The Safety Series document at the fundamentals level on the principles of radioactive waste management was approved by the Board of Governors in March 1995 and all the initial preconditions for starting work on the convention were then fulfilled. (author)

  8. Guide to radioactive waste management literature

    International Nuclear Information System (INIS)

    Houser, B.L.; Holoway, C.F.; Madewell, D.G.

    1977-10-01

    Increased public concern about radioactive waste management has called attention to this aspect of the nuclear fuel cycle. Socio-economic planning and technical development are being undertaken to assure that such wastes will be managed safely. This Guide to Radioactive Waste Management Literature has been compiled to serve scientists, engineers, administrators, legislators, and private citizens by directing them to sources of information on various aspects of the subject. References were selected from about 6000 documents on waste management in the computerized information centers in Oak Ridge. The documents were selected, examined, indexed, and abstracted between 1966-1976 by several knowledgeable indexers, principally at the Nuclear Safety Information Center. The selected references were further indexed and classified into 12 categories. Each category is discussed in enough detail to give some understandng of present technology in various phases of waste management and some appreciation of the attendant issues and problems. The bibliographic part of this guide exists in computerized form in the Health Physics Information System and is available through the Oak Ridge Information Center Complex for searching from remote terminals

  9. Guide to radioactive waste management literature

    Energy Technology Data Exchange (ETDEWEB)

    Houser, B.L.; Holoway, C.F.; Madewell, D.G.

    1977-10-01

    Increased public concern about radioactive waste management has called attention to this aspect of the nuclear fuel cycle. Socio-economic planning and technical development are being undertaken to assure that such wastes will be managed safely. This Guide to Radioactive Waste Management Literature has been compiled to serve scientists, engineers, administrators, legislators, and private citizens by directing them to sources of information on various aspects of the subject. References were selected from about 6000 documents on waste management in the computerized information centers in Oak Ridge. The documents were selected, examined, indexed, and abstracted between 1966-1976 by several knowledgeable indexers, principally at the Nuclear Safety Information Center. The selected references were further indexed and classified into 12 categories. Each category is discussed in enough detail to give some understandng of present technology in various phases of waste management and some appreciation of the attendant issues and problems. The bibliographic part of this guide exists in computerized form in the Health Physics Information System and is available through the Oak Ridge Information Center Complex for searching from remote terminals.

  10. Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Second national report on implementation by France of its obligations under the convention

    International Nuclear Information System (INIS)

    2005-09-01

    The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, hereinafter referred to as the 'Joint Convention', is the result of international discussions which took place following adoption of the Convention on Nuclear Safety in 1994. France signed the Joint Convention on 29 September 1997, the first day on which it was opened for signature, during the General Conference of the International Atomic Energy Agency (IAEA). France approved it on 22 February 2000 and deposited the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in international action to reinforce nuclear safety and it considers the Joint Convention to be a key step in this direction. The fields it covers have for a long time been part of the French approach to nuclear safety. This report, which is the second of its kind, is published in accordance with article 32 of the Joint Convention and presents the measures taken by France to meet each of the obligations set out in the Convention. The facilities and radioactive materials which are the subject of this Convention are of widely differing types and in France are covered by different regulatory authorities, as explained in section E of this report. Above a certain radioactive content threshold, a facility is referred to as a 'basic nuclear installation' (BNI) and is placed under the authority of the Nuclear Safety Authority. This category includes in particular all facilities receiving spent fuel (reactors, reprocessing plants, storage facilities, etc.), most of the facilities whose 'main purpose is management of radioactive waste' as defined by this Convention, and a large number of facilities containing radioactive waste, even if management of the waste is not their primary objective: the total number of all types of BNIs is about 125 facilities. Below this threshold, an

  11. Progress report on safety research on high-level waste management for the period April 1989 to March 1990

    International Nuclear Information System (INIS)

    Muraoka, Susumu; Senoo, Muneaki; Kobayashi, Yoshii

    1991-02-01

    Research on high-level waste management at the Engineered Barrier Materials Laboratory, Environmental Geochemistry Laboratory and Environmental Radiochemistry Laboratory of the Department of Environmental Safety Research, JAERI in the fiscal year of 1989 are described. The topics are as follows: 1) As for waste forms and engineered barrier material, performance assessment studies on glass and ceramic forms, and corrosion test of carbon steel were continued. 2) In the safety evaluation study for geological disposal, chemical behavior of nuclide in water, nuclide migration and retardation in geosphere were studied. New microspectrometers was developed to analyze the chemical form in rocks. 3) Distribution and migration of uranium in uranium ore were examined as a natural analogue study. (author)

  12. Progress report on safety research on high-level waste management for the period April 1991 to March 1992

    International Nuclear Information System (INIS)

    Muraoka, Susumu; Senoo, Muneaki; Kobayashi, Yoshii

    1993-03-01

    Research on high-level waste management at the Engineered Barrier Materials Laboratory, Environmental Geochemistry Laboratory and Environmental Radiochemistry Laboratory of the Department of Environmental Safety Research, JAERI in the fiscal year of 1991 are described. The topics are as follows: 1) As for waste forms and engineered barrier material, performance assessment studies on glass, ceramic and buffer materials were carried out. 2) In the safety evaluation study for geological disposal, behavior of radionuclide in deep underground water, nuclide migration in-situ and natural groundwater flow system were studied. 3) Changes in layer charge of smectite, alteration of uranium mineral and uranium fixation in uranium ore were examined as a natural analogue study. (author)

  13. Safety related aspects of ultimate disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Goemmel, R.

    1992-01-01

    Solutions and questions related to nuclear waste management are presented. In particular, long-term safety of repositories in Germany and Sweden is considered, with special attention being paid to methods of detection, geotechnical barriers and post-operational phase of salt dome repositories, and conditioning of wastes to make them fit for ultimate disposal. (DG) [de

  14. Recent Trends In The Methods Of Safety Assessment Of Rad Waste Treatment And Disposal

    International Nuclear Information System (INIS)

    Mahmoud, N.S.

    2012-01-01

    Radioactive waste management system involves a huge variety of processes and activities. This includes; collection and segregation, pretreatment, treatment, conditioning, storage and finally disposal. To assure the safety of the different facility of each step in the waste management system, the operator should prepare a safety analysis report to be assessed by the national regulatory body. The content of the safety analysis report must include all data about the site, facility design, operational phase, waste materials, and safety assessment methodologies. Safety assessment methodologies are iterative processes involving site-specific, prospective modeling evaluations of the pre-operational, operational, and post-closure time in case of disposal facilities. The safety assessment focuses primarily on a decision about compliance with performance objectives, rather than the much more difficult problem of predicting actual radiological impacts on the public at far future times. The recent organization processes of the safety assessment are improved by the ISAM working group from IAEA for waste disposal site. These safety assessment methodologies have been modified within SADRWMS IAEA project for the establishment of safety methodologies for the pre-disposal facilities (treatment and storage facilities) and the disposal site.

  15. Overview of management of low and intermediate level radioactive wastes at the Institute for Nuclear Research for to save management of the waste from decommissioning of nuclear facilities

    International Nuclear Information System (INIS)

    Bujoreanu, D.; Bujoreanu, L.

    2010-01-01

    The national policy of radioactive waste management fully complies with the international requirements established by 'Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management and with the EURATOM treaty, directives, recommendations and policy of radioactive waste management promoted at the level of the European Union. The Institute for Nuclear Research Pitesti (INR) has its own Radwaste Treatment Plant. The object of activity is to treat and condition radioactive waste resulted from the nuclear facility. According to the National Nuclear Program, the institute is the main support for implementation of the methods and technologies for conditioning and disposal of radioactive waste generated by Cernavoda NPP. For all these, in accordance with the Governmental order no. 11/2003, INR shall must prepare and manage the decommissioning projects of its own facilities and to upgrade the facilities for the management of the radioactive waste resulting from decommissioning activities. (authors)

  16. HSE policy on decommissioning and radioactive waste management at licensed nuclear sites

    International Nuclear Information System (INIS)

    Bacon, M.

    1997-01-01

    In the UK, radioactive waste management and decommissioning on a licensed nuclear is regulated by the Health and Safety Executive. The same legislative framework used for operating nuclear power stations is also applied to radioactive waste management and decommissioning activities. This provides a continuous but flexible safety regime until there is no danger from ionizing radiations. The regulatory policy is discussed, taking into account the implications of the 1995 White Paper reviewing radioactive waste management policy. For both radioactive waste management and decommissioning the key element of HSE policy is the need for strategic planning. This should ensure that problems are not allowed to build up and to demonstrate that, taking into account all factors, the proposed actions are the optimum in terms of safety. There is a presumption in HSE's policy towards disposal of radioactive waste as soon as possible where disposal routes exist. Where long-term storage is necessary passively safe forms are preferred over those requiring continuous monitoring or frequent intervention. (author)

  17. Improvement of the safety regulations in the management of radioactive waste accumulated in the liquid radioactive waste water basins of the PO 'Majak' (Ozersk), the Siberian Chemical Plant (Seversk) and the Mining-Chemical Plant (Zheleznogorsk)

    International Nuclear Information System (INIS)

    Vishnevski, Y.G.; Kislov, A.I.; Irushkin, V.M.

    2002-01-01

    One of the most important problems of radiation safety in Russia is the decommissioning of the liquid radioactive waste water basins of the PO 'Majak' (Ozersk), Siberian Chemical Plant (Seversk) and Mining-Chemical Plant (Zheleznogorsk). The liquid radioactive waste water basins were constructed in 1950-1960 for the collection and storage of liquid waste from the radiochemical plants. The potential hazards of the liquid in the radioactive waste water basins are: migration of radionuclides into the soil of the liquid radioactive waste water basin floors; wind-induced carry-over of radionuclides from the liquid radioactive waste water basins; hazards (radiation included) to the environment and population arising in case physical barriers and hydraulic structures are damaged; and criticality hazards. The classification of the liquid radioactive waste water basins were developed based on the collection and analyzes of the information on liquid radioactive waste water basin characteristics and the method of multicriterion expert assessment of potential hazards. Three main directions for the improvement of safety regulation in the management of radioactive waste accumulated in the liquid radioactive waste water basins were defined: 1. Common directions for the improvement of safety regulation in the area of rehabilitation of the territories contaminated with radioactive substances. 2. Common directions for the improvement of safety regulation in the area of rehabilitation of the territories, such as the liquid radioactive waste water basins. 3. Special directions for the regulatory activities in the area of operation and decommissioning of the liquid radioactive waste water basins of the PO 'Majak' (Ozersk), Siberian Chemical Plant (Seversk) and Mining-Chemical Plant (Zheleznogorsk). As a result, concrete recommendations on safety regulation for the management of radioactive waste accumulated in the water basins were developed. (author)

  18. Safe management of radioactive waste in Ghana

    International Nuclear Information System (INIS)

    Glover, E.T.; Fletcher, J.J.

    2000-01-01

    The Ghana Atomic Energy Commission was established in 1963 by an Act of Parliament, Act 204 for the Promotion, Development and Peaceful Application of Nuclear Techniques for the Benefit of Ghana. As in many developing countries the use of nuclear application is growing considerably in importance within the national economy. The Radiation Protection Board was established as the national regulatory authority and empowered by the Radiation Protection Instrument LI 1559 (1993). The above regulations, Act 204 and LI 1559 provided a minimum legal basis for regulatory control of radioactive waste management as it deals with waste management issues in a very general way and is of limited practical use to the waste producer. Hence the National Radioactive Waste Management Centre was established in July 1995 to carry out waste safety operations in Ghana. This paper highlights steps that have been taken to develop a systemic approach for the safe management of radioactive waste in the future and those already in existence. (author)

  19. Feed Materials Production Center Waste Management Plan

    International Nuclear Information System (INIS)

    Watts, R.E.; Allen, T.; Castle, S.A.; Hopper, J.P.; Oelrich, R.L.

    1986-01-01

    In the process of producing uranium metal products used in Department of Energy (DOE) defense programs at other DOE facilities, various types of wastes are generated at the Feed Materials Production Center (FMPC). Process wastes, both generated and stored, are discussed in the Waste Management Plan and include low-level radioactive waste (LLW), mixed hazardous/radioactive waste, and sanitary/industrial waste. Scrap metal waste and wastes requiring special remediation are also addressed in the Plan. The Waste Management Plan identifies the comprehensive programs developed to address safe storage and disposition of all wastes from past, present, and future operations at the FMPC. Waste streams discussed in this Plan are representative of the waste generated and waste types that concern worker and public health and safety. Budgets and schedules for implementation of waste disposition are also addressed. The waste streams receiving the largest amount of funding include LLW approved for shipment by DOE/ORO to the Nevada Test Site (NTS) (MgF 2 , slag leach filter cake, and neutralized raffinate); remedial action wastes (waste pits, K-65 silo waste); thorium; scrap metal (contaminated and noncontaminated ferrous and copper scrap); construction rubble and soil generated from decontamination and decommissioning of outdated facilities; and low-level wastes that will be handled through the Low-Level Waste Processing and Shipping System (LLWPSS). Waste Management milestones are also provided. The Waste Management Plan is divided into eight major sections: Introduction; Site Waste and Waste Generating Process; Strategy; Projects and Operations; Waste Stream Budgets; Milestones; Quality Assurance for Waste Management; and Environmental Monitoring Program

  20. EVALUATION OF BIOMEDICAL WASTE MANAGEMENT PRACTICES IN MULTI-SPECIALITY TERTIARY HOSPITAL

    Directory of Open Access Journals (Sweden)

    Shalini Srivastav

    2010-06-01

    Full Text Available Background: Biomedical Waste (BMW, collection and proper disposal has become a significant concern for both the medical and the general community The scientific “Hospital waste Management “is of vital importance as its improper management poses risks to the health care workers ,waste handlers patients, community in general and largely the environment. Objectives: (i To assess current practices of Bio-medical Waste management including generation, collection, transportation storage, treatment and disposal technologies in tertiary health care center. (ii To assess health andsafetypracticesfor the health care personnel involved in Bio-Medical waste Management. Materials and Methods: Waste management practices in tertiary care-centre was studied during May 2010 June 2010. The information/data regarding Bio-Medical Waste Management practices and safety was collected by way of semi structured interview, proforma being the one used for WASTE AUDITING QUESTIONNAIRE. The information collected was verified by personal observations of waste management practices in each ward of hospital. Results : SRMS-IMS generates 1. 25Kgs waste per bed per day and maximum waste is generated in wards. The institute has got separate color coded bins in each ward for collection of waste but segregation practices needs to be more refined. The safety measures taken by health care workers was not satisfactory it was not due to unavailability of Personal protective measures but because of un-awareness of health hazards which may occur due to improper waste management practices. Thus it is concluded that there should be strict implementation of a waste management policy set up in the institute, training and motivation must be given paramount importance to meet the current needs and standard of bio-medical waste management.

  1. Promethean ethics and nuclear waste management

    International Nuclear Information System (INIS)

    Brown, J.B. Jr.

    1985-01-01

    The proposed safety standards for commercial nuclear waste management are examined and shown to be Promethean; that is, they are shown to be dominated by time and care for future generations. Some of the long-term environmental impact assessment methodologies being developed in commmercial waste management are examined. They are aimed at demonstrating repository isolation integrity over a 10,000-year period or 300 human generations, a truly Promethean period of examination unknown in other 20th Century technical analyses

  2. Radioactive waste management at nuclear power plant Cernavoda

    International Nuclear Information System (INIS)

    Raducea, D.

    2002-01-01

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

  3. Waste Management Program. Technical progress report, July-December, 1984

    International Nuclear Information System (INIS)

    1986-10-01

    This report provides information on operations and development programs for the management of radioactive wastes from operation of the Savannah River Plant and offplant participants. The studies on environmental and safety assessments, other support, in situ storage or disposal, waste form development and characterization, process and equipment development, and the Defense Waste Processing Facility are a part of the Long-Term Waste Management Technology Program. The following studies are reported for the SR Interim Waste Operations: tank farm operation, inspection program, burial ground operations, and waste transfer/tank replacement

  4. Public acceptance in radioactive waste management

    International Nuclear Information System (INIS)

    Diaconu, Stela; Covreag, Ilinca

    2008-01-01

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

  5. Nuclear waste management. Quarterly progress report, April-June 1979

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Powell, J.A. (comps.)

    1979-09-01

    Progress is reported on: decontamination and densification of chop-leach cladding residues; monitoring methods for particulate and gaseous effluents from waste solidification process; TRU waste immobilization; krypton solidification; /sup 14/C and /sup 129/I fixation; waste management system and safety studies; waste isolation safety assessment; well logging instrumentation development for shallow land burial; monitoring and physical characterization of unsaturated zone transport; detection and characterization of mobile organic complexes of fission products; and electropolishing for surface decontamination of metals. 9 figures, 14 tables. (DLC)

  6. Managing Waste Throughout Lean-Green Perspective

    Directory of Open Access Journals (Sweden)

    Lamyaa Mohammed Dawood

    2017-11-01

    Full Text Available Managing waste has been known as a crucial need as it may reduce resource consumption, rigid regulations regarded to the environment and occupational health and safety. Lean and green management are two approaches of management that validate waste. Since performance measures are crucial to improve waste management as its  goals of  to promote the performance of organizations .In this research four primary KPIs have been employed that are significant to lean-green management; operational, environmental, economic and social performance factors, subdivided further into sixteen as (Value stream mapping, life cycle assessment,---etc. Also in this research   determination and ranking of these performance measures and their influence on waste minimization is conducted. Interpretive Structural Modeling (ISM methodology is applied to the classification of Key Performance Indicators (KPIs according to the priority of their importance and the correlation between them and their impact to waste minimization. Cronbach’s Alpha coefficient is employed  to assess the reliability of performance measures to minimize waste, and increase customer  satisfaction.  Results showed that Al-Kufa Cement plant has bad overall performance toward lean green waste management perspective. The highest individual score is for operational performance (6.6 rated as medium. But  the lowest individual score is for economic performance [very bad (2.0].   

  7. Medical Waste Management in Community Health Centers.

    Science.gov (United States)

    Tabrizi, Jafar Sadegh; Rezapour, Ramin; Saadati, Mohammad; Seifi, Samira; Amini, Behnam; Varmazyar, Farahnaz

    2018-02-01

    Non-standard management of medical waste leads to irreparable side effects. This issue is of double importance in health care centers in a city which are the most extensive system for providing Primary Health Care (PHC) across Iran cities. This study investigated the medical waste management standards observation in Tabriz community health care centers, northwestern Iran. In this triangulated cross-sectional study (qualitative-quantitative), data collecting tool was a valid checklist of waste management process developed based on Iranian medical waste management standards. The data were collected in 2015 through process observation and interviews with the health center's staff. The average rate of waste management standards observance in Tabriz community health centers, Tabriz, Iran was 29.8%. This case was 22.8% in dimension of management and training, 27.3% in separating and collecting, 31.2% in transport and temporary storage, and 42.9% in sterilization and disposal. Lack of principal separation of wastes, inappropriate collecting and disposal cycle of waste and disregarding safety tips (fertilizer device performance monitoring, microbial cultures and so on) were among the observed defects in health care centers supported by quantitative data. Medical waste management was not in a desirable situation in Tabriz community health centers. The expansion of community health centers in different regions and non-observance of standards could predispose to incidence the risks resulted from medical wastes. So it is necessary to adopt appropriate policies to promote waste management situation.

  8. The IAEA Promotes the Application of Safety Standards and Best Practices for the Management of Radioactive Waste

    International Nuclear Information System (INIS)

    2014-01-01

    The IAEA works to promote a high level of safety as it facilitates peaceful uses of nuclear energy worldwide. The IAEA’s Statute authorizes it to establish or adopt standards of safety for protection of health and minimization of danger to life and property, and to provide for the application of these standards. The Statute also mandates the IAEA to foster the exchange of scientific and technical information to facilitate the peaceful uses of atomic energy. To this end, the IAEA develops safety standards on different topics, including on the safety of radioactive waste management. These standards, issued in the IAEA Safety Standards Series, reflect an international consensus on what constitutes a high level of safety for protecting people from harmful effects of ionizing radiation and protecting the environment

  9. The ETSON study on treatment processes for the sustainable management of radioactive waste

    International Nuclear Information System (INIS)

    Besnus, Francois; Metcalf, Phil; Wasselin-Trupin, Virginie; Pfingsten, Wilfred; Smidts, Olivier; Miksova, Jitka; Tokaresvski, Oleksei

    2016-01-01

    ETSON (European Technical Safety Organisation Network): • European association of nuclear assessment bodies; • Objective: - develop and promote best practice in nuclear safety assessment; - foster the convergence of technical nuclear safety practices within the EU and beyond; - assist with planning of nuclear safety research programmes; - facilitate the application of the European directives on nuclear, radiation and radioactive waste and spent fuel safety. • ETSON Activities: - forum for voluntary exchange on both analyses and R&D in the fields of nuclear, radiation and radioactive waste safety; - Issue technical and scientific opinions; - 13 expert groups; one dedicated to Waste management and decommissioning issues (WM&D Group); • WM&D work programme: - Elaborate a common position on decommissioning strategies; - Prepare elements for technical guidance on the operational safety of underground disposal facilities; - Organise an international workshop on sustainable waste management processes prior to disposal

  10. Safety of radioactive waste management: International conference in Spain seeks board platform of consensus among experts and regulators

    International Nuclear Information System (INIS)

    2000-01-01

    The document gives short information about the Conference on the Safety of Radioactive Waste Management (13-17 March 2000, Cordoba, Spain) organized by the IAEA in cooperation with the European Commission, the World Health Organization, and the Nuclear Energy Agency of the Organization for Economic Co-operation and Development

  11. The safety case for deep geological disposal of radioactive waste

    International Nuclear Information System (INIS)

    Kwong, Gloria

    2014-01-01

    The concept of a 'safety case' for a deep geological repository for radioactive waste was first introduced by the NEA Expert Group on Integrated Performance Assessment (IPAG). It was further developed in the NEA report entitled Confidence in the Long-term Safety of Deep Geological Repositories (1999), and since then it has been taken up in international safety standards as promulgated by the International Atomic Energy Agency (IAEA, 2006, 2011) and more recently in recommendations by the International Commission on Radiological Protection on the application of the system of radiological protection in geological disposal (ICRP, 2013). Many national radioactive waste disposal programmes and regulatory guides are also applying this concept. The NEA has used the safety case as a guide in several international peer reviews of national repository programmes and safety documentation. In Europe, the EU Directive 2011/70/ Euratom (EU, 2011) establishes a framework to ensure responsible and safe management of spent fuel and radioactive waste by member states that, inter alia, requires a decision-making process based on safety evidence and arguments that mirror the safety case concept. In 2007, the NEA, the IAEA and the European Commission (EC) organised a symposium on Safety Cases for the Deep Disposal of Radioactive Waste: Where Do We Stand? Since this time, however, there have been some major developments in a number of national geological disposal programmes and significant experience in preparing and reviewing cases for the operational and long-term safety of proposed and operating geological repositories. A symposium on The Safety Case for Deep Geological Disposal of Radioactive Waste: 2013 State of the Art was thus organised to assess developments since 2007 in the practice, understanding and roles of the safety case, as applied internationally at all stages of repository development, including the interplay of technical, regulatory and societal issues. The symposium

  12. Radioactive waste management in Brazil: a realistic view

    International Nuclear Information System (INIS)

    Heilbron Filho, Paulo Fernando Lavalle; Perez Guerrero, Jesus Salvador; Xavier, Ana Maria

    2014-01-01

    The objective of this article is to present a realistic view of the main issues related to the management of radioactive waste in Brazil as well as a comprehensive picture of the regulatory waste management status in the country and internationally. Technical aspects that must be considered to ensure a safe construction of near surface disposal facilities for radioactive waste of low and medium levels of radiation are addressed. Different types of deposits, the basic regulatory issues involving the licensing of these facilities, the development of a financial compensation model for the Brazilian Municipalities where deposits are to be placed, the importance of the participation of the scientific community and society in the process of radioactive waste site selection and disposal, guidance for the application of the basic requirements of safety and radiation protection, the general safety aspects involved and the current actions for the disposal of radioactive waste in Brazil are highlighted. (author)

  13. Radioactive waste management in Brazil: a realistic view

    Energy Technology Data Exchange (ETDEWEB)

    Heilbron Filho, Paulo Fernando Lavalle; Perez Guerrero, Jesus Salvador, E-mail: paulo@cnen.gov.br, E-mail: jperez@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Xavier, Ana Maria, E-mail: axavier@cnen.gov.br [Comissao Nacional de Energia Nuclear (ESPOA/CNEN-RS), Porto Alegre, RS (Brazil)

    2014-07-01

    The objective of this article is to present a realistic view of the main issues related to the management of radioactive waste in Brazil as well as a comprehensive picture of the regulatory waste management status in the country and internationally. Technical aspects that must be considered to ensure a safe construction of near surface disposal facilities for radioactive waste of low and medium levels of radiation are addressed. Different types of deposits, the basic regulatory issues involving the licensing of these facilities, the development of a financial compensation model for the Brazilian Municipalities where deposits are to be placed, the importance of the participation of the scientific community and society in the process of radioactive waste site selection and disposal, guidance for the application of the basic requirements of safety and radiation protection, the general safety aspects involved and the current actions for the disposal of radioactive waste in Brazil are highlighted. (author)

  14. Deconstructing the Nature of Safety and Acceptability in Nuclear Fuel Waste Management, Canada

    International Nuclear Information System (INIS)

    Murphy, Brenda L.

    2003-01-01

    Since the Hare report was released in 1977, Canada's nuclear fuel waste management policies have been focused on one option, deep geologic disposal. However, since new legislation, called the Nuclear Fuel Waste Management Act came into force on November 15, 2002, the newly established Nuclear Waste Management Organisation has been mandated to review, over the next three years, not only deep geologic disposal but also to consider a suite of other options including reactor-site and centralised storage, and both above and below ground options. At this point in time, the process for the study and the criteria by which it will be evaluated are still quite unclear. The need for this new approach to NFW management in Canada was highlighted by an Environmental Assessment Panel (EA Panel) report in 1998. This EA Panel reviewed the 1994 environmental impact statement submitted by Atomic Energy Canada Limited (AECL) regarding the concept of deep geologic disposal in the Canadian Shield (Disposal Concept EA). The EA Panel's key conclusion was: From a technical perspective, safety of the AECL concept has been on balance adequately demonstrated for a conceptual stage of development, but from a social perspective, it has not. As it stands, the AECL concept for deep geological disposal has not been demonstrated to have broad public support. The concept in its current form does not have the required level of acceptability to be adopted as Canada's approach for managing nuclear fuel wastes. AECL's study consisted of a review of the deep geologic disposal concept, since no site has yet been selected. It is generally understood that this type of disposal facility, if eventually sited, will be located on the Ontario portion of the Canadian Shield because Ontario power generators own and manage about 90% of Canada's NFW. This key EA Panel conclusion is predicated on the use of two key decision-making criteria - safety and acceptability. This paper reviews and assesses the specific ways

  15. The International Conference on Radioactive Waste Management

    International Nuclear Information System (INIS)

    1983-01-01

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

  16. Nuclear waste management. Quarterly progress report, January-March 1980

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Powell, J.A. (comps.)

    1980-06-01

    Reported are: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, criteria for defining waste isolation, and spent fuel and pool component integrity. (DLC)

  17. The Canadian fuel waste management program

    International Nuclear Information System (INIS)

    McConnell, D.B.

    1986-04-01

    This report is the sixth in the series of annual reports on the research and development program for the safe management and disposal of Canada's nuclear fuel waste. The report summarizes progress in 1984 for the following activities: storage and transportation of used fuel, immobilization of nuclear fuel waste, geotechnical research, environmental research, and environmental and safety assessment. 186 refs

  18. Safe and environmentally sound management of radioactive wastes in India

    International Nuclear Information System (INIS)

    Krishnamoorthy, T.M.; Mishra, U.C.

    1999-09-01

    It was recognised quite early in India's nuclear power programme that the safe management of radioactive waste is vital for its success. An entirely self-sustained fuel cycle based on indigenous resources necessitated evaluation of hazard potential vis-a-vis radioactive wastes generated at different stages of the cycle, starting from mining and milling; fuel fabrication and through the stages of reactor operation and finally spent fuel reprocessing. Emphasis was laid on studies related to impact of radioactivity in the environment and on developing technologies to effectively isolate and contain them. The radiological safety assessment for a radioactive waste management practice is a regulatory mandate and it requires quantitative estimate of the maximum burden to the present and future generation. Safety assessment models are employed to derive this estimate that could be compared with regulatory criteria to ensure the safety of the public. Decades of experience have proved that the present practices are safe, yet there is a constant endeavour to use new technologies to further restrict the releases so that ultimate goal of radioactive waste management should go beyond merely satisfying prevailing regulations. The comprehensive system of waste management, from water generation to its disposal developed in India, is briefly presented in this report. (author)

  19. A system approach for the management of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Fearnley, I.G. [British Nuclear Fuels plc, Warrington, Cheshire (United Kingdom)

    1995-12-31

    An integrated approach to Waste Management and Decommissioning, which takes account of the lifetime implications (safety, dose uptake, discharges and cost) is an important strategic process in forward planning. This type of approach is particularly relevant when making decisions concerning waste minimization and segregation, packaging and surface storage of high and intermediate level waste in advance of the existence of disposal facilities. Such a systematic approach forms an integral part of a process which enables progress to be assessed and plans to be updated in response to changing demands upon business operations and can continually be applied to waste management policy and to optimise the detailed waste management plans. (author)

  20. A system approach for the management of radioactive waste

    International Nuclear Information System (INIS)

    Fearnley, I.G.

    1995-01-01

    An integrated approach to Waste Management and Decommissioning, which takes account of the lifetime implications (safety, dose uptake, discharges and cost) is an important strategic process in forward planning. This type of approach is particularly relevant when making decisions concerning waste minimization and segregation, packaging and surface storage of high and intermediate level waste in advance of the existence of disposal facilities. Such a systematic approach forms an integral part of a process which enables progress to be assessed and plans to be updated in response to changing demands upon business operations and can continually be applied to waste management policy and to optimise the detailed waste management plans. (author)

  1. Policy and practice of radioactive waste management in India

    International Nuclear Information System (INIS)

    Sunder Radzhan, N.S.

    1986-01-01

    The Indian program on radioactive waste management comprising two main variants: engineering subsurface repositories for low- and intermediate-level wastes and deep geological formations for alpha-bearing and high-level wastes (HLW) is presented. One of the problems deals with the matrices with improved properties for HLW inclusion. The other aspect concerns development of management with alpha-emitting radionuclides in HLW. Special attention is paid to the problems of safety

  2. Radioactive wastes. Safety of storage facilities

    International Nuclear Information System (INIS)

    Devillers, Ch.

    2001-01-01

    A radioactive waste storage facility is designed in a way that ensures the isolation of wastes with respect to the biosphere. This function comprises the damping of the gamma and neutron radiations from the wastes, and the confinement of the radionuclides content of the wastes. The safety approach is based on two time scales: the safety of the insulation system during the main phase of radioactive decay, and the assessment of the radiological risks following this phase. The safety of a surface storage facility is based on a three-barrier concept (container, storage structures, site). The confidence in the safety of the facility is based on the quality assurance of the barriers and on their surveillance and maintenance. The safety of a deep repository will be based on the site quality, on the design and construction of structures and on the quality of the safety demonstration. This article deals with the safety approach and principles of storage facilities: 1 - recall of the different types of storage facilities; 2 - different phases of the life of a storage facility and regulatory steps; 3 - safety and radiation protection goals (time scales, radiation protection goals); 4 - safety approach and principles of storage facilities: safety of the isolation system (confinement system, safety analysis, scenarios, radiological consequences, safety principles), assessment of the radiation risks after the main phase of decay; 5 - safety of surface storage facilities: safety analysis of the confinement system of the Aube plant (barriers, scenarios, modeling, efficiency), evaluation of radiological risks after the main phase of decay; experience feedback of the Manche plant; variants of surface storage facilities in France and abroad (very low activity wastes, mine wastes, short living wastes with low and average activity); 6 - safety of deep geological disposal facilities: legal framework of the French research; international context; safety analysis of the confinement system

  3. Waste management bibliography 1979-1981

    International Nuclear Information System (INIS)

    Oakley, D.T.

    1981-10-01

    The Los Alamos National Laboratory is conducting a variety of research and development to ensure the safety of storing and treating all types of radioactive wastes. These activities include the assay and sorting of waste, the interaction of waste with the earth, and the treatment of waste to reduce the volume and mobility of radionuclides in waste. The practical lessons learned from safely storing waste at Los Alamos since the mid-1940s are an ingredient in determining the direction of our research. National waste management programs are structured according to categories of waste, for example, high level, low level, mill tailings, and transuranic. In this bibliography publications are listed since 1979 according to the following disciplines to show the relevance of work to more than one category of waste: summary and overview; material science; environmental studies; geochemistry and geology; waste assay; soil/waste interactions shallow land burial; volume reduction and technology development; and nonradioactive wastes

  4. Safety in the final disposal of radioactive waste. Final report

    International Nuclear Information System (INIS)

    Broden, K.; Carugati, S.; Brodersen, K.

    1997-12-01

    During 1994-1997 a project on the disposal of radioactive waste was carried out as part of the NKS program. The objective of the project was to give authorities and waste producers in the Nordic countries background material for determinations about the management and disposal of radioactive waste. The project NKS/AFA-1 was divided into three sub-projects: AFA-1.1, AFA-1.2 and AFA-1.3. AFA-1.1 dealt with waste characterisation, AFA-1.2 dealt with performance assessment for repositories and AFA-1.3 dealt with Environmental Impact Assessment (EIA). The studies mainly focused on the management of long-lived low- and intermediate-level radioactive waste from research, hospitals and industry. The AFA-1.1 study included an overview on waste categories in the Nordic countries and methods to determine or estimate the waste content. The results from the AFA-1.2 study include a short overview of different waste management systems existing and planned in the Nordic countries. However, the main emphasis of the study was a general discussion of methodologies developed and employed for performance assessments of waste repositories. Some of the phenomena and interactions relevant for generic types of repository were discussed as well. Among the different approaches for the development of scenarios for safety and performance assessments one particular method, the Rock Engineering System (RES), was chosen to be tested by demonstration. The possible interactions and their safety significance were discussed, employing a simplified and generic Nordic repository system as the reference system. New regulations for the inventory of a repository may demand new assessments of old radioactive waste packages. The existing documentation of a waste package is then the primary information source although additional measurements may be necessary. (EG)

  5. Safety in the final disposal of radioactive waste. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Broden, K.; Carugati, S.; Brodersen, K. [and others

    1997-12-01

    During 1994-1997 a project on the disposal of radioactive waste was carried out as part of the NKS program. The objective of the project was to give authorities and waste producers in the Nordic countries background material for determinations about the management and disposal of radioactive waste. The project NKS/AFA-1 was divided into three sub-projects: AFA-1.1, AFA-1.2 and AFA-1.3. AFA-1.1 dealt with waste characterisation, AFA-1.2 dealt with performance assessment for repositories and AFA-1.3 dealt with Environmental Impact Assessment (EIA). The studies mainly focused on the management of long-lived low- and intermediate-level radioactive waste from research, hospitals and industry. The AFA-1.1 study included an overview on waste categories in the Nordic countries and methods to determine or estimate the waste content. The results from the AFA-1.2 study include a short overview of different waste management systems existing and planned in the Nordic countries. However, the main emphasis of the study was a general discussion of methodologies developed and employed for performance assessments of waste repositories. Some of the phenomena and interactions relevant for generic types of repository were discussed as well. Among the different approaches for the development of scenarios for safety and performance assessments one particular method, the Rock Engineering System (RES), was chosen to be tested by demonstration. The possible interactions and their safety significance were discussed, employing a simplified and generic Nordic repository system as the reference system. New regulations for the inventory of a repository may demand new assessments of old radioactive waste packages. The existing documentation of a waste package is then the primary information source although additional measurements may be necessary. (EG) 33 refs.

  6. Process innovations in the management of radioactive wastes

    International Nuclear Information System (INIS)

    Theyyunni, T.K.

    1995-01-01

    Innovative processes and techniques were investigated for their possible application in the management of low, intermediate and high level radioactive wastes. High decontamination, high volume reduction, process simplicity and operational safety are some of the objectives of these investigation. Based on the favourable results, it is hoped that many of these process innovations can be introduced in the waste management schemes with beneficial results. (author)

  7. Hospital waste management and toxicity evaluation: A case study

    International Nuclear Information System (INIS)

    Tsakona, M.; Anagnostopoulou, E.; Gidarakos, E.

    2007-01-01

    Hospital waste management is an imperative environmental and public safety issue, due to the waste's infectious and hazardous character. This paper examines the existing waste strategy of a typical hospital in Greece with a bed capacity of 400-600. The segregation, collection, packaging, storage, transportation and disposal of waste were monitored and the observed problematic areas documented. The concentrations of BOD, COD and heavy metals were measured in the wastewater the hospital generated. The wastewater's toxicity was also investigated. During the study, omissions and negligence were observed at every stage of the waste management system, particularly with regard to the treatment of infectious waste. Inappropriate collection and transportation procedures for infectious waste, which jeopardized the safety of staff and patients, were recorded. However, inappropriate segregation practices were the dominant problem, which led to increased quantities of generated infectious waste and hence higher costs for their disposal. Infectious waste production was estimated using two different methods: one by weighing the incinerated waste (880 kg day -1 ) and the other by estimating the number of waste bags produced each day (650 kg day -1 ). Furthermore, measurements of the EC 50 parameter in wastewater samples revealed an increased toxicity in all samples. In addition, hazardous organic compounds were detected in wastewater samples using a gas chromatograph/mass spectrograph. Proposals recommending the application of a comprehensive hospital waste management system are presented that will ensure that any potential risks hospital wastes pose to public health and to the environment are minimized

  8. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Rummery, T.E.; Rosinger, E.L.J.

    1984-12-01

    The Canadian Nuclear Fuel Waste Management Program is in the fourth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the basic safety and environmental aspects of the concept of isolating immobilized fuel waste by deep underground disposal in plutonic rock. The major scientific and engineering components of the program, namely immobilization studies, geoscience research, and environmental and safety assessment, are described. Program funding, scheduling and associated external review processes are briefly outlined

  9. Comparative techniques for nuclear fuel cycle waste management systems

    International Nuclear Information System (INIS)

    Pelto, P.J.; Voss, J.W.

    1979-09-01

    A safety assessment approach for the evaluation of predisposal waste management systems is described and applied to selected facilities in the light water reactor (LWR) once-through fuel cycle and a potential coprocessed UO 2 -PuO 2 fuel cycle. This approach includes a scoping analysis on pretreatment waste streams and a more detailed analysis on proposed waste management processes. The primary evaluation parameters used in this study include radiation exposures to the public from radionuclide releases from normal operations and potential accidents, occupational radiation exposure from normal operations, and capital and operating costs. On an overall basis, the waste management aspects of the two fuel cycles examined are quite similar. On an individual facility basis, the fuel coprocessing plant has the largest waste management impact

  10. Tank waste remediation system nuclear criticality safety inspection and assessment plan

    International Nuclear Information System (INIS)

    VAIL, T.S.

    1999-01-01

    This plan provides a management approved procedure for inspections and assessments of sufficient depth to validate that the Tank Waste Remediation System (TWRS) facility complies with the requirements of the Project Hanford criticality safety program, NHF-PRO-334, ''Criticality Safety General, Requirements''

  11. The radioactive waste management policy and practice in the Czech Republic

    International Nuclear Information System (INIS)

    Kucerka, M.

    1996-01-01

    In recent period, the new Czech Atomic Law is in the final stage of preparation, and the author expects that Parliament of the Czech Republic will approve it in the first half of the year 1996. Partly the law deals with new distribution of responsibilities among bodies involved in utilization of nuclear energy and ionizing radiation, the state and local authorities. The new provisions include also radioactive waste management activities. These provisions clarify the relations between radioactive waste generators and state, and define explicitly duties of waste generators. One of the most important duties is to cover all expenses for radioactive waste management now and in the future, including radioactive waste disposal and decommissioning of nuclear facilities. The law establishes radioactive waste management and decommissioning funds and the new, on waste generators independent radioactive waste management organization, controlled by state, to ensure the safety of inhabitants and the environment, and a optimization of expenses. Parallel to the preparation of the law, the Ministry of Industry and Trade prepares drafts of a statute of the radioactive waste management organization and its control board, and of the methodology and rules of management the radioactive waste fund. First drafts of these documents are expected to be complete in January 1996. The paper will describe recent practice and policy of the radioactive waste management including uranium mining and milling tailings, amounts of waste and its activities, economical background, and safety. A special attention will be paid to description of expected changes in connection with the new Atomic Law and expected steps and time schedule of reorganization of the radioactive waste management structure in the Czech Republic

  12. Waste management '05; Entsorgung '05

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The pocket book comprises two sections. The first part discusses waste management issues in Germany: Refuse-derived fuels, emission trading, domestic waste management market, separate collecting of the biogenic waste fraction, waste management in Canada, the Belgian system Recupel for electric and electronic scrap, contracting and energy efficiency, treatment of organic waste in the EU, industrial safety, Deutsche Bundesstiftung Umwelt (DBU), funding of environmental projects, recycling and utilisation, renewables in new products, quality assurance. Part 2 contains data and figures of the waste management industry: Waste market, data of waste management organisations, waste volumes of the federal states, disposal and recycling, waste wood, water management, members of the BDE and its regional associations, press departments, European associations, authorities, environmental consulting, research institutions, energy agencies, journals. (uke) [German] Das Taschenbuch gliedert sich in 2 Teile. Der 1. Teile eroertert Themen der Entsorgungswirtschaft in Deutschland: Einsatz von Sekundaerbrennstoffen, Emissionshandel, Abfallwirtschaft im Binnenmarkt, Anspruch auf Beibehaltung der getrennten Bioabfall-Erfassung, Abfallwirtschaft und Abfallentsorgung in Kanade, das belgische System Recupelzur Sammlung und Entsorgungvon Elektro- und Electronik-Altgeraeten, Contracting und Energieeffizienz, Behandlung organische Abfaelle in der EU, Arbeitssicherheit, Deutsche Bundesstiftung Umwelt (DBU) Umweltfoerderung, Kreislaufwirtschaft, Recycling von Stoffstroemen und Einsatz nachwachsender Rohstoffe in neuen Produkten, Qualitaetsicherung. Im 2. Teil werden Daten und Zahlen der Entsorgungswirtschaft zusammengetragen: Abfallmarkt, Wirtschaftsdaten der Unternehmen, Abfallmengen in den Bundeslaendern, Entsorgung und Verwertung, Altholz, Wasserwirtschaft, Mitglieder des BDE und seiner Regionalverbaende, Pressestellen, europaeische Fachverbaende, Behoerden

  13. Nuclear waste management. Quarterly progress report, April-June 1980

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Powell, J.A. (comps.)

    1980-09-01

    The status of the following programs is reported: high-level waste immobilization; alternative waste forms; Nuclear Waste Materials Characterization Center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of fission products in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; systems study on engineered barriers; criteria for defining waste isolation; spent fuel and fuel pool component integrity program; analysis of spent fuel policy implementation; asphalt emulsion sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and development of backfill material.

  14. Preliminary Safety Design Report for Remote Handled Low-Level Waste Disposal Facility

    Energy Technology Data Exchange (ETDEWEB)

    Timothy Solack; Carol Mason

    2012-03-01

    A new onsite, remote-handled low-level waste disposal facility has been identified as the highest ranked alternative for providing continued, uninterrupted remote-handled low-level waste disposal for remote-handled low-level waste from the Idaho National Laboratory and for nuclear fuel processing activities at the Naval Reactors Facility. Historically, this type of waste has been disposed of at the Radioactive Waste Management Complex. Disposal of remote-handled low-level waste in concrete disposal vaults at the Radioactive Waste Management Complex will continue until the facility is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). This preliminary safety design report supports the design of a proposed onsite remote-handled low-level waste disposal facility by providing an initial nuclear facility hazard categorization, by discussing site characteristics that impact accident analysis, by providing the facility and process information necessary to support the hazard analysis, by identifying and evaluating potential hazards for processes associated with onsite handling and disposal of remote-handled low-level waste, and by discussing the need for safety features that will become part of the facility design.

  15. Solid waste burial grounds interim safety analysis

    International Nuclear Information System (INIS)

    Saito, G.H.

    1994-01-01

    This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment

  16. Solid waste burial grounds interim safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Saito, G.H.

    1994-10-01

    This Interim Safety Analysis document supports the authorization basis for the interim operation and restrictions on interim operations for the near-surface land disposal of solid waste in the Solid Waste Burial Grounds. The Solid Waste Burial Grounds Interim Safety Basis supports the upgrade progress for the safety analysis report and the technical safety requirements for the operations in the Solid Waste Burial Grounds. Accident safety analysis scenarios have been analyzed based on the significant events identified in the preliminary hazards analysis. The interim safety analysis provides an evaluation of the operations in the Solid Waste Burial Grounds to determine if the radiological and hazardous material exposures will be acceptable from an overall health and safety standpoint to the worker, the onsite personnel, the public, and the environment.

  17. Technical Safety Requirements for the Waste Storage Facilities

    International Nuclear Information System (INIS)

    Larson, H L

    2007-01-01

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

  18. Technical Safety Requirements for the Waste Storage Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Larson, H L

    2007-09-07

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

  19. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Report of the Federal Republic of Germany for the sixth review meeting in May 2018; Gemeinsames Uebereinkommen ueber die Sicherheit der Behandlung abgebrannter Brennelemente und ueber die Sicherheit der Behandlung radioaktiver Abfaelle. Bericht der Bundesrepublik Deutschland fuer die sechste Ueberpruefungskonferenz im Mai 2018

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2017-08-15

    The joint convention on the safety of spent fuel management and on the safety of radioactive waste management covers the following topics: historical development and actual status of the civil use of nuclear power, politics and the spent fuel management, inventories and listing, legislation and executive systems, other safeguard regulations, safety during spent fuel handling, safety during radioactive waste processing, transport across national borders, disused enclosed radioactive sources, general regulations for safety enhancement.

  20. Waste management, waste resource facilities and waste conversion processes

    International Nuclear Information System (INIS)

    Demirbas, Ayhan

    2011-01-01

    In this study, waste management concept, waste management system, biomass and bio-waste resources, waste classification, and waste management methods have been reviewed. Waste management is the collection, transport, processing, recycling or disposal, and monitoring of waste materials. A typical waste management system comprises collection, transportation, pre-treatment, processing, and final abatement of residues. The waste management system consists of the whole set of activities related to handling, treating, disposing or recycling the waste materials. General classification of wastes is difficult. Some of the most common sources of wastes are as follows: domestic wastes, commercial wastes, ashes, animal wastes, biomedical wastes, construction wastes, industrial solid wastes, sewer, biodegradable wastes, non-biodegradable wastes, and hazardous wastes.

  1. The challenge of the radioactive waste management

    International Nuclear Information System (INIS)

    Dupuis, M. C.

    2008-01-01

    The problem of waste management has gained relevance with the development of electronuclear production and the increased social awareness on the need to protect the environment. While most developed countries have found solutions for the disposal of waste of low intensity and duration, the storage of used fuel and other kind of waste of higher intensity and duration is one of the main challenges for the next decade. Scientific research focuses on long term safety, while questions on the need for new governance are raised at the socio political level. Organizations such as the AEN have strengthened international cooperation to overcome the scientific, technical and socio-political challenges related to the nuclear waste management. (Author) 15 refs

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

    International Nuclear Information System (INIS)

    Wei Fangxin

    2012-01-01

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

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

    International Nuclear Information System (INIS)

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

    1989-01-01

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

  4. Radioactive wastes. The management of nuclear wastes. Waste workshop, first half-year - Year 2013-2014

    International Nuclear Information System (INIS)

    Esteoulle, Lucie; Rozwadowski, Elodie; Duverger, Clara

    2014-01-01

    The first part of this report first presents radioactive wastes with their definition, and their classification (radioactivity level, radioactive half-life). It addresses the issue of waste storage by presenting the different types of storage used since the 1950's (offshore storage, surface warehousing, storage in deep geological layer), and by discussing the multi-barrier approach used for storage safety. The authors then present the French strategy which is defined in the PNGMDR to develop new management modes on the long term, to improve existing management modes, and to take important events which occurred between 2010 and 2012 into account. They also briefly present the Cigeo project (industrial centre of geological storage), and evoke controversies related to the decision to locate this project in Bure (existence of geological cracks and defects, stability and tightness of the clay layer, geothermal potential of the region, economic cost). The second part proposes an overview of the issue of nuclear waste management. The author recalls the definition of a radioactive waste, indicates the origins of these wastes and their classification. She proposes a history of the radioactive waste: discovery of radioactivity, military industrialisation and awareness of the dangerousness of radioactive wastes, nuclear wastes and recent incidents (West Valley, La Hague, Windscale). An overview of policies of nuclear waste management is given: immersion of radioactive wastes, major accidental releases, solutions on the short term and on the medium term

  5. Issues in radioactive waste management for fusion power

    International Nuclear Information System (INIS)

    Maninger, R.C.; Dorn, D.W.

    1983-01-01

    Analysis of recent conceptual designs reveals that commercial fusion power systems will raise issues of occupational and public health and safety. This paper focuses on radioactive wastes from fusion reactor materials activated by neutrons. The analysis shows that different selections of materials and neutronic designs can make differences in orders-of magnitude of the kinds and amounts of radioactivity to be expected. By careful and early evaluation of the impacts of the selections on waste management, designers can produce fusion power systems with radiation from waste well below today's limits for occupational and public health and safety

  6. Issues in radioactive-waste management for fusion power

    International Nuclear Information System (INIS)

    Maninger, R.C.; Dorn, D.W.

    1982-01-01

    Analysis of recent conceptual designs reveals that commercial fusion power systems will raise issues of occupational and public health and safety. This paper focuses on radioactive wastes from fusion reactor materials activated by neutrons. The analysis shows that different selections of materials and neutronic designs can make differences in orders-of-magnitude of the kinds and amounts of radioactivity to be expected. By careful and early evaluation of the impacts of the selections on waste management, designers can produce fusion power systems with radiation from waste well below today's limits for occupational and public health and safety

  7. Swedish national plan for the management of all radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    2010-01-15

    The Swedish Radiation Safety Authority has been assigned by the government to develop a national plan for the management of all radioactive waste. This report was presented to the government 30 June 2009. The report has been developed in coordination with representatives from other authorities, trade and industry organizations, operators and other parties interested, forming a joint action group. The action proposals in this report are focused on bringing waste management outside the nuclear field, where requirements are essentially regulated by the Act on Radiation Protection, to a level comparable with the management of nuclear waste (including the management of spent nuclear fuel). The Swedish Radiation Safety Authority believes that the objective of the national waste plan is that Sweden, by 2020, will have a comprehensive waste management system whereby all types of radioactive waste will be disposed of in a safe manner. The plan will make it easier to ensure that waste sub-systems for nuclear and non-nuclear waste - which could otherwise easily be regarded as being separated from each other - do not need to be distinguished to any great extent. To ensure continuity in the work in the future, with regard to the follow-up of plans for all radioactive waste, the Swedish Radiation Safety Authority propose that the national waste plan is updated every three years. The plan can then function as the strategy document or the action plan it is intended to be, ensuring that the focus remains on the various problems associated with waste management at different times, so that the set objective can be reached by 2020. A survey was carried out to identify the problems and shortcomings that were found in the waste-management system and what measures are required to resolve them within the near future. The joint action group has contributed by describing various problems as well as by offering points of view on the action proposals which the Swedish Radiation Safety

  8. Swedish national plan for the management of all radioactive waste

    International Nuclear Information System (INIS)

    2011-01-01

    The Swedish Radiation Safety Authority has been assigned by the government to develop a national plan for the management of all radioactive waste. This report was presented to the government 30 June 2009. The report has been developed in coordination with representatives from other authorities, trade and industry organizations, operators and other parties interested, forming a joint action group. The action proposals in this report are focused on bringing waste management outside the nuclear field, where requirements are essentially regulated by the Act on Radiation Protection, to a level comparable with the management of nuclear waste (including the management of spent nuclear fuel). The Swedish Radiation Safety Authority believes that the objective of the national waste plan is that Sweden, by 2020, will have a comprehensive waste management system whereby all types of radioactive waste will be disposed of in a safe manner. The plan will make it easier to ensure that waste sub-systems for nuclear and non-nuclear waste - which could otherwise easily be regarded as being separated from each other - do not need to be distinguished to any great extent. To ensure continuity in the work in the future, with regard to the follow-up of plans for all radioactive waste, the Swedish Radiation Safety Authority propose that the national waste plan is updated every three years. The plan can then function as the strategy document or the action plan it is intended to be, ensuring that the focus remains on the various problems associated with waste management at different times, so that the set objective can be reached by 2020. A survey was carried out to identify the problems and shortcomings that were found in the waste-management system and what measures are required to resolve them within the near future. The joint action group has contributed by describing various problems as well as by offering points of view on the action proposals which the Swedish Radiation Safety

  9. Actions of a protocol for radioactive waste management

    International Nuclear Information System (INIS)

    Sousa, Joyce Caroline de Oliveira; Andrade, Idalmar Gomes da Silva; Frazão, Denys Wanderson Pereira; Abreu, Lukas Maxwell Oliveira de; França, Clyslane Alves; Macedo, Paulo de Tarso Silva de

    2017-01-01

    Radioactive wastes are all those materials generated in the various uses of radioactive materials, which can not be reused and which have radioactive substances in quantities that can not be treated as ordinary waste. All management of these wastes must be carried out carefully, including actions ranging from its collection to the point where they are generated to their final destination. However, any and all procedures must be carried out in order to comply with the requirements for the protection of workers, individuals, the public and the environment. The final product of the study was a descriptive tutorial on the procedures and actions of a standard radioactive waste management protocol developed from scientific publications on radiation protection. The management of radioactive waste is one of the essential procedures in the radiological protection of man and the environment where the manipulation of radioactive materials occurs. The standard radioactive management protocol includes: collection, segregation of various types of wastes, transport, characterization, treatment, storage and final disposal. The radioactive wastes typology interferes with sequencing and the way in which actions are developed. The standardization of mechanisms in the management of radioactive waste contributes to the radiological safety of all those involved

  10. Nuclear waste management. Quarterly progress report, April-June 1981

    Energy Technology Data Exchange (ETDEWEB)

    Chikalla, T.D.; Powell, J.A.

    1981-09-01

    Reports and summaries are presented for the following: high-level waste process development; alternative waste forms; TMI zeolite vitrification demonstration program; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton implantation; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclides in soils; handbook of methods to decrease the generation of low-level waste; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; and analysis of spent fuel policy implementation.

  11. Sweden's second national report under the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Swedish implementation of the obligations of the Joint Convention

    International Nuclear Information System (INIS)

    2005-01-01

    Article 32 of the Joint Convention calls for a self-assessment by each Contracting Party regarding compliance with the obligations of the Convention. Sweden's self-assessment has demonstrated compliance with all the obligations of the Convention, as shown in detail in sections B to K of this report. Having taken a very active part in the creation of the Joint Convention, Sweden wishes to emphasise the incentive character of the Convention. In Sweden's opinion, the Convention implies a commitment to continuous improvement of safety whenever operating experience, safety research or technical development indicates that there is room for such improvement. Continuous learning from experience and a proactive approach to safety are in fact corner stones of the current Swedish nuclear and radiation safety work, both for the industry and the regulatory bodies. Therefore, Sweden has found it important that its National Report highlights strong features in national practices, as well as areas in which improvements are justified. Implementation of such improvements should then be followed up in the National Reports to subsequent Review Meetings. The major events in the Swedish nuclear programme since the first report to the Convention was issued are: - The general safety regulations of SKI have been revised and issued as SKIFS 2004:1. - A commission of inquiry has been carried out in order to review and suggest improvements to the financing system. - The second unit of the twin nuclear power plant unit at Barsebaeck (Barsebaeck 2) was permanently shut down 31 May 2005. The first unit (Barsebaeck 1) was closed in 1999. - The research reactors R2 and R2-0 at the Studsvik site were permanently shut down 16 June 2005. - The Swedish Nuclear Fuel and Waste Management Co. (SKB) has announced its decision to take over operation of the interim storage facility for spent nuclear fuel (Clab). The operation of Clab is currently contracted out to OKG, who operates the three nuclear power

  12. Better safe than sorry: Increasing safety in radioactive waste management

    International Nuclear Information System (INIS)

    Gaspar, Miklos; Mutluer, Adem

    2015-01-01

    Abderrahim Bouih used to be worried about space. In charge of managing Morocco’s radioactive waste since 2006, he had long projected that the country’s sole radioactive waste facility would fill up by 2019. Thanks to a new methodology he and his colleagues learned through an IAEA project, they can now dismantle smoke detectors, lightning rods and other waste that contains radioactive material, safely separating the radioactive components from the metal, and significantly reducing the amount of radioactive waste they need to store.

  13. National system for radioactive waste management in Lithuania and its harmonization with the European Union legislation

    International Nuclear Information System (INIS)

    Adomaitis, J. E.; Poshkas, P.

    1999-01-01

    Radioactive waste management philosophies and technologies are still emerging, and there is therefore a need to reorganize and improve the national system for radioactive waste management in Lithuania. Lithuania's Law on Radioactive Waste Management and the new regulations will be harmonized with the European Union legislation in this field, with the IAEA general principles and with the obligations of the Republic of Lithuania under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. Different organizational and financial schemes available in the EU countries for radioactive waste management are described and analyzed. The most important aspects needed to establish the Lithuania's Radioactive Waste Management Agency and Fund are defined and developed. (author)

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

    International Nuclear Information System (INIS)

    Semenov, B.A.

    1984-01-01

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

  15. Waste management

    International Nuclear Information System (INIS)

    Chmielewska, E.

    2010-01-01

    In this chapter formation of wastes and basic concepts of non-radioactive waste management are explained. This chapter consists of the following parts: People in Peril; Self-regulation of nature as a guide for minimizing and recycling waste; The current waste management situation in the Slovak Republic; Categorization and determination of the type of waste in legislative of Slovakia; Strategic directions waste management in the Slovak Republic.

  16. Finnish Research Programme on Nuclear Waste Management (KYT). Framework Programme for 2002-2005

    International Nuclear Information System (INIS)

    Rasilainen, K.

    2002-12-01

    The new Finnish research programme on nuclear waste management (KYT) will be conducted in 2002 - 2005. This framework programme describes the starting point, the basic aims and the organisation of the research programme. The starting point of the KYT programme is derived from the present state and future challenges of Finnish nuclear waste management. The research programme is funded mainly by the Ministry of Trade and Industry (KTM), the Radiation and Nuclear Safety Authority (STUK), Posiva Oy, Fortum Oyj, Teollisuuden Voima Oy (TVO), and the National Technology Agency (Tekes). As both regulators and implementors are involved, the research programme concentrates on neutral research topics that must be studied in any case. Methods and tools for experimental and theoretical studies fall in this category. State of the art -reviews on relevant topics also create national know-how. Topics that directly belong to licensing activities of nuclear waste management are excluded from the research programme. KYT carries out technical studies that increase national know-how in the area of nuclear waste management. The aim is to maintain and develop basic expertise needed in the operations derived from the national nuclear waste management plan. The studies have been divided into strategic studies and studies enhancing the long-term safety of spent nuclear fuel disposal. Strategic studies support the overall feasibility of Finnish nuclear waste management. These studies include basic options and overall safety principles related to nuclear fuel cycle and nuclear waste management. In addition, general cost estimates as well as general safety considerations related to transportations, low- and medium level wastes, and decommissioning are included in strategic studies. Studies supporting the long-term safety of spent fuel disposal include issues related to performance assessment methodology, release of radionuclides from the repository, behaviour of bedrock and groundwater

  17. Nuclear waste management. Quarterly progress report, October-December 1979

    Energy Technology Data Exchange (ETDEWEB)

    Platt, A.M.; Powell, J.A. (comps.)

    1980-04-01

    Progress and activities are reported on the following: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization programs, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, monitoring of unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions technology, spent fuel and fuel pool integrity program, and engineered barriers. (DLC)

  18. The work of the High Commission for transparency and information on nuclear safety concerning the management of radioactive materials and waste

    International Nuclear Information System (INIS)

    Revol, H.

    2011-01-01

    Created by law in June 2006, the High Committee for Transparency and Information about Nuclear Security (HCTISN) is a pluralist instance dedicated to information, consultation and debates on issues related to nuclear activities and their impacts on environment and health. Currently chaired by a honorary senator, the High committee is composed of about forty persons who meet at least every three months. The subject of sustainable management of radioactive materials and waste is one of the main topical issues examined by the High committee. Since 2009, a dedicated think-tank has been set up to deal with questions of information, consultation and transparency all along the decision making process for the creation of a new storage installation for radioactive waste. In 2010, the High committee has been mandated by the Ministry in charge of nuclear safety to draw up a report on the transparency in the field of management of waste and materials produced at each stage of fuel cycle. Management of radioactive waste continues to raise discussion and rich debates within the High committee. In 2011, the High committee's intentions are to organize public information, consultations and debates about sustainable management of radioactive materials and waste. (author)

  19. Battery collection in municipal waste management in Japan: Challenges for hazardous substance control and safety

    International Nuclear Information System (INIS)

    Terazono, Atsushi; Oguchi, Masahiro; Iino, Shigenori; Mogi, Satoshi

    2015-01-01

    Highlights: • Consumers need to pay attention to the specific collection rules for each type of battery in each municipality in Japan. • 6–10% of zinc carbon and alkaline batteries discarded in Japan currently could be regarded as containing mercury. • Despite announcements by producers and municipalities, only 2.0% of discarded cylindrical dry batteries were insulated. • Batteries made up an average of 4.6% of the total collected small WEEE under the small WEEE recycling scheme in Japan. • Exchangeable batteries were used in almost all of mobile phones, but the removal rate was as low as 22% for mobile phones. - Abstract: To clarify current collection rules of waste batteries in municipal waste management in Japan and to examine future challenges for hazardous substance control and safety, we reviewed collection rules of waste batteries in the Tokyo Metropolitan Area. We also conducted a field survey of waste batteries collected at various battery and small waste electric and electronic equipment (WEEE) collection sites in Tokyo. The different types of batteries are not collected in a uniform way in the Tokyo area, so consumers need to pay attention to the specific collection rules for each type of battery in each municipality. In areas where small WEEE recycling schemes are being operated after the enforcement of the Act on Promotion of Recycling of Small Waste Electrical and Electronic Equipment in Japan in 2013, consumers may be confused about the need for separating batteries from small WEEE (especially mobile phones). Our field survey of collected waste batteries indicated that 6–10% of zinc carbon and alkaline batteries discarded in Japan currently could be regarded as containing mercury. More than 26% of zinc carbon dry batteries currently being discarded may have a lead content above the labelling threshold of the EU Batteries Directive (2006/66/EC). In terms of safety, despite announcements by producers and municipalities about using

  20. Battery collection in municipal waste management in Japan: Challenges for hazardous substance control and safety

    Energy Technology Data Exchange (ETDEWEB)

    Terazono, Atsushi, E-mail: terazono@nies.go.jp [National Institute for Environmental Studies, 16-2 Onogawa, Tsukuba, Ibaraki 305-8506 (Japan); Oguchi, Masahiro [National Institute for Environmental Studies, 16-2 Onogawa, Tsukuba, Ibaraki 305-8506 (Japan); Iino, Shigenori [Tokyo Metropolitan Research Institute for Environmental Protection, 1-7-5 Shinsuna, Koto-ku, Tokyo 136-0075 (Japan); Mogi, Satoshi [Bureau of Environment, Tokyo Metropolitan Government, 2-8-1 Nishi-shinjuku, Shinjuku-ku, Tokyo 163-8001 (Japan)

    2015-05-15

    Highlights: • Consumers need to pay attention to the specific collection rules for each type of battery in each municipality in Japan. • 6–10% of zinc carbon and alkaline batteries discarded in Japan currently could be regarded as containing mercury. • Despite announcements by producers and municipalities, only 2.0% of discarded cylindrical dry batteries were insulated. • Batteries made up an average of 4.6% of the total collected small WEEE under the small WEEE recycling scheme in Japan. • Exchangeable batteries were used in almost all of mobile phones, but the removal rate was as low as 22% for mobile phones. - Abstract: To clarify current collection rules of waste batteries in municipal waste management in Japan and to examine future challenges for hazardous substance control and safety, we reviewed collection rules of waste batteries in the Tokyo Metropolitan Area. We also conducted a field survey of waste batteries collected at various battery and small waste electric and electronic equipment (WEEE) collection sites in Tokyo. The different types of batteries are not collected in a uniform way in the Tokyo area, so consumers need to pay attention to the specific collection rules for each type of battery in each municipality. In areas where small WEEE recycling schemes are being operated after the enforcement of the Act on Promotion of Recycling of Small Waste Electrical and Electronic Equipment in Japan in 2013, consumers may be confused about the need for separating batteries from small WEEE (especially mobile phones). Our field survey of collected waste batteries indicated that 6–10% of zinc carbon and alkaline batteries discarded in Japan currently could be regarded as containing mercury. More than 26% of zinc carbon dry batteries currently being discarded may have a lead content above the labelling threshold of the EU Batteries Directive (2006/66/EC). In terms of safety, despite announcements by producers and municipalities about using

  1. CEA's waste management policy and strategy. Lessons learned - 59201

    International Nuclear Information System (INIS)

    Dall'ava, Didier

    2012-01-01

    Document available in abstract form only. Full text of publication follows: Radioactive wastes are generated during operation as well as during the decontamination and dismantling of CEA's nuclear facility/installation. The safe and responsible management of radioactive wastes at all stages is an essential requirement of the regulatory system. The management covers the whole sequence of operations starting with the generation of waste and ending with its disposal. The disposal here means discarding of waste with no intention for retrieval. It is important to note here that the safety principles and practices that are applicable during the operational phase are also applicable during the decommissioning phase. As the radioactive waste arising is an inevitable outcome of decommissioning work, all the regulatory requirements associated with decommissioning remain in force in waste management. This presentation deals initially with the regulatory standards related to the management of wastes. As the management of radioactive wastes inevitably includes treatment and conditioning of wastes, following treatment and conditioning of wastes, storage, transportation and eventual disposal are the logical outcome of the radioactive wastes, processes are at any time improved based on the feedback experience and the lessons learned. (author)

  2. Radioactive waste management of the nuclear medicine services

    International Nuclear Information System (INIS)

    Barboza, Alex

    2009-01-01

    Radioisotope applications in nuclear medicine services, for diagnosis and therapy, generate radioactive wastes. The general characteristics and the amount of wastes that are generated in each facility are function of the number of patients treated, the procedures adopted, and the radioisotopes used. The management of these wastes embraces every technical and administrative activity necessary to handle the wastes, from the moment of their generation, till their final disposal, must be planned before the nuclear medicine facility is commissioned, and aims at assuring people safety and environmental protection. The regulatory framework was established in 1985, when the National Commission on Nuclear Energy issued the regulation CNEN-NE-6.05 'Radioactive waste management in radioactive facilities'. Although the objective of that regulation was to set up the rules for the operation of a radioactive waste management system, many requirements were broadly or vaguely defined making it difficult to ascertain compliance in specific facilities. The objective of the present dissertation is to describe the radioactive waste management system in a nuclear medicine facility and provide guidance on how to comply with regulatory requirements. (author)

  3. Nuclear waste management. Quarterly progress report, July-September 1980

    Energy Technology Data Exchange (ETDEWEB)

    Chikalla, T.D.

    1980-11-01

    Research is reported on: high-level waste immobilization, alternative waste forms, TRU waste immobilization and decontamination, krypton solidification, thermal outgassing, /sup 129/I fixation, unsaturated zone transport, well-logging instrumentation, waste management system and safety studies, effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, backfill material, spent fuel storage (criticality), barrier sealing and liners for U mill tailings, and revegetation of inactive U tailings sites. (DLC)

  4. Management of wastes from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Heafield, W.; Barlow, P.

    1988-01-01

    The management of wastes from the nuclear fuel cycle is a key activity which affects all stages of the cycle and in which there is intense public interest, particularly at the culmination of waste management activities where dispersal and disposal are practised or are proposed. The different categories of waste are considered - high, intermediate and low level. A description is given of how and where in the fuel cycle they are produced, giving indications of volumes and activities. The fundamental objectives of waste management are reviewed and the application of these objectives to select practicable waste management processes, covering process systems product and safety considerations is discussed. Current technology can deal with the wastes now in storage, those which will be generated from oxide fuel reprocessing and future decommissioning activities; examples of these technologies, ranging from compaction and incineration for low level waste, encapsulation for intermediate level waste through to vitrification for high level waste, are described. The specific objectives relating to disposal are considered in the context of international co-operation on development and national strategies aimed at providing safe, deep repositories over the next 20 years. (author)

  5. A comparative assessment of alternative waste management procedures for selected reprocessing wastes

    International Nuclear Information System (INIS)

    Hickford, G.E.; Plews, M.J.

    1983-07-01

    This report, which has been prepared by Associated Nuclear Services for the Department of the Environment, presents the results of a study and comparative assessment of management procedures for low and intermediate level solid waste streams arising from current and future fuel reprocessing operations on the Sellafield site. The characteristics and origins of the wastes under study are discussed and a reference waste inventory is presented, based on published information. Waste management strategy in the UK and its implications for waste conditioning, packaging and disposal are discussed. Wastes currently arising which are not suitable for Drigg burial or sea dumping are stored in an untreated form. Work is in hand to provide additional and improved disposal facilities which will accommodate all the waste streams under study. For each waste stream viable procedures are identified for further assessment. The procedures comprise a series of on-site operations-recovery from storage, pre-treatment, treatment, encapsulation, and packaging, prior to storage or disposal of the conditioned waste form. Assessments and comparisons of each procedure for each waste are presented. These address various process, operational, economic, radiological and general safety factors. The results are presented in a series of tables with supporting text. For the majority of wastes direct encapsulation with minimal treatment appears to be a viable procedure. Occupational exposure and general safety are not identified as significant factors governing the choice of procedures. The conditioned wastes meet the general requirements for safe handling during storage and transportation. The less active wastes suitable for disposal by currently available routes meet the appropriate disposal criteria. It is not possible to consider in detail the suitability for disposal of the more active wastes for which disposal facilities are not yet available. (Author)

  6. Demonstration and Dialogue: Mediation in Swedish Nuclear Waste Management

    International Nuclear Information System (INIS)

    Elam, Mark; Lidberg, Maria; Soneryd, Linda; Sundqvist, Goeran

    2009-01-01

    This report analyses mediation and mediators in Swedish nuclear waste management. Mediation is about establishing agreement and building common knowledge. It is argued that demonstrations and dialogue are the two prominent approaches to mediation in Swedish nuclear waste management. Mediation through demonstration is about showing, displaying, and pointing out a path to safe disposal for inspection. It implies a strict division between demonstrator and audience. Mediation through dialogue on the other hand, is about collective acknowledgements of uncertainty and suspensions of judgement creating room for broader discussion. In Sweden, it is the Swedish Nuclear Fuel and Waste Management Co. (SKB) that is tasked with finding a method and a site for the final disposal of the nation's nuclear waste. Two different legislative frameworks cover this process. In accordance with the Act on Nuclear Activities, SKB is required to demonstrate the safety of its planned nuclear waste management system to the government, while in respect of the Swedish Environmental Code, they are obliged to organize consultations with the public. How SKB combines these requirements is the main question under investigation in this report in relation to materials deriving from three empirical settings: 1) SKB's safety analyses, 2) SKB's public consultation activities and 3) the 'dialogue projects', initiated by other actors than SKB broadening the public arena for discussion. In conclusion, an attempt is made to characterise the long- term interplay of demonstration and dialogue in Swedish nuclear waste management

  7. Progress report on safety research on radioactive waste management for the period April 1996 to March 1998

    International Nuclear Information System (INIS)

    Ohnuki, Toshihiko; Muraoka, Susumu; Banba, Tsunetaka

    1998-10-01

    This report summarizes the research and development activities on radioactive waste management at the Engineered Barrier Materials Laboratory, Natural Barrier Laboratory and Environmental Geochemistry Laboratory of the Department of Environmental Safety Research, JAERI during the fiscal year of 1996 and 1997 (April 1, 1996 - March 31, 1998). The topics are as follows: (1) In the research and development of waste forms and engineered barrier, studies on development of ceramic waste forms, the leaching behaviors from glass waste at reduced condition and sorption behaviors on backfill materials have been carried out. (2) In studies on shallow land disposal, studies on the migration behaviors of radionuclides in the presence of humic acid have been carried out. (3) In the studies on geological disposal, the studies on diffusivity in rock formation, in-situ migration and diffusion experiments, sorption mechanism, fixation mechanism, natural analogue study and geochronology have been carried out. (author)

  8. Managing nuclear waste from power plants

    International Nuclear Information System (INIS)

    Keeney, R.L.; Winterfeldt, D. von

    1994-01-01

    National strategies to manage nuclear waste from commercial nuclear power plants are analyzed and compared. The current strategy is to try to operate a repository at Yucca Mountain, Nevada, to dispose storage at a centralized facility or next to nuclear power plants. If either of these is pursued now, the analysis assumes that a repository will be built in 2100 for waste not subsequently put to use. The analysis treats various uncertainties: whether a repository at Yucca Mountain would be licensed, possible theft and misuse of the waste, innovations in repository design and waste management, the potential availability of a cancer cure by 2100, and possible future uses of nuclear waste. The objectives used to compare alternatives include concerns for health and safety, environmental and socioeconomic impacts, and direct economic costs, as well as equity concerns (geographical, intergenerational, and procedural), indirect economic costs, as well as equity concerns (geographical, intergenerational, and procedural), indirect economic costs to electricity ratepayers, federal government responsibility to manage nuclear waste, and implications of theft and misuse of nuclear waste. The analysis shows that currently building an underground repository at Yucca Mountain is inferior to other available strategies by the equivalent of $10,000 million to $50,000 million. This strongly suggests that this policy should be reconsidered. A more detailed analysis using the framework presented would help to define a new national policy to manage nuclear waste. 36 refs., 3 figs., 17 tabs

  9. Technical Safety Requirements for the Waste Storage Facilities

    International Nuclear Information System (INIS)

    Laycak, D.T.

    2010-01-01

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2009). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting

  10. Technical Safety Requirements for the Waste Storage Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D T

    2008-06-16

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas

  11. Topical issues in nuclear, radiation and radioactive waste safety. Contributed papers

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-08-01

    The IAEA International Conference on Topical Issues in Nuclear, Radiation and Radioactive Waste Safety was held in Vienna, Austria, 30 August - 4 September 1998 with the objective to foster the exchange of information on topical issues in nuclear, radiation and radioactive waste safety, with the aim of consolidating an international consensus on: the present status of these issues; priorities for future work; and needs for strengthening international co-operation, including recommendations for the IAEA`s future activities. The document includes 43 papers presented at the Conference dealing with the following topical issues: Safety Management; Backfitting, Upgrading and Modernization of NPPs; Regulatory Strategies; Occupational Radiation Protection: Trends and Developments; Situations of Chronic Exposure to Residual Radioactive Materials: Decommissioning and Rehabilitation and Reclamation of Land; Radiation Safety in the Far Future: The Issue of Long Term Waste Disposal. A separate abstract and indexing were provided for each paper. Refs, figs, tabs

  12. Topical issues in nuclear, radiation and radioactive waste safety. Contributed papers

    International Nuclear Information System (INIS)

    1998-08-01

    The IAEA International Conference on Topical Issues in Nuclear, Radiation and Radioactive Waste Safety was held in Vienna, Austria, 30 August - 4 September 1998 with the objective to foster the exchange of information on topical issues in nuclear, radiation and radioactive waste safety, with the aim of consolidating an international consensus on: the present status of these issues; priorities for future work; and needs for strengthening international co-operation, including recommendations for the IAEA's future activities. The document includes 43 papers presented at the Conference dealing with the following topical issues: Safety Management; Backfitting, Upgrading and Modernization of NPPs; Regulatory Strategies; Occupational Radiation Protection: Trends and Developments; Situations of Chronic Exposure to Residual Radioactive Materials: Decommissioning and Rehabilitation and Reclamation of Land; Radiation Safety in the Far Future: The Issue of Long Term Waste Disposal. A separate abstract and indexing were provided for each paper

  13. Waste Encapsulation and Storage Facility interim operational safety requirements

    CERN Document Server

    Covey, L I

    2000-01-01

    The Interim Operational Safety Requirements (IOSRs) for the Waste Encapsulation and Storage Facility (WESF) define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt and inspection of cesium and strontium capsules from private irradiators; decontamination of the capsules and equipment; surveillance of the stored capsules; and maintenance activities. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological consequences below risk evaluation guidelines (EGs) are included.

  14. Probabilistic safety assessment for Hanford high-level waste tanks

    International Nuclear Information System (INIS)

    MacFarlane, D.R.; Stack, D.S.; Kindinger, J.P.; Deremer, R.K.

    1995-01-01

    This paper gives results from the first comprehensive level-3 probabilistic safety assessment (PSA), including consideration of external events, for the Hanford tank farm (HTF). This work was sponsored by the U.S. Department of Energy/Environmental Restoration and Waste Management Division (DOE/EM). At the HTF, there are 177 underground tanks in 18 separate tank farms containing accumulated liquid/sludge/saltcake radioactive wastes from 50 yr of weapons materials production activities. The total waste volume is ∼60 million gal, containing ∼200 million Ci of radioactivity

  15. The Safety Case and Safety Assessment for the Disposal of Radioactive Waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2012-09-15

    This Safety Guide provides guidance and recommendations on meeting the safety requirements in respect of the safety case and supporting safety assessment for the disposal of radioactive waste. The safety case and supporting safety assessment provide the basis for demonstration of safety and for licensing of radioactive waste disposal facilities and assist and guide decisions on siting, design and operations. The safety case is also the main basis on which dialogue with interested parties is conducted and on which confidence in the safety of the disposal facility is developed. This Safety Guide is relevant for operating organizations preparing the safety case as well as for the regulatory body responsible for developing the regulations and regulatory guidance that determine the basis and scope of the safety case. Contents: 1. Introduction; 2. Demonstrating the safety of radioactive waste disposal; 3. Safety principles and safety requirements; 4. The safety case for disposal of radioactive waste; 5. Radiological impact assessment for the period after closure; 6. Specific issues; 7. Documentation and use of the safety case; 8. Regulatory review process.

  16. IAEA Mission Says France Committed to Safe, Responsible Management of Radioactive Waste

    International Nuclear Information System (INIS)

    2018-01-01

    An International Atomic Energy Agency (IAEA) team of experts said France demonstrated a comprehensive commitment to safety with a responsible approach to the management of radioactive waste and spent nuclear fuel. The team also made suggestions aimed at further enhancements and noted several good practices. The Integrated Review Service for Radioactive Waste and Spent Fuel Management, Decommissioning and Remediation (ARTEMIS) team concluded an 11-day mission to France on 24 January. The mission, requested by the Government of France, was hosted by the Directorate General of Energy and Climate (DGEC), with the participation of officials from several relevant organizations including the French National Radioactive Waste Agency (ANDRA) and the Nuclear Safety Authority (ASN), which is responsible for nuclear and radiation safety regulation in the country. ARTEMIS missions provide independent expert advice from an international team of specialists convened by the IAEA. Reviews are based on the IAEA safety standards as well as international good practices. The mission to France aimed to help the country meet European Union obligations that require an independent peer review of national programmes for the safe and responsible management of spent fuel and radioactive waste. Nuclear power currently generates more than 70 percent of France’s electricity. The country has 58 operating nuclear power reactors, which will require the continuing safe management of radioactive waste and spent fuel. France operates facilities for the disposal of very low-level and low-level wastes, and is developing a deep geological repository for the disposal of high-level waste.

  17. Radioactive waste management. Ukraine. WAMAP mission to Ukraine

    International Nuclear Information System (INIS)

    Bergman, C.; Samiei, M.; Takats, F.

    1993-01-01

    In February 1992, the Ukrainian State Committee on Nuclear and Radiation Safety IAEA assisted in management of radwaste and spent fuel. A three member IAEA mission was sent to Ukraine for fact-finding. The present report discusses the outcome of this mission. It gives present legislation, regulations and organizational situation in Ukraine and generation and waste management of radioactive wastes. It discusses possible area of technical co-operation, conclusions and recommendations of the mission

  18. Operational safety of near surface waste disposal facilities in the Republic of Moldova

    International Nuclear Information System (INIS)

    Ursulean, I.; Balaban, V.

    2000-01-01

    Over the last few years, the Republic of Moldova, with assistance from the IAEA, undertook the establishment of the legislative and normative basis consisting of a regulatory body infrastructure, including a monitoring optimization strategy concerning radioactive waste management safety. At present the following work is underway: the introduction of a new law 'About Radiation Safety and Population Protection', the re-implementation of a normative base, and the incorporation of the IAEA Basic Safety Standards through the national legislation. Presently in the Republic of Moldova, there exists a system of radioactive waste management, comprising collection, disposal, transportation and storage. This system consists of the radioactive material users, the designated disposal facility and the regulatory bodies. (author)

  19. Transforming Argonne's waste management organization - the road to energy quality

    International Nuclear Information System (INIS)

    Torres, T.A.; Sodaro, M.A.; Thuot, J.R.

    1996-01-01

    Argonne National Laboratory's (ANL's) Waste Management Department began its journey to excellence in 1990. The department was organized to provide for waste cleanup, waste handling, decontamination, and other services. The staff was principally workers and foremen with few professional staff. The department has transitioned into a highly effective organization that has competed for the President's Energy Quality Award. The department is currently staffed by 58 people, including professional staff and waste mechanics. The department began by recognizing and addressing the problems that existed: There was no formal waste safety program or waste reduction culture. Formal procedures did not cover all aspects of waste operations, waste handling procedures and acceptance criteria were out of date, and the Waste Management Department did not have a customer-centered culture. The department began a step by step program to improve the waste management organization

  20. The UK Committee on Radioactive Waste Management

    International Nuclear Information System (INIS)

    Baverstock, Keith; Ball, David J

    2005-01-01

    The UK Committee on Radioactive Waste Management is charged with recommending to Government, by July 2006, options for the long term management of the UK's radioactive waste legacy. These options should inspire public confidence. Now, more than halfway into the time allotted, we, as two former members of the Committee, express our concerns at the wayward approach that has been adopted. The Committee has placed emphasis on gaining public confidence but this has been done at the expense of recruiting the best scientific expertise in the management of radioactive waste, an act which we believe will actually undermine public confidence. Furthermore, given also the immense importance of this decision to public safety, national security and the national interest, we believe urgent steps should be taken to review the Committee's process, its management and its sponsorship. (opinion)

  1. Regulatory framework for the management of radioactive wastes in Argentina

    International Nuclear Information System (INIS)

    D'Amato, E.; Siraky, G.; Petraitis, E.; Novo, R.

    2000-01-01

    The legal and regulatory framework within which the radioactive waste management is carried out in Argentina are exposed. The activities of the Nuclear Regulatory Authority (ARN) in relation to facility inspections, safety assessments and collaboration with international agencies in the matter are also presented. Further, the regulatory criteria applied to waste management are reported. (author)

  2. Regulatory requirements important to Hanford single-shell tank waste management decisions

    International Nuclear Information System (INIS)

    Keller, J.F.; Woodruff, M.G.

    1989-06-01

    This report provides an initial analysis of the regulations that may be pertinent to SST management activities (e.g., characterization, disposal, retrieval, processing, etc.) and the interrelationships among those regulations. Waste disposal decisions regarding SST waste must consider the regulatory requirements against which technical solutions will be evaluated. Regulatory requirements can also be used as guidelines for management and disposal of waste in a manner that protects human health and safety and the environment. Also, in cases where waste management regulations do not specifically address a waste form, such as radioactive mixed waste, the SST waste may come under the purview of a number of regulations related to radioactive waste management, hazardous waste management, and water and air quality protection. This report provides a comprehensive review of the environmental pollution control and radioactive waste management statutes and regulations that are relevant to SST waste characterization and management. Also, other statutes and regulations that contain technical standards that may be used in the absence of directly applicable regulations are analyzed. 8 refs., 4 figs

  3. 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.)

  4. Medical Waste Management Training for Healthcare Managers - a Necessity?

    Directory of Open Access Journals (Sweden)

    Aclan Ozder

    2013-07-01

    Full Text Available Background:This is an interventional study, since a training has been given, performed in order to investigate whether training has significant impact on knowledge levels of healthcare managers (head-nurses, assistant head nurses, hospital managers and deputy managers regarding bio-medical waste management.Methods:The study was conducted on 240 volunteers during June – August 2010 in 12 hospitals serving in Istanbul (private, public, university, training-research hospitals and other healthcare institutions. A survey form prepared by the project guidance team was applied to the participants through the internet before and after the training courses. The training program was composed of 40 hours of theory and 16 hours of practice sessions taught by persons known to have expertise in their fields. Methods used in the analysis of the data chi-square and t-tests in dependent groups.Results:67.5% (162 of participants were female. 42.5% (102 are working in private, and 21.7% in state-owned hospitals. 50.4% are head-nurses, and 18.3% are hospital managers.A statistically significant difference was found among those who had received medical waste management training (preliminary test and final test and others who had not (p<0.01. It was observed that information levels of all healthcare managers who had received training on waste management had risen at the completion of that training session.Conclusion:On the subject of waste management, to have trained healthcare employees who are responsible for the safe disposal of wastes in hospitals is both a necessity for the safety of patients and important for its contribution to the economy of the country.

  5. Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. Fourth National Report on Compliance with the Joint Convention Obligations. France

    International Nuclear Information System (INIS)

    2011-09-01

    The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, hereinafter referred to as the 'Joint Convention', is the result of international discussions that followed the adoption of the Convention on Nuclear Safety, in 1994. France signed the Joint Convention at the General Conference of the International Atomic Energy Agency (IAEA) held on 29 September 1997, the very first day the Joint Convention was opened for signature. She approved it on 22 February 2000 and filed the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in the pursuit of international actions to reinforce nuclear safety and considers the Joint Convention to be a key step in that direction. The fields covered by the Joint Convention have long been part of the French approach to nuclear safety. This report is the fourth of its kind. It is published in accordance with Article 32 of the Joint Convention and presents the measures taken by France to meet each of her obligations set out in the Convention. The facilities and radioactive materials covered by the Joint Convention are much diversified in nature and are controlled in France by different regulatory authorities (see Section E). Over and above a specific threshold of radioactive content, a facility is referred to as a 'basic nuclear facility' (installation nucleaire de base - INB) and placed under the control of the French Nuclear Safety Authority (Autorite de surete nucleaire - ASN). Below that threshold and provided that the facility involved falls under a category of the nomenclature of classified facilities for other purposes than their radioactive materials, any facility may be considered as a 'classified facility on environmental-protection grounds' (installation classee pour la protection de l'environnement - ICPE) and placed under the control of the Ministry for the

  6. 340 Waste Handling Facility interim safety basis

    International Nuclear Information System (INIS)

    Bendixsen, R.B.

    1995-01-01

    This document establishes the interim safety basis (ISB) for the 340 Waste Handling Facility (340 Facility). An ISB is a documented safety basis that provides a justification for the continued operation of the facility until an upgraded final safety analysis report is prepared that complies with US Department of Energy (DOE) Order 5480.23, Nuclear Safety Analysis Reports. The ISB for the 340 Facility documents the current design and operation of the facility. The 340 Facility ISB (ISB-003) is based on a facility walkdown and review of the design and operation of the facility, as described in the existing safety documentation. The safety documents reviewed, to develop ISB-003, include the following: OSD-SW-153-0001, Operating Specification Document for the 340 Waste Handling Facility (WHC 1990); OSR-SW-152-00003, Operating Limits for the 340 Waste Handling Facility (WHC 1989); SD-RE-SAP-013, Safety Analysis Report for Packaging, Railroad Liquid Waste Tank Cars (Mercado 1993); SD-WM-TM-001, Safety Assessment Document for the 340 Waste Handling Facility (Berneski 1994a); SD-WM-SEL-016, 340 Facility Safety Equipment List (Berneski 1992); and 340 Complex Fire Hazard Analysis, Draft (Hughes Assoc. Inc. 1994)

  7. Safe Management and disposal of nuclear waste. Volume 3

    International Nuclear Information System (INIS)

    1993-01-01

    These proceedings of the international conference Safewaste 93, volume 3 are divided into three poster sessions bearing on: poster session P-1: Radioactive waste management and actinide burning; poster session P-2: Safety aspects of radioactive waste disposal; poster session P-3: Transport and disposal

  8. Better safe than sorry: Increasing safety in radioactive waste management

    International Nuclear Information System (INIS)

    Gaspar, Miklos; Mutluer, Adem

    2015-01-01

    Abderrahim Bouih used to be worried about space. In charge of managing Morocco’s radioactive waste since 2006, he had long projected that the country’s sole radioactive waste facility would fill up by 2019. Thanks to a new methodology he and his colleagues learned through an IAEA project, they can now dismantle smoke detectors, lightning rods and other waste that contains radioactive material, safely separating the radioactive components from the metal, and significantly reducing the amount of radioactive waste they need to store. “We have condensed 60 drums of waste into just two,” said Bouih, Head of the Radioactive Waste Collection, Treatment and Storage Unit at the Moroccan National Centre for Nuclear Energy, Sciences and Technology. “This means our site won’t fill up for another 16 years.”

  9. Publicly administrated nuclear waste management research programme 1994-1996. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Vuori, S. [ed.] [VTT Energy, Espoo (Finland)

    1997-09-01

    The main objective of the JYT-programme has been to provide the authorities with independent information and research results relevant for the safety of nuclear waste management. The main emphasis in this research programme has been devoted to the final disposal of spent fuel. The whole area of the research programme has been subdivided into following main topic areas: (1) bedrock structure and stability, rock investigation methods and characteristics and flow of ground water, (2) release of radionuclides from a repository and subsequent transport in the bedrock, (3) performance and safety assessment of repositories and other phases of nuclear waste management, (4) natural analogue studies, (5) waste management technology and costs and (6) socio political and other societal issues and environmental impact assessment.

  10. Publicly administrated nuclear waste management research programme 1994-1996. Final report

    International Nuclear Information System (INIS)

    Vuori, S.

    1997-09-01

    The main objective of the JYT-programme has been to provide the authorities with independent information and research results relevant for the safety of nuclear waste management. The main emphasis in this research programme has been devoted to the final disposal of spent fuel. The whole area of the research programme has been subdivided into following main topic areas: (1) bedrock structure and stability, rock investigation methods and characteristics and flow of ground water, (2) release of radionuclides from a repository and subsequent transport in the bedrock, (3) performance and safety assessment of repositories and other phases of nuclear waste management, (4) natural analogue studies, (5) waste management technology and costs and (6) socio political and other societal issues and environmental impact assessment

  11. Feed Materials Production Center Waste Management: Annual report for fiscal year 1986

    International Nuclear Information System (INIS)

    Watts, R.E.; Kottner, S.A.

    1986-01-01

    During FY-1986, the Westinghouse Materials Company of Ohio (WMCO) and the Department of Energy focused on safe storage and disposition of all wastes at the Feed Materials Production Center (FMPC) in compliance with federal and state regulations concerning waste management and worker health and safety. The Waste Management Annual Report identifies the comprehensive programs developed to achieve WMCO goals at the FMPC. The programs address waste issues which concern worker and public health and safety. Among those programs discussed are the decontamination, safe storage, and disposition of low-level and mixed hazardous radioactive waste. Principal attention and resources were allocated to programs which identify the largest waste streams (both currently generated and inventory backlogged). The most voluminous waste streams include low-level waste approved for shipment to the Nevada Test Site (MgF 2 slag, slag leach filter cake, and neutralized raffinate); remedial action wastes (K-65, stormwater runoff/effluent, and waste pits); thorium; and contaminated construction rubble and soil. Goals were established and met for the Waste Management Section in the form of completed milestones. The completed milestones involved such activities as characterization studies for the waste pits, K-65 Silos and adjacent areas; issuance of the Waste Management Plan required by DOE; analysis of decontamination alternatives for copper scrap; and analysis of silo structural integrity and remedial action alternatives

  12. The Research Results of Radioactive Waste Management Technology Center Year 1997/1998

    International Nuclear Information System (INIS)

    1998-12-01

    The research results of Radioactive Waste Management Technology Center, National Atomic Energy Agency of Indonesia year 1997/1998 contain paper as form of research results on radioactive waste management related fields. There were included many aspects such as radioactive waste processing, storage, decontamination, decommissioning, safety and environmental aspects. There are 26 papers indexed individually (ID)

  13. The Radioactive Waste Management course: 14 High-yield editions

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  14. Radioactive waste data base through the net: A tool to improve the development of waste management

    International Nuclear Information System (INIS)

    Sanhueza Mir, Azucena

    2003-01-01

    One of the duties in Chilean Commission for Nuclear Energy (CCHEN) is the timely reply to the International Atomic Energy Agency (IAEA) Net enable waste management data base (NEWMDB) in the waste management field. This duty is carried out by the Radioactive Waste Management Section. CCHEN has complete this data base from about one decade ago. Through the time, the data base has changed according to new available information technologies, to the point that the access using the international net is a need today. The NEWMDB objective is to exchange information and knowledge between member states related to radioactive waste management situation and to conform a world inventory of radioactive waste. The Chilean experience got from the NEWMDB first data collection cycle (1999-2000) is presented here, and recommendations to be considered for incorporation in the domestic waste management system are exposed. In so doing, the data base answer should be easy to do and totally understood by everyone whose job is waste management around the world, in the context of the glossary, criteria and conventions on this data base is supported. The composition of the NEWMDB considers a General Frame which indicates the way in which the waste management is enfaced in the country, regulations, authorities, policies, infrastructure; a Waste Classification matrix which give the equivalence between proper country waste classification and that recommended by IAEA; Waste Data which give the quantities and situation of waste in the different steps of the management such as: conditioned waste, unconditioned stored waste, etc. Finally, the Sustainable Development for radioactive waste management Indicators (SDI) for the safety and environmental radioactive waste management are estimated (Au)

  15. RAF 9054 - Strengthening Radioactive Waste Management in Africa

    International Nuclear Information System (INIS)

    Atogo, M.

    2017-01-01

    Radioactive waste is waste that contains Radioactive Material . It is usually a by-product of nuclear power generation and other applications of nuclear fission or nuclear technology, such as research and medicine. Radioactive waste management is a requirement to protect human beings and the environment from radioactive hazards now and for the long term. The application of management system requirements shall be graded to deploy resources at appropriate levels. Grading should not be used as a justification for not applying all of the necessary management system elements or required quality controls. The classification of RW is important to allow for easy handling and transportation and enhancement of safety while going through the process of waste management. The AFRA project “Strengthening Waste Management Infrastructure”, RAF/4/015 was initiated in 1996 by the IAEA. The objective of the project was to build the RWM infrastructure of AFRA member state. A follow-up project “Sustaining Waste Management Infrastructure”, RAF/3/005, was approved in 2005 for a duration of 5 years to help sustain the RWM capabilities and programs initiated in the AFRA member states as well as to help the new African countries joining the IAEA. RAF 9054 provides for a framework for the formulation of relevant legislations and technical skills for the establishment for a framework for the safe management of radioactive waste

  16. System study of alternative waste management techniques: Final report

    International Nuclear Information System (INIS)

    1986-01-01

    This report summarizes the important results achieved in conjunction with the Research and Development Priority ''Alternative Waste Management Techniques'' sponsored by the Federal Ministry of Research and Technology from 1981 to 1984. The subject of these studies was solely ''direct disposal'' of spent fuel elements. For this purpose a reference concept was selected from a variety of possible processes and engineered in detailed form by firms in the nuclear industry. Those who worked on the engineering concepts consider this waste management method technically feasible. Several disposal casks have been fabricated. The basic licensability of direct disposal can be evaluated on the basis of the documentation developed by the companies. The direct disposal method was compared with the ''integrated waste management concept'' using reference fuel cycles with respect to the following criteria: radiological safety and nuclear material safeguards and, in addition, economic and energy-policy aspects. It was found that with respect to radiological safety, including the long-term safety of the final repository, there are no significant differences between the two fuel cycles with and without reprocessing. With respect to the nuclear material safeguards of a final repository containing spent fuel elements, there are still a number of unanswered questions. From an economic standpoint, direct disposal will be more economical in the foreseeable future than integrated waste management. Quantification of the effects of one or the other waste management method on the national economy is not necessarily possible. Reprocessing is supported primarily by technological and energy-policy considerations. On the basis of the results, the conclusion is reached that reprocessing should be pursued further, but that at the same time direct disposal should be developed to the point of practical maturity

  17. The Research Results of Radioactive Waste Management Technology Center Year 1996/1997

    International Nuclear Information System (INIS)

    Budiman, P.; Martono, H.; Las, T.; Lubis, E.; Mulyanto; Wisnubroto, D. S.; Sucipta

    1997-12-01

    The research results of Radioactive Waste Management Technology Center, National Atomic Energy Agency of Indonesia year 1996/1997 contain paper as form of research results on radioactive waste management related fields. There were included many aspects such as radioactive waste processing, storage, decontamination, decommissioning, safety and environmental aspects. There are 24 papers and 12 short communications indexed individually(ID)

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

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  19. Safety aspects of radioactive waste transportation and storage in the Republic of Moldova

    International Nuclear Information System (INIS)

    Gasca, Iu.

    2009-01-01

    A special attention continues to be given to the management of radioactive wastes. The National Department of Radioactive Waste Management is a unique institute in Moldova that deals with reception, transportation and storage of radioactive wastes. It collaborates with International Atomic Energy Agency. The management of low- and intermediate-level waste has remained permanently focused at the IAEA work. In 2003 IAEA supported the construction and technique of low-level and intermediate-level radioactive waste repository in Moldova. During 2003-2005 the US Department of Energy supported financing of planning and building of the underground storage for keeping the installations with high-level radioactive sources with all safety systems (signalization, video-monitoring). In 2008 the construction of radioactive wastes conditioning station was initiated with support of the US Embassy's Bureau for military cooperation

  20. Status of the Canadian Nuclear Fuel Waste Management Program

    International Nuclear Information System (INIS)

    Lyon, R.B.

    1985-10-01

    The Canadian Nuclear Fuel Waste Management Program is in the fifth year of a ten-year generic research and development phase. The major objective of this phase of the program is to assess the basic safety and environmental aspects of the concept of isolating immobilized fuel waste by deep underground disposal in plutonic rock. The major scientific and engineering components of the program, namely immobilization studies, geoscience research, and environmental and safety assessment, are well established

  1. Alpha waste management at the Valduc Research Center

    International Nuclear Information System (INIS)

    Jouan, A.; Cartier, R.; Durec, J.P.; Flament, T.

    1995-01-01

    Operation of the reprocessing facilities at the Valduc Research Center of the French Atomic Energy Commission (CEA) generates waste with a variety of characteristics. The waste compatible with surface storage requirements is transferred to the French Radioactive Waste Management Agency (ANDRA); rest is reprocessed under a program which enables storage in compliance with the requirements of permits issued by safety Authorities. The waste reprocessing program provides for the construction of an incinerator capable of handling nearly all of the combustible waste generated by the Center and vitrification facility for treating liquid waste generated by the plutonium handling plant. (authors)

  2. Current policy and research on radioactive waste management in the European Union

    International Nuclear Information System (INIS)

    Forsstroem, H.; Taylor, D.M.

    2000-01-01

    Each Member State of the European Union is responsible for the safe management and disposal of the radioactive waste produced on its own territory. This includes setting the policy and taking the necessary steps to ensure that the radioactive waste does not constitute a threat to the health of workers and to the general public. For the practical implementation of the policy, specific waste management organizations have been established. Extensive cooperation, not least in the area of research, is taking place between these organizations and between the regulatory authorities, both bilaterally and through the European Commission. Cooperation takes place through the European Commission by two different mechanisms, the Community Plan of Action in the field of radioactive waste and the EURATOM framework programme on research and training. In view of the future enlargement of the European Union, the Commission is also actively involved in the development of waste management practices in the Central and Eastern European countries. Waste management is also an important aspect of the Tacis and other nuclear safety support programmes to the States of the former Soviet Union. The general policies for waste management in all Member States are in harmony with the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The specific policies are, however, dependent on the specific conditions of that State, e.g. the existence, size and time perspective of the nuclear power programme, the geological formations available for disposal (clay, salt, crystalline rock), etc. The management of short lived waste is an established practice in many Member States and the research needs are consequently low. Most of the policy efforts and research are thus dedicated to the management, treatment, conditioning and geological disposal of long lived waste and spent fuel. Each Member State with a nuclear power programme also has an important

  3. Safety Assessment Context for Croatian Low and Intermediate Level Radioactive Waste Repository

    International Nuclear Information System (INIS)

    Levanat, I.; Lokner, V.

    1998-01-01

    Safety assessments in a small country are usually performed to support the national waste management strategy, demonstrating compliance with national regulation for a particular facility. However, this assessment should - quite generally - provide reasonable assurance both to the public and to decision makers than the Croatian share of LILW from NPP Krsko can be safely disposed in Croatia. More specifically, assessment should clearly present all realistic options and compare the associated long term repository performances, demonstrating that desirable safety goals can be archived by an appropriate choice of (a) location, (b) facility design, (c) institutional control period and (d) waste acceptance criteria. As relevant national legislation is presently under review, generally recognized international safety standards, criteria and recommendations (e.g. as presented in the recent IAEA publications) should provide guidance for the assessment evaluation, since it is expected that they will be incorporated in the new national regulations. Finally, since Croatian radioactive waste management strategy is yet to be developed, such an assessment may contribute to its formulation and facilitate some specific decisions. (author)

  4. Answers to questions on National Report of the Slovak Republic. Compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2006

    International Nuclear Information System (INIS)

    2003-04-01

    Slovakia is pleased to present to the State Parties of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management the Answers to questions received on the National Report of the Slovak Republic compiled according to the terms of the Joint Convention (2005). Slovakia is ready to provide additional explanations to these Answers during the 2 nd Review Meeting. In the Annexes the 541/2004 Coll. LL. Act of 9 September 2004 on Peaceful Use of Nuclear Energy (Atomic Act) and on Alternations and Amendments to Some Acts

  5. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dixon, R.S.

    1984-12-01

    The Canadian Nuclear Fuel Waste Management Program involves research into the storage and transportation of used nuclear fuel, immobilization of fuel waste, and deep geological disposal of the immobilized waste. The program is now in the fourth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the safety and environmental aspects of the deep underground disposal of immobilized fuel waste in plutonic rock. The objectives of the research for each component of the program and the progress made to the end of 1983 are described in this report

  6. Methodology for estimating accidental radioactive releases in nuclear waste management

    International Nuclear Information System (INIS)

    Levy, H.B.

    1979-01-01

    Estimation of the risks of accidental radioactive releases is necessary in assessing the safety of any nuclear waste management system. The case of a radioactive waste form enclosed in a barrier system is considered. Two test calculations were carried out

  7. The management and regulation of decommissioning wastes

    International Nuclear Information System (INIS)

    Berkhout, F.

    1990-01-01

    Radioactive waste management is an inevitable consequence of nuclear technology. In the past it was often regarded as a peripheral matter, easily dealt with, and having little impact on the economics of the fuel cycle. Gradually, over the last two decades, waste management has asserted itself as one of nuclear power's most intractable problems. First, it is a problem of trying to understand through science the effects of discharging and disposing of man-made radioactivity to the general environment. Second, technologies for treating and disposing of the wastes, as well as techniques to verify their safety, must be developed. Third, and most problematically, a wide spread of public trust in the techniques of management must be nurtured. Disputes over each of these dimensions of the question exist in nearly all countries with nuclear programmes. Some of them may be near resolution, but many others are far from closure. Decommissioning, because it comes last in the nuclear life-cycle, is also the last important aspect of the technology to be considered seriously. In Britain, wastes arising from decommissioning, whether it is done slowly or quickly, are projected to have an important impact on the scale of radioactive waste management programmes, beginning in the mid-1990s. It follows that decommissioning, contentious in itself, is likely to exacerbate the difficulties of waste management. (author)

  8. A review of mechanochemistry applications in waste management

    International Nuclear Information System (INIS)

    Guo Xiuying; Xiang Dong; Duan Guanghong; Mou Peng

    2010-01-01

    Mechanochemistry is defined to describe the chemical and physicochemical transformation of substances during the aggregation caused by the mechanical energy. Mechanochemical technology has several advantages, such as simple process, ecological safety and the possibility of obtaining a product in the metastable state. It potentially has a prospective application in pollution remediation and waste management. Therefore, this paper aims to give an overall review of the mechanochemistry applications in waste management and the related mechanisms. Based on our study, the modification of fly ash and asbestos-containing wastes (ACWs) can be achieved by mechanochemical technology. Waste metal oxides can be transformed into easily recyclable sulfide by mechanochemical sulfidization. Besides, the waste plastics and rubbers, which are usually very difficult to be recycled, can also be recycled by mechanochemical technology.

  9. Status report on resolution of Waste Tank Safety Issues at the Hanford Site. Revision 1

    International Nuclear Information System (INIS)

    Dukelow, G.T.; Hanson, G.A.

    1995-05-01

    The purpose of this report is to provide and update the status of activities supporting the resolution of waste tank safety issues and system deficiencies at the Hanford Site. This report provides: (1) background information on safety issues and system deficiencies; (2) a description of the Tank Waste Remediation System and the process for managing safety issues and system deficiencies; (3) changes in safety issue description, prioritization, and schedules; and (4) a summary of the status, plans, order of magnitude, cost, and schedule for resolving safety issues and system deficiencies

  10. 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)

  11. Regulations for the safe management of radioactive wastes and spent nuclear fuel

    International Nuclear Information System (INIS)

    Voica, Anca

    2007-01-01

    The paper presents the national, international and European regulations regarding radioactive waste management. ANDRAD is the national authority charged with nation wide coordination of safe management of spent fuel and radioactive waste including their final disposal. ANDRAD's main objectives are the following: - establishing the National Strategy concerning the safety management of radioactive waste and spent nuclear fuel; - establishing the national repositories for the final disposal of the spent nuclear fuel and radioactive waste; - developing the technical procedures and establishing norms for all stages of management of spent nuclear fuel and radioactive waste, including the disposal and the decommissioning of the nuclear and radiologic facilities

  12. An approach for the reasonable TRU waste management in NUCEF

    International Nuclear Information System (INIS)

    Mineo, H.; Dojiri, S.; Takeshita, I.; Tsujino, T.; Matsumura, T.; Nishizawa, I.; Sugikawa, S.

    1995-01-01

    The Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF) has started its hot operation at the beginning of 1995, where TRU (transuranic) elements are used. The management of TRU waste arisen in the facility is very important issue. Liquid and solid wastes containing TRU elements are generated mainly from the Fuel Treatment System for critical experiments and from the researches of reprocessing process and TRU waste management for reprocessing plants using hot cells and glove-boxes. The TRU waste management in NUCEF is based on the classification of waste, and is to maximize the recycle of reagents and the reuse of TRU elements separated from the waste, as well as to reduce the waste volume and to lower the risk of waste by advanced separation and solidification. In the future, the separation and solidification of TRU elements in the tanks of liquid waste, and the classification and discrimination of solid wastes, will be carried out applying the outcomes of the development by the researches in NUCEF. (authors)

  13. Economic optimization of nuclear waste management

    International Nuclear Information System (INIS)

    DeWames, R.E.; Grantham, L.F.; Guon, J.; McKisson, R.L.

    1984-01-01

    The paper presented here addresses the impact of waste management system operating parameters on overall system economics. The conclusion reached by this study is that currently available technology and proposed operating conditions do not lead to optimum economics. The decision to utilize the current reference waste package and non-optimum operating conditions will cause added expenditures of 7 billion dollars over the next several decades. Further, this paper points out that optimum economics is not necessarily incompatible with improved system safety

  14. Waste Isolation Pilot Plant Safety Analysis Report

    International Nuclear Information System (INIS)

    1995-11-01

    The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions'' (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.'' This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment

  15. Waste Isolation Pilot Plant Safety Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-11-01

    The following provides a summary of the specific issues addressed in this FY-95 Annual Update as they relate to the CH TRU safety bases: Executive Summary; Site Characteristics; Principal Design and Safety Criteria; Facility Design and Operation; Hazards and Accident Analysis; Derivation of Technical Safety Requirements; Radiological and Hazardous Material Protection; Institutional Programs; Quality Assurance; and Decontamination and Decommissioning. The System Design Descriptions`` (SDDS) for the WIPP were reviewed and incorporated into Chapter 3, Principal Design and Safety Criteria and Chapter 4, Facility Design and Operation. This provides the most currently available final engineering design information on waste emplacement operations throughout the disposal phase up to the point of permanent closure. Also, the criteria which define the TRU waste to be accepted for disposal at the WIPP facility were summarized in Chapter 3 based on the WAC for the Waste Isolation Pilot Plant.`` This Safety Analysis Report (SAR) documents the safety analyses that develop and evaluate the adequacy of the Waste Isolation Pilot Plant Contact-Handled Transuranic Wastes (WIPP CH TRU) safety bases necessary to ensure the safety of workers, the public and the environment from the hazards posed by WIPP waste handling and emplacement operations during the disposal phase and hazards associated with the decommissioning and decontamination phase. The analyses of the hazards associated with the long-term (10,000 year) disposal of TRU and TRU mixed waste, and demonstration of compliance with the requirements of 40 CFR 191, Subpart B and 40 CFR 268.6 will be addressed in detail in the WIPP Final Certification Application scheduled for submittal in October 1996 (40 CFR 191) and the No-Migration Variance Petition (40 CFR 268.6) scheduled for submittal in June 1996. Section 5.4, Long-Term Waste Isolation Assessment summarizes the current status of the assessment.

  16. Geological safety aspects of nuclear waste disposalin in Finland

    Energy Technology Data Exchange (ETDEWEB)

    Ahonen, L; Hakkarainen, V; Kaija, J; Kuivamaki, A; Lindberg, A; Paananen, M; Paulamaki, S; Ruskeeniemi, T

    2011-07-01

    The management of nuclear waste from Finnish power companies is based on the final geological disposal of encapsulated spent fuel at a depth of several hundreds of metres in the crystalline bedrock. Permission for the licence requires that the safety of disposal is demonstrated in a safety case showing that processes, events and future scenarios possibly affecting the performance of the deep repository are appropriately understood. Many of the safety-related issues are geological in nature. The Precambrian bedrock of Finland has a long history, even if compared with the time span considered for nuclear waste disposal, but the northern location calls for a detailed study of the processes related to Quaternary glaciations. This was manifested in an extensive international permafrost study in northern Canada, coordinated by GTK. Hydrogeology and the common existence of saline waters deep in the bedrock have also been targets of extensive studies, because water chemistry affects the chemical stability of the repository near-field, as well as radionuclide transport. The Palmottu natural analogue study was one of the international high-priority natural analogue studies in which transport phenomena were explored in a natural geological system. Currently, deep biosphere processes are being investigated in support of the safety of nuclear waste disposal. (orig.)

  17. Development and application of safety and waste management protocols for the Laboratorio de Ingenieria Quimica

    International Nuclear Information System (INIS)

    Scott Jimenez, Stephanie

    2014-01-01

    Security and waste management protocols are developed for the laboratory de la Escuela de Ingenieria Quimica at the Universidad de Costa Rica. The protocols are elaborated according to the provisions and guidelines stipulated in the Costa Rican legislation, technical references and documents issued by the chemical regency of the Universidad de Costa Rica. An inspection guide was prepared and applied as diagnostic tool for the evaluation of the safety conditions and handling of chemical substances in the laboratory. Inspections of the physical plant and interviews to area managers were realized. The results obtained have allowed to implement improvements of the activities in safe working environment conditions and teaching; and an adequate signaling and demarcation of the facilities, location and recharge of fire extinguishers. An emergency plan is elaborated for the Laboratorio de Ingenieria Quimica, by performing a sequence of stages proposed by Comision Nacional de Emergencias. In addition, a plan for the safe and effective management of waste generated is made based on the reagents most frequently used in the different practices. The method of storage Flinn Scientific was selected as the most appropriate method to organize and distribute chemicals in the laboratory reagent storage area, obtaining the highest percentage in the decision matrix. Security aspects in the registration and documentation system implemented in the laboratory administration are evaluated by a checklist. This assessment has allowed to propose improvements, to increase the efficiency and to obtain an easy storage, control and a fast search of the information by means of the procedures documented and elaborated. Some of the recommendations proposed have been the establishment of an emergency action committee, the reduction of unnecessary quantities of chemicals stored, training on safety, operation of fire extinguisher and first aid; and construction of an emergency exit, etc. [es

  18. Signs of progress. IAEA perspectives on radioactive waste management

    International Nuclear Information System (INIS)

    ElBaradei, M.

    2000-01-01

    From various perspectives, the issue of radioactive waste management is a compelling one. There are, for example, different levels and categories of waste, different storage and disposal methods, and different siting and environmental requirements. The differences reflect the issue's complexity. Regrettably they also can serve to cloud public perceptions about the issue as a whole. We should not lose sight of communicating a broader ''holistic approach'' - all types of generated radioactive wastes need to be managed safely and we should intensify efforts to clarify the complex picture and further advance public understanding. The main goal we are pursuing is the protection of public health, safety, and the environment in which we live. Fortunately, notable progress is being made through international cooperation in radioactive waste management to resolve common problems and bring us closer toward achieving this goal for all types of radioactive wastes

  19. Oak Ridge National Laboratory Waste Management Plan, fiscal year 1994

    International Nuclear Information System (INIS)

    Turner, J.W.

    1993-12-01

    US Department of Energy (DOE) Order 5820.2A was promulgated in final form on September 26, 1988. The order requires heads of field organizations to prepare and to submit updates on the waste management plans for all operations under their purview according to the format in Chap. 6, open-quotes Waste Management Plan Outline.close quotes These plans are to be submitted by the DOE Oak Ridge Operations Office (DOE-ORO) in December of each year and distributed to the DP-12, ES ampersand H-1, and other appropriate DOE Headquarters (DOE-HQ) organizations for review and comment. This document was prepared in response to this requirement for fiscal year (FY) 1994. The Oak Ridge National Laboratory (ORNL) waste management mission is reduction, collection, storage, treatment, and disposal of DOE wastes, generated primarily in pursuit of ORNL missions, in order to protect human health and safety and the environment. In carrying out this mission, waste management staff in the Waste Management and Remedial Action Division (WMRAD) will (1) guide ORNL in optimizing waste reduction and waste management capabilities and (2) conduct waste management operations in a compliant, publicly acceptable, technically sound, and cost-efficient manner. Waste management requirements for DOE radioactive wastes are detailed in DOE Order 5820.2A, and the ORNL Waste Management Program encompasses all elements of this order. The requirements of this DOE order and other appropriate DOE orders, along with applicable Tennessee Department of Environment and Conservation and US Environmental Protection Agency (EPA) rules and regulations, provide the principal source of regulatory guidance for waste management operations at ORNL. The objective of this document is compilation and consolidation of information on how the ORNL Waste Management Program is conducted, which waste management facilities are being used to manage wastes, what activities are planned for FY 1994, and how all of the activities are

  20. Risk and safety analyses for disposal of alpha-contaminated waste in INEL

    International Nuclear Information System (INIS)

    Smith, T.

    1982-01-01

    The author first discusses the context, objectives, and scope of the risk analysis. Then he gives some background on the waste and how its managed, including the alternatives for long-term management. These are followed by risk evaluation approach, results, and 7 conclusions and problems. One of his conclusions is that a 100 nCi/g limit would provide adequate safety margins. Raising the limit to 100 nCi/g would allow about 20% of the stored waste to be diverted to near-surface disposal. He added that analyzing waste packages at 10 nCi/g is not now practical. 21 figures

  1. 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)

  2. Alternative processes for managing existing commercial high-level radioactive wastes

    International Nuclear Information System (INIS)

    1976-04-01

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

  3. Hospital waste management in Lebanon

    International Nuclear Information System (INIS)

    Chaker, Alissar

    1999-01-01

    Hospital wastes comprises approximately 80% domestic waste components, also known as non-risk waste and 20% hazardous or risk waste. The 20% of the hospital waste stream or the risk waste (also known as infectious, medical, clinical wastes) comprises components which could be potentially contaminated with infections, chemical or radioactive agents. Therefore, it should be handled and disposed of in such a manner as to minimize potential human exposure and cross-contamination. Hospital risk waste and be subdivided into seven general categories as follows: infections, anatomical/pathological, chemical, pharmaceutical, radioactive waste, sharps and pressurised containers. These waste categories are generated by many types of health care establishments, including hospitals, clinics, infirmaries.... The document presents also tables of number of hospitals and estimated bed number in different regions in Lebanon; estimated hospital risk and non-risk waste generation per tonnes per day for the years 1998 until 2010 and finally sensitivity analysis of estimated generation of hospital risk waste in Lebanon per tonnes per day for the years 1998 until 2010. The management, treatment and disposal of hospital risk waste constitute important environmental and public safety issues. It is recognised that there is alack of infrastructure for the safe and environmentally acceptable disposal of hospital waste in Lebanon

  4. Developing a Pre-disposal radioactive waste management framework for malawi

    International Nuclear Information System (INIS)

    Guasi, Ephron

    2016-04-01

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

  5. Scientific and technical challenges of radioactive waste management

    International Nuclear Information System (INIS)

    Vira, J.

    1996-01-01

    In spite of considerable spending on research and technical development, the management of nuclear wastes continues to be a difficult issue in public decision making. The nuclear industry says that it has safe solutions for the ultimate disposal of nuclear wastes, but the message has not really got through to the public at large. Although communications problems reflect the general stigmatization of nuclear power, there are obvious issues in safety and performance assessment of nuclear waste disposal which evade scientific resolution. Any scientist is concerned for his personal credibility must respect the rules and limits of scientific practice, but the intriguing question is whether he would not do better to address the layman's worries about radioactive substances? The discussion in this paper points out the intricacies of the distinction between scientific proof and judgement, with emphasis on safety assessment for nuclear waste disposal. Who are the final arbitrators? In a democratic society it is probably those who vote.Building confidence in expert judgements is a challenge for waste managers and scientists. The media may create their own 'experts', whose only necessary credential is the trust of their audience, but scientific judgements must stand the test of time.'Confidence building' is currently a key word on the whole nuclear waste management scene, and confidence in science and scientists is certainly needed for any progress towards practical implementation of plans. The means for building confidence in the decision-making process are probably different from those applied for science and scientists. (author)

  6. Radioactive Waste Management - Community Policy and Research Initiatives. The sixth international conference on the management and disposal of radioactive waste - Euradwaste '04

    Energy Technology Data Exchange (ETDEWEB)

    Forsstroem, Hans [Research Directorate Energy, Nuclear Fission and Radiation Protection, European Commission, MO-75 5/37, 200 avenue de la Loi, B-1049 Brussels (Belgium); Ruiz, P Fernandez [DG Research, Energy, Consejo de Seguridad Nuclear, CSN, C/ Justo Dorado, 11, E-28040 Madrid (Spain)

    2004-07-01

    The sixth international conference on the management and disposal of radioactive waste organized be European Commission, held on 29-31 March 2004 in Luxembourg aimed to cover the following objectives: - To present EC policy in waste management, in particular the proposed 'Directive on the Management of Spent Nuclear Fuel and Radioactive Waste' and to discuss relating issues such as the effect on national programmes, site selection, EU added value, the case for EU safety standards, and various socio-political aspects; - To highlight the main results of the Fifth Framework Programme (FP5) of EURATOM for 'Nuclear Energy, Fission Research and Training Activities' in the field of waste in spent fuel management and disposal, and partitioning and transmutation; - To present examples of activities under FP5 and to discuss further research European integration through FP6. The program was divided into two main groups: 1. 'Community Policy and Socio-Political Aspects' which included sessions on community policy initiatives, disposal option, common safety standards and public involvement and acceptance; 2. 'Community Research Activities - FP5' which included sessions on partitioning and transmutation, geological disposal and research networking. There were 29 oral presentations and 36 poster presentations which, for the latter, allowed detailed presentations of the results of the EU-funded research projects. The conference was attended by some 240 participants from 27 countries.

  7. Reduction of waste arising as an option for improvement of waste management systems at NPPs with WWER type reactors

    International Nuclear Information System (INIS)

    Dultchenko, A.; Mikolaitchouk, H.

    1995-01-01

    After the USSR breakdown Ukraine inherited five NPPs with 12 WWER type reactor units and 4 RBMK type reactor units and no selected disposal site for NPP operational waste and just a few waste treatment facilities which had not been licensed or certified and could not be considered as complying safety requirements and NPP needs. At the same time the lack of competent designer organizations in Ukraine and the overall economical situation including the payment crisis resulted in significant delays in the development of radioactive waste management infrastructure and brought to the foreground a reduction of waste arisings and implementation of waste recycling technologies. In order to evaluate efficiency of waste management systems at Ukrainian NPPs in comparison with current practices at western NPPs and fix main deficiencies and optimum upgrading measures the comparative analyses of waste management systems at Ukrainian NPPs was initiated within the R and D program supported by the Ukrainian State Committee for Nuclear and Radiation Safety (UkrSCNRS). In carrying out the analyses the results of IAEA Technical Assistance Regional project on Advice on Waste Management at WWER type Reactors were used. Taking into account an influence of the Chernobyl accident consequences on the waste management system of Chernobyl NPP the case of Chernobyl NPP was set apart and cannot be considered typical so the authors confine their analysis to the WWER type reactors. For the purposes of comparison the related information about Kozlodui, Paks, Loviisa and Russian NPPs provided under the above-mentioned IAEA Regional Project was used

  8. Use of quality parameters system in sphere of the radioactive waste management

    International Nuclear Information System (INIS)

    Loginov, A.P.; Sandul, G.A.

    2003-01-01

    Quality parameters system is used at quality ensuring assessment for such concrete situations: change of quality, including safety, radioactive waste at the stepwise management with them (the treatment stage is considered); quality level comparison of the same type containers for radioactive waste disposal (two types of containers are considered: in the form of a parallelepiped and a cylinder); research of kinetic properties of those containers quality parameters which are function of time (reliability parameters and ecological parameters closely connected to them). The received results potentially can find practical application at an assessment of safety in process of radioactive waste management, at the development of containers for radioactive waste, at the decision of line of optimization problems with observance of ALARA principle and in other adjacent areas

  9. 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

  10. Obtention to the methodology for evaluation to the confirmation of the hazardous wastes safety isolation

    International Nuclear Information System (INIS)

    Peralta, J.L.; Gil, R.; Castillo, R.; Leyva, D.

    2003-01-01

    Taking into account, the practical experience of the safety assessment in the radioactive wastes management, the International Atomic Energy Agency (IAEA) recommendations in this topics, the norms and national and international legislation about noxious substances to the environment and their restriction limits, the best international practices and approaches of isolation hazardous wastes sites, a Methodology is developed (Cuba particular conditions) to obtaining and/or confirmation of the hazardous wastes safety isolation, as a tool able to carry out the assessment of facilities to build and all installation and/or place where hazardous wastes isolated from the environment. The Methodology, embraces the evaluation of technical, economic and social topics, allowing to develop an integral safety assessment which allows to estimate the environment possible impact for hazardous waste isolation (radioactive and non radioactive); Just are shown in this paper the selection approaches for the obtaining and/or evaluation of the best site, the steps description to continue for the definition of the main scenarios and the models to take into account in the valuation of the possible liberation and pathway to the environment of the non radioactive pollutants. The main contribution of this Methodology resides in the creation of a scientific-technique necessary guide for the evident demand of carrying out the most organized, effective and hazardous wastes safety management

  11. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dixon, R.S.; Rosinger, E.L.J.

    1984-04-01

    This report, the fifth of a series of annual reports, reviews the progress that has been made in the research and development program for the safe management and disposal of Canada's nuclear fuel waste. The report summarizes activities over the past year in the following areas: public interaction; used fuel storage and transportation; immobilization of used fuel and fuel recycle waste; geoscience research related to deep underground disposal; environmental research; and environmental and safety assessment

  12. Solid waste management

    OpenAIRE

    Srebrenkoska, Vineta; Golomeova, Saska; Zhezhova, Silvana

    2013-01-01

    Waste is unwanted or useless materials from households, industry, agriculture, hospitals. Waste materials in solid state are classified as solid waste. Increasing of the amount of solid waste and the pressure what it has on the environment, impose the need to introduce sustainable solid waste management. Advanced sustainable solid waste management involves several activities at a higher level of final disposal of the waste management hierarchy. Minimal use of material and energy resources ...

  13. The CEC contribution to radioactive waste management, decommissioning and related radiation protection issues

    International Nuclear Information System (INIS)

    Finzi, S.

    1991-01-01

    The Commission of the European Communities has, for more than 15 years, supported Research and Development (R and D) programmes on ''Radioactive Waste Management'' (since 1975) as well as on ''Decommissioning of Nuclear Installations'' (since 1979), which are carried out by research laboratories, universities, public organisations and private companies of the EC Member states, under shared-cost contracts. Under these contracts, the Commission of the European Communities generally funds up to 50% of the total cost of a research project. The main objective of the ''Radioactive Waste Management Programme'' is to ensure the safety of the waste management and disposal systems with the goal that the scientific and technological results can be used in practice on industrial scale with full respect for safety and environmental protection requirements. Studies have been performed on three main components of the radioactive waste management system, (i) the waste packages, (ii) the geological repository and (iii) the performance assessment, either through experiments or by theoretical evaluation. The current programme which has two main components, one on waste management, the other on the construction and operation of underground storage facilities, is discussed. (author)

  14. Balancing requirements for radioactive waste management and radiation protection

    International Nuclear Information System (INIS)

    Lafuma, J.; Lefevre, J.

    1985-01-01

    The authors recall the principles of radiation protection and their application to radioactive waste management. The dose limitation system applies to every stage in management. The accepted risk limits should be compared with the level of risk from other sources, particularly from natural radiation. The uncertainties associated with long-term estimates should not lead to unrealistic requirements. The optimum rules are to be obtained by discussion among those responsible for radiation protection, nuclear safety and radioactive waste management. Satisfactory, applicable rules can be worked out in the present state of the art [fr

  15. 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)

  16. Sustainable waste management through end-of-waste criteria development.

    Science.gov (United States)

    Zorpas, Antonis A

    2016-04-01

    The Waste Framework Directive 2000/98 (WFD) contains specific requirements to define end-of-waste criteria (EWC). The main goal of EWC is to remove and eliminate the administrative loads of waste legislation for safe and high-quality waste materials, thereby facilitating and assisting recycling. The target is to produce effective with high quality of recyclables materials, promoting product standardization and quality and safety assurance, and improving harmonization and legal certainty in the recyclable material markets. At the same time, those objectives aim to develop a plan in order to improve the development and wider use of environmental technologies, which reduce pressure on environment and at the same time address the three dimensions of the Lisbon strategy: growth, jobs and environment. This paper presents the importance of EWC, and the approach of setting EWC as EWC affect several management systems as well as sustainable and clean technologies.

  17. Probabilistic safety assessment for high-level waste tanks at Hanford

    International Nuclear Information System (INIS)

    Sullivan, L.H.; MacFarlane, D.R.; Stack, D.W.

    1996-01-01

    Los Alamos National Laboratory has performed a comprehensive probabilistic safety assessment (PSA), including consideration of external events, for the 18 tank farms at the Hanford Tank Farm (HTF). This work was sponsored by the Department of Energy/Environmental Restoration and Waste Management Division (DOE/EM)

  18. Radioactive waste management policy for nuclear power

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  19. Safety aspects in fuel reprocessing and radioactive waste management

    International Nuclear Information System (INIS)

    Agarwal, K.

    2018-01-01

    Nuclear energy is used for generation of electricity and for production of a wide range of radionuclides for use in research and development, healthcare and industry. Nuclear industry uses nuclear fission as source of energy so a large amount of energy is available from very small amount of fuel. As India has adopted c losed fuel cycle , spent nuclear fuel from nuclear reactor is considered as a material of resource and reprocessed to recovery valuable fuel elements. Main incentive of reprocessing is to use the uranium resources effectively by recovering/recycling Pu and U present in the spent fuel. This finally leads to a very small percentage of residual material present in spent nuclear fuel requiring their management as radioactive waste. Another special feature of the Indian Atomic Energy Program is the attention paid from the very beginning to the safe management of radioactive waste

  20. Introduction to Waste Management

    DEFF Research Database (Denmark)

    Christensen, Thomas Højlund

    2011-01-01

    Solid waste management is as old as human civilization, although only considered an engineering discipline for about one century. The change from the previous focus on public cleansing of the cities to modern waste management was primarily driven by industrialization, which introduced new materials...... and chemicals, dramatically changing the types and composition of waste, and by urbanization making waste management in urban areas a complicated and costly logistic operation. This book focuses on waste that commonly appears in the municipal waste management system. This chapter gives an introduction to modern...... waste management, including issues as waste definition, problems associated with waste, waste management criteria and approaches to waste management. Later chapters introduce aspects of engineering (Chapter 1.2), economics (Chapter 1.3) and regulation (Chapter 1.4)....

  1. Application of the new requirements of safety of the IAEA for the previous management to the final disposal of radioactive waste in the region: a personal vision

    International Nuclear Information System (INIS)

    Sed, Luis Andres Jova

    2013-01-01

    The work includes the requirements for the responsibilities associated with the management prior to the final disposal of radioactive waste and as they are referred to in the Region. Also discusses the requirements for the main stages of the management prior to the final disposal of radioactive waste. A very important section of the new requirements is that establish requirements for safe operation of facilities management prior to the final disposal of radioactive wastes and the implementation of activities under conditions of safety and development. The work is emphatic on the importance of safety justification since the beginning of the development of a facility as a basis for the decision-making and approval process. Emphasis is also on the gradual approach which should provide for the collection, analysis and interpretation of the relevant technical data, plans for the design and operation, and the formulation of the justification of the security. This paper gives a personal view of the situation in the Region

  2. Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Third review meeting. Questions asked to France and answers

    International Nuclear Information System (INIS)

    2009-01-01

    The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, referred to as the 'Joint Convention', is the result of international discussions that followed the adoption of the Convention on Nuclear Safety, in 1994. France signed the Joint Convention at the General Conference of the International Atomic Energy Agency (IAEA) held on 29 September 1997, the very first day the Joint Convention was opened for signature. She approved it on 22 February 2000 and filed the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in the pursuit of international actions to reinforce nuclear safety and considers the Joint Convention to be a key step in that direction. The fields covered by the Joint Convention have long been part of the French approach to nuclear safety. For his third report, France presented a document reflecting the viewpoints of the various stakeholders (regulatory authorities and operators). Thus, for each of the chapters in which the regulatory authority is not the only party to express its point of view, a three-stage structure was adopted: first of all a description by the regulatory authority of the regulations, followed by a presentation by the operators of the steps taken to meet the regulations and finally, an analysis by the regulatory authority of the steps taken by the operators. This third report was distributed in October 2008 to all Contracting Parties who asked 213 questions on the French report. France answered each of them in the present document

  3. Waste Management Program management plan. Revision 1

    International Nuclear Information System (INIS)

    1997-02-01

    As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management's objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL

  4. The principles of radioactive waste management. A publication within the RADWASS programme

    International Nuclear Information System (INIS)

    1995-01-01

    This publication defines the objective of radioactive waste management and the associated set of internationally agreed principles. The Safety Fundamentals include the objective of radioactive waste management and fundamental principles of radioactive waste management. The fundamental principles fall into the following general subject areas: protection of human health, protection of the environment, protection beyond national borders, responsibility to future generations and implementation procedures. Each principle is stated, and supporting and explanatory information pertaining to the principle is provided. 1 fig

  5. Radioactive wastes. Management

    International Nuclear Information System (INIS)

    Guillaumont, R.

    2001-01-01

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

  6. Cooperation in Nuclear Waste Management, Radiation Protection, Emergency Preparedness, Reactor Safety and Nuclear Non-Proliferation in Eastern Europe

    International Nuclear Information System (INIS)

    Dassen, Lars van; Delalic, Zlatan; Ekblad, Christer; Keyser, Peter; Turner, Roland; Rosengaard, Ulf; German, Olga; Grapengiesser, Sten; Andersson, Sarmite; Sandberg, Viviana; Olsson, Kjell; Stenberg, Tor

    2009-10-01

    The Swedish Radiation Safety Authority (SSM) is trusted with the task of implementing Sweden's bilateral assistance to Russia, Ukraine, Georgia, Belarus and Armenia in the fields of reactor safety, nuclear waste management, nuclear non-proliferation as well as radiation protection and emergency preparedness. In these fields, SSM also participates in various projects financed by the European Union. The purpose of this project-oriented report is to provide the Swedish Government and other funding agencies as well as other interested audiences in Sweden and abroad with an encompassing understanding of our work and in particular the work performed during 2008. the activities are divided into four subfields: Nuclear waste management; Reactor safety; Radiation safety and emergency preparedness; and, Nuclear non-proliferation. SSM implements projects in the field of spent nuclear fuel and radioactive waste management in Russia. The problems in this field also exist in other countries, yet the concentration of nuclear and radioactive materials are nowhere higher than in north-west Russia. And given the fact that most of these materials stem from the Cold War era and remain stored under conditions that vary from 'possibly acceptable' to 'wildly appalling' it is obvious that Sweden's first priority in the field of managing nuclear spent fuel and radioactive waste lies in this part of Russia. The prioritisation and selection of projects in reactor safety are established following thorough discussions with the partners in Russia and Ukraine. For specific guidance on safety and recommended safety improvements at RBMK and VVER reactors, SSM relies on analyses and handbooks established by the IAEA in the 1990s. In 2008, there were 16 projects in reactor safety. SSM implements a large number of projects in the field of radiation protection and emergency preparedness. The activities are at a first glance at some distance from the activities covered and foreseen by for instance the

  7. Cooperation in Nuclear Waste Management, Radiation Protection, Emergency Preparedness, Reactor Safety and Nuclear Non-Proliferation in Eastern Europe

    Energy Technology Data Exchange (ETDEWEB)

    Dassen, Lars van; Delalic, Zlatan; Ekblad, Christer; Keyser, Peter; Turner, Roland; Rosengaard, Ulf; German, Olga; Grapengiesser, Sten; Andersson, Sarmite; Sandberg, Viviana; Olsson, Kjell; Stenberg, Tor

    2009-10-15

    The Swedish Radiation Safety Authority (SSM) is trusted with the task of implementing Sweden's bilateral assistance to Russia, Ukraine, Georgia, Belarus and Armenia in the fields of reactor safety, nuclear waste management, nuclear non-proliferation as well as radiation protection and emergency preparedness. In these fields, SSM also participates in various projects financed by the European Union. The purpose of this project-oriented report is to provide the Swedish Government and other funding agencies as well as other interested audiences in Sweden and abroad with an encompassing understanding of our work and in particular the work performed during 2008. the activities are divided into four subfields: Nuclear waste management; Reactor safety; Radiation safety and emergency preparedness; and, Nuclear non-proliferation. SSM implements projects in the field of spent nuclear fuel and radioactive waste management in Russia. The problems in this field also exist in other countries, yet the concentration of nuclear and radioactive materials are nowhere higher than in north-west Russia. And given the fact that most of these materials stem from the Cold War era and remain stored under conditions that vary from 'possibly acceptable' to 'wildly appalling' it is obvious that Sweden's first priority in the field of managing nuclear spent fuel and radioactive waste lies in this part of Russia. The prioritisation and selection of projects in reactor safety are established following thorough discussions with the partners in Russia and Ukraine. For specific guidance on safety and recommended safety improvements at RBMK and VVER reactors, SSM relies on analyses and handbooks established by the IAEA in the 1990s. In 2008, there were 16 projects in reactor safety. SSM implements a large number of projects in the field of radiation protection and emergency preparedness. The activities are at a first glance at some distance from the activities covered and

  8. Use of a Knowledge Management System in Waste Management Projects

    International Nuclear Information System (INIS)

    Gruendler, D.; Boetsch, W.U.; Holzhauer, U.; Nies, R.A.

    2006-01-01

    In Germany the knowledge management system 'WasteInfo' about waste management and disposal issues has been developed and implemented. Beneficiaries of 'WasteInfo' are official decision makers having access to a large information pool. The information pool is fed by experts, so called authors This means compiling of information, evaluation and assigning of appropriate properties (metadata) to this information. The knowledge management system 'WasteInfo' has been introduced at the WM04, the operation of 'WasteInfo' at the WM05. The recent contribution describes the additional advantage of the KMS being used as a tool for the dealing with waste management projects. This specific aspect will be demonstrated using a project concerning a comparative analysis of the implementation of repositories in six countries using nuclear power as examples: The information of 'WasteInfo' is assigned to categories and structured according to its origin and type of publication. To use 'WasteInfo' as a tool for the processing the projects, a suitable set of categories has to be developed for each project. Apart from technical and scientific aspects, the selected project deals with repository strategies and policies in various countries, with the roles of applicants and authorities in licensing procedures, with safety philosophy and with socio-economic concerns. This new point of view has to be modelled in the categories. Similar to this, new sources of information such as local and regional dailies or particular web-sites have to be taken into consideration. In this way 'WasteInfo' represents an open document which reflects the current status of the respective repository policy in several countries. Information with particular meaning for the German repository planning is marked and by this may influence the German strategy. (authors)

  9. Waste Management Program management plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    As the prime contractor to the Department of Energy Idaho Operations Office (DOE-ID), Lockheed Martin Idaho Technologies Company (LMITCO) provides comprehensive waste management services to all contractors at the Idaho National Engineering and Environmental Laboratory (INEEL) through the Waste Management (WM) Program. This Program Management Plan (PMP) provides an overview of the Waste Management Program objectives, organization and management practices, and scope of work. This document will be reviewed at least annually and updated as needed to address revisions to the Waste Management`s objectives, organization and management practices, and scope of work. Waste Management Program is managed by LMITCO Waste Operations Directorate. The Waste Management Program manages transuranic, low-level, mixed low-level, hazardous, special-case, and industrial wastes generated at or transported to the INEEL.

  10. Radioactive waste management strategies: setting the scene

    International Nuclear Information System (INIS)

    Allan, C.J.

    1994-01-01

    This work deals with the radioactive waste management strategies. The objectives, concentrated on research and development activities to evaluate the safety and feasibility of various alternatives, on the selection of suitable disposal sites and on optimization studies covering safety, environmental, industrial and economical issues are presented. The disposal concepts for deep geological disposal are based on a combination of engineered barriers and the natural barrier provided by the host geological medium. Considerable efforts have been made to evaluate the behaviour of deep geological repositories with time, and their long-term safety and form the subject of the second part. The third part speaks about the incremental decision-making process that a number of countries are following in developing disposal facilities for nuclear fuel waste. The last part deals with public involvement which is required for establishing disposal facilities. (O.L.). 10 refs

  11. Current safety issues in the development of geological disposal of radioactive waste in France

    International Nuclear Information System (INIS)

    Raimbault, P.

    2002-01-01

    Deep geological disposal of high level and medium level long-lived waste in France is one of the three research paths defined by the law of 30th December 1991 on radioactive waste management. Research should be undertaken on: separation and transmutation of long-lived radionuclides in these waste; reversible or non reversible disposal in deep geological layers supported by investigations in underground laboratories; processes for conditioning and long term surface storage of these waste. In 2006, a global evaluation report on this research should be established by the Government and sent to the French Parliament. On this basis the Parliament should promulgate a law providing new objectives for the research and possibly presenting a framework for a deep disposal process. The French Nuclear Safety Authority has the responsibility to license the underground laboratories foreseen in the second research path and the nuclear facilities involved in the first and third research paths and make sure that existing high level and medium level long-lived waste currently produced are properly managed. It will give its advice on the safety aspects associated to the envisaged future management options. Its main concern is that results obtained in 2006 will be conclusive enough to take decisions for future orientations. Concerning the deep disposal option, under the responsibility of ANDRA (Agence Nationale pour la gestion des Dechets RAdioactifs), the construction of an underground laboratory has been authorized on the Bure site, in eastern France, and the shafts are under construction. The main issue is the level of investigations that may be performed in the host rock in order to support the feasibility study of a disposal concept on this site. Other issues are the elaboration of new safety standards to set a framework for a safety assessment of a disposal concept, the specifications for acceptance of waste packages in a future deep disposal, and relation of safety matters with

  12. Harmonization of industrial and oilfield waste management issues in Alberta

    International Nuclear Information System (INIS)

    Halla, S.

    1999-01-01

    There has been an ongoing discussion concerning the harmonization of waste management requirements within Alberta between the Alberta Energy and Utilities Board (EUB) and Alberta Environment (AENV), with the ultimate goal of publishing a memorandum of understanding (MOU) that will lay out the division of responsibilities between the two authorities on this matter. An overview is included of waste management in Alberta and of the harmonization agreements attained to date, with a stress on oil field waste issues. The EUB and AENV developed a MOE on the harmonization of waste management in Alberta, and a discussion is made of the concept of equivalency, which is used in the development of 'EUB guide 58: oilfield waste management requirements for the upstream petroleum industry' and will be a guiding principle for the MOU. Although the EUB's processes for waste management will not be exactly the same as AENV's, the EUB has made the commitment that, as a minimum, the requirements will provide the same level of environmental protection and public safety equivalent to that provided by AENV

  13. The management of radioactive wastes and the dismantling of nuclear installations in Spain

    International Nuclear Information System (INIS)

    Bouchet, Bertrand

    2014-08-01

    This report first presents the Spanish institutional framework, briefly presents the multi-year national plan of management of radioactive wastes, and indicates the origin and volume of radioactive wastes produced in Spain. It addresses the management of low and medium level wastes, the case of spent fuel and high level wastes (storage in pool and installations of temporary warehousing, project of a centralized temporary storage, the question of definitive management), and proposes an overview of R and D activities in the different domains of waste management in Spain: waste technology, technologies and processes of treatment, packaging and dismantling, materials and containment systems, behaviour and safety assessment, radiological protection and associated modelling, infrastructure and cooperation. The two last parts briefly address the funding of waste management and the dismantling of nuclear installations

  14. Re-defining the concepts of waste and waste management:evolving the Theory of Waste Management

    OpenAIRE

    Pongrácz, E. (Eva)

    2002-01-01

    Abstract In an attempt to construct a new agenda for waste management, this thesis explores the importance of the definition of waste and its impact on waste management, and the role of ownership in waste management. It is recognised that present legal waste definitions are ambiguous and do not really give an insight into the concept of waste. Moreover, despite its explicit wish of waste prevention, when according to present legislation a thing is assigned the label...

  15. Radioactive Waste Management - Community Policy and Research Initiatives. The sixth international conference on the management and disposal of radioactive waste - Euradwaste '04

    Energy Technology Data Exchange (ETDEWEB)

    Forsstroem, Hans [Research Directorate Energy, Nuclear Fission and Radiation Protection, European Commission, MO-75 5/37, 200 avenue de la Loi, B-1049 Brussels (Belgium); Ruiz, P. Fernandez (ed.) [DG Research, Energy, Consejo de Seguridad Nuclear, CSN, C/ Justo Dorado, 11, E-28040 Madrid (Spain)

    2004-07-01

    The sixth international conference on the management and disposal of radioactive waste organized be European Commission, held on 29-31 March 2004 in Luxembourg aimed to cover the following objectives: - To present EC policy in waste management, in particular the proposed 'Directive on the Management of Spent Nuclear Fuel and Radioactive Waste' and to discuss relating issues such as the effect on national programmes, site selection, EU added value, the case for EU safety standards, and various socio-political aspects; - To highlight the main results of the Fifth Framework Programme (FP5) of EURATOM for 'Nuclear Energy, Fission Research and Training Activities' in the field of waste in spent fuel management and disposal, and partitioning and transmutation; - To present examples of activities under FP5 and to discuss further research European integration through FP6. The program was divided into two main groups: 1. 'Community Policy and Socio-Political Aspects' which included sessions on community policy initiatives, disposal option, common safety standards and public involvement and acceptance; 2. 'Community Research Activities - FP5' which included sessions on partitioning and transmutation, geological disposal and research networking. There were 29 oral presentations and 36 poster presentations which, for the latter, allowed detailed presentations of the results of the EU-funded research projects. The conference was attended by some 240 participants from 27 countries.

  16. Latest developments in the predisposal of radioactive waste at the radioactive waste management department from ifin-hh

    International Nuclear Information System (INIS)

    Dragolici, F.; Dogaru, G.; Neacsu, E.

    2016-01-01

    The Radioactive Waste Management Department (DMDR) from IFIN-HH has a wide experience in the management of the non-fuel cycle radioactive wastes from all over Romania generated from nuclear techniques and technologies application, assuring the radiological safety and security of operators, population and environment. During 2011-2015 was implemented a major upgrading programme applied both on the technological systems of the building and on equipment. The paper describes the facility developments having the scope to share to the public and stakeholders the radioactive waste predisposal capabilities available at DMDR-IFIN-HH. As a whole, today DMDR-IFIN-HH represents a complete and complex infrastructure, assuring high quality services in all the steps related to the management of the institutional radioactive waste in Romania. (authors)

  17. Safety culture aspects of managing for safety. Experience of a large nuclear reprocessing site

    International Nuclear Information System (INIS)

    Rycraft, H.S.

    1996-01-01

    The Nuclear Industry is going through turbulent times both in terms of public acceptance and business issues. Safety is one area which impacts on whether the business is allowed to continue, and how an organisation organizes itself. The need to cut costs to make nuclear power a viable energy resource, has forced the nuclear utilities to review manning policies, and management style, and in particular how to maintain safety standards during a period of change, and ultimately support continuing improvement of standards. The shrinking workforce requires a new style of management, one that depends more on the people of the organisation taking responsibility for safety at all levels of the organisation. Not only personal safety but the safety of their colleagues, general public and the environment. The safety culture of an organisation is indivisible from the company culture, each aspect of a culture influences the whole and so the balance between business, safety and quality, has to be managed. BNFL provides a full fuel cycle service to nuclear power plants, and associated services to many national and international organisations. The following notes are taken from the work carried out in the company, and mostly at the Nuclear Reprocessing and Waste storage Site at Sellafield, based in the North West of England. Following the recent re-organisation, the site now employs 6200 people and has a further 1500 contractors working on construction activities on the site. Activities on the site range from remote handling to hands on tasks, involving highly active materials to low level waste. (author)

  18. Institute of Energy and Climate Research IEK-6. Nuclear waste management report 2013/2014. Material science for nuclear waste management

    Energy Technology Data Exchange (ETDEWEB)

    Neumeier, S.; Klinkenberg, M.; Bosbach, D. (eds.)

    2016-07-01

    This is the third bi-annual report of the Nuclear Waste Management section of the Institute of Energy and Climate Research (IEK-6) at Forschungszentrum Juelich since 2009 - almost a tradition. Our institute has seen two more years with exciting scientific work, but also major changes regarding nuclear energy in Germany and beyond. After the reactor accident in Fukushima (Japan) in 2011, it was decided in Germany to phase out electricity production by nuclear energy by 2022. It seems clear, that the decommissioning of the nuclear power plants will take several decades. The German nuclear waste repository Konrad for radioactive waste with negligible heat generation (all low level and some of the intermediate level radioactive waste) will start operation in the next decade. The new site selection act from 2013 re-defines the selection procedure for the German high level nuclear waste repository. Independently of the decision to stop electricity production by nuclear energy, Germany has to manage and ultimately dispose of its nuclear waste in a safe way. Our basic and applied research for the safe management of nuclear waste is focused on radiochemistry and materials chemistry aspects - it is focused on the behaviour of radionuclides and radioactive waste materials within the back-end of the nuclear fuel cycle. Itis organized in four areas: (1) research supporting the scientific basis of the safety case of a deep geological repository for high level nuclear waste, (2) fundamental structure research of radionuclide containing (waste) materials (3) R and D for waste management concepts for special nuclear wastes and (4) international safeguards. A number of excellent scientific results have been published in more than 80 papers in international peer-reviewed scientific journals in 2013 - 2014. Here, I would like to mention four selected scientific highlights - more can be found in this report: (1) The retention of radionuclides within a nuclear waste repository system by

  19. Institute of Energy and Climate Research IEK-6. Nuclear waste management report 2013/2014. Material science for nuclear waste management

    International Nuclear Information System (INIS)

    Neumeier, S.; Klinkenberg, M.; Bosbach, D.

    2016-01-01

    This is the third bi-annual report of the Nuclear Waste Management section of the Institute of Energy and Climate Research (IEK-6) at Forschungszentrum Juelich since 2009 - almost a tradition. Our institute has seen two more years with exciting scientific work, but also major changes regarding nuclear energy in Germany and beyond. After the reactor accident in Fukushima (Japan) in 2011, it was decided in Germany to phase out electricity production by nuclear energy by 2022. It seems clear, that the decommissioning of the nuclear power plants will take several decades. The German nuclear waste repository Konrad for radioactive waste with negligible heat generation (all low level and some of the intermediate level radioactive waste) will start operation in the next decade. The new site selection act from 2013 re-defines the selection procedure for the German high level nuclear waste repository. Independently of the decision to stop electricity production by nuclear energy, Germany has to manage and ultimately dispose of its nuclear waste in a safe way. Our basic and applied research for the safe management of nuclear waste is focused on radiochemistry and materials chemistry aspects - it is focused on the behaviour of radionuclides and radioactive waste materials within the back-end of the nuclear fuel cycle. Itis organized in four areas: (1) research supporting the scientific basis of the safety case of a deep geological repository for high level nuclear waste, (2) fundamental structure research of radionuclide containing (waste) materials (3) R and D for waste management concepts for special nuclear wastes and (4) international safeguards. A number of excellent scientific results have been published in more than 80 papers in international peer-reviewed scientific journals in 2013 - 2014. Here, I would like to mention four selected scientific highlights - more can be found in this report: (1) The retention of radionuclides within a nuclear waste repository system by

  20. Concepts and strategies for management of nuclear wastes

    International Nuclear Information System (INIS)

    1979-11-01

    Three modes of reactor strategies are chosen and discussed; (1) Once-through type light water reactor, (2) U-Pu cycle light water reactor, and (3) U-Pu cycle fast breeder reactor. The arising of wastes in each mode of nuclear fuel cycle is first estimated for unit nuclear power generation of 1 GWe.year and the amount of wastes to be managed in each year is then calculated. Assuming the 2nd and the 3rd reprocessing plants are not operative, the decrease of waste arising is also estimated, which, nevertheless, claims the need for spent fuel storage pools. In addition, the arisings of decommissioning wastes are evaluated to identify their effect on waste management. Based on above fact, a generic logic of waste management is brought about, placing major emphasis on volume reduction, barrier- and decay-effects. According to the characteristics, the wastes arisen at each stage of nuclear fuel cycle can be categorized into (1) extremely low-level waste, (2) low- and intermediate-level waste, (3) alpha-waste and (4) high-level waste, and the suitable isolation periods for the specified categories can be set by the aid of hazard index, suggesting that the disposal options may possibly be selected. The waste disposal gives environmental impacts through dispersion and migration of contained nuclides into biosphere; the dispersion and migration paths are investigated and a mathematical expression to evaluate the impacts as dose commitment is presented. A multi-barrier concept is proposed since combined artificial and natural barriers have possibility of lengthening the migration path to enable safe disposal. Finally, items of research/development in waste management are represented from the viewpoints of (1) establishment of management system, (2) safety assessment covering verification of technology and system, and (3) regulation, giving recommendations for national policy making as well as for international co-operation. (JPN)

  1. Progress in waste management technology

    International Nuclear Information System (INIS)

    Hart, R.G.

    1978-08-01

    In a previous paper by the same author, emphasis was placed on the role that 'pathways analysis' would play in providing 'beyond reasonable doubt' that a particular method and a particular formation would be suitable for the safe geologic disposal of nuclear wastes. Since that paper was released, pertinent pathways analyses have been published by Bernard Cohen, de Marsily et al., the American Physical Society's Special Study Group on Nuclear Fuel Cycles and Waste Management, and KBS of Sweden. The present paper reviews and analyses the strengths and weaknesses of each of these papers and their implications for the Canadian plan for the geologic disposal of nuclear waste. The conclusion is that the Canadian plan is on the right track and that the disposal of nuclear wastes is not an intractable problem. Indeed the analyses show that several options, each with large safety factors, are likely eventually to be identified. (author)

  2. Legal and governmental infrastructure for nuclear, radiation, radioactive waste and transport safety. Safety requirements

    International Nuclear Information System (INIS)

    2000-01-01

    This publication establishes requirements for legal and governmental responsibilities in respect of the safety of nuclear facilities, the safe use of sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material. Thus, it covers development of the legal framework for establishing a regulatory body and other actions to achieve effective regulatory control of facilities and activities. Other responsibilities are also covered, such as those for developing the necessary support for safety, involvement in securing third party liability and emergency preparedness

  3. Legal and governmental infrastructure for nuclear, radiation, radioactive waste and transport safety. Safety requirements

    International Nuclear Information System (INIS)

    2004-01-01

    This publication establishes requirements for legal and governmental responsibilities in respect of the safety of nuclear facilities, the safe use of sources of ionizing radiation, radiation protection, the safe management of radioactive waste and the safe transport of radioactive material. Thus, it covers development of the legal framework for establishing a regulatory body and other actions to achieve effective regulatory control of facilities and activities. Other responsibilities are also covered, such as those for developing the necessary support for safety, involvement in securing third party liability and emergency preparedness

  4. 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

  5. A study on the methodology of integrated safety assessment on low and intermediate level waste (LILW) managed in temporary storage facility at NPP

    International Nuclear Information System (INIS)

    Ahn, Min Ho

    2010-02-01

    Since 1978, the KHNP has been operating 20 NPPs (16 PWRs and 4 CANDUs) and generating about 67,000 drums (200 L) of LILW (as of December 31, 2005), which have been stored in the temporary storage facility (TSF) at each NPP due to the absence of a repository for the disposal of LILW. Therefore, the period of temporary storage of LILW is so long compared to other countries. Furthermore, the details with respect to the safety analyse on the TSF have not been considered in PSAR and FSAR. Especially, the risk assessment on the TSF has scarcely been conducted as opposed to many researches on the disposal of LILW. Since 2003, however, the IAEA has been recognized on the importance of predispoal management of LILW. And then, the regulatory frame of U.S. NRC was being shifted to risk-based regulation from the deterministic approach. Therefore, most of radioactive wastes including the LILW will be managed in terms of the risk-based graded approach to future regulation system called RIR (risk informed regulation). If the radioactive wastes do not quantitatively deal with the risk-based regulation, the radiological risk on some of radioactive wastes might be overestimated or underestimated regardless of the degree of the risk. According to a consequence of these situations, the numbers of the researches on the predisposal management of LILW have been required for the preparation on new regulatory frame. In this study, the main objective of this study is to establish the methodology of integrated safety assessment on LILW managed in the TSF at NPP, and to develop the integrated safety assessment code for routine operating condition and for for accident analysis on LILW managed in the TSF. In order to establish the methodology of integrated safety assessment on LILW managed in the TSF at NPP, three main parameters were considered: risk-based accident scenarios, radionuclide inventory, and atmospheric dispersion factor (χ/Q). Arbitrary accidents related to LILW management in the

  6. Canadian high-level radioactive waste management system issues

    International Nuclear Information System (INIS)

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

    1992-01-01

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

  7. Issues and trends in radioactive waste management in the perspectives of Bangladesh

    International Nuclear Information System (INIS)

    Alam, M.N.

    2002-01-01

    Radioactive wastes arising in Bangladesh comes from the use of radionuclides in medicine, industry, research and agriculture. Regulatory arrangement to manage radioactive wastes in Bangladesh has been established through promulgation of nuclear safety and radiation control rules-1997, SRO No. 205-Law/1997. A national waste management strategy for waste classification, regulatory control would have been developed and implemented taking due account of the nature and magnitude of the waste in the country. An adequate training programme for the persons responsible for waste management and the staff of the regulatory body has been in place. Waste management facility and building construction for storage for decay and then clearance for disposal is in progress at the Atomic Energy Research Establishment, Bangladesh Atomic Energy Commission, Savar, Dhaka, Bangladesh, under the auspices and help of the International Atomic Energy Agency expertise. (author)

  8. Waste management in reprocessing plants

    International Nuclear Information System (INIS)

    Mortreuil, M.

    1982-01-01

    This lecture will give a survey of the French policy for the management of wastes in reprocessing plants. In consideration of their radioactivity, they must be immobilized in matrix in such a manner that they are stored under optimal safety conditions. A general review on the nature, nucleide content and quantity of the various wastes arising from thermal nuclear fuel reprocessing is given in the light of the French plants UP1 at Marcoule and UP2 at La Hague. The procedures of treatment of such wastes and their conditioning into inert packages suitable for temporary or terminal storage are presented, especially concerning the continuous vitrification process carried out for fission product solutions. The requirements of each option are discussed and possible alternative solutions are exposed. (orig./RW)

  9. The national plan of radioactive materials and wastes management. 2010-2012 edition

    International Nuclear Information System (INIS)

    2010-01-01

    This short presentation, given by the nuclear safety authority (ASN) at the meeting of January 26, 2010 of the high committee for the nuclear safety transparency and information (HCTISN), describes the different stages of the elaboration of the new edition of the French national plan of radioactive materials and wastes management (PNGMDR). The plan comprises 3 parts: the principles and objectives of the radioactive materials and wastes management, the status of existing procedures and of procedures still under development by the end of 2009, the improvements made. The topics concern: the interim storage, the long-term management and the global consistency of the plan. (J.S.)

  10. Office of Civilian Radioactive Waste Management: Annual report to Congress

    International Nuclear Information System (INIS)

    1987-04-01

    This document summarizes the activities of the Office of Civilian Radioactive Waste Management for FY 1986. Topics include public interaction between the states and affected Indian Tribes, planning for a waste management system, site selection and site characterization of potential geologic repositories, participation in international repository projects, proposal development for a monitored retrievable storage system, demonstrations of spent fuel storage, and development of quality assurance and safety plans. 59 refs., 10 figs., 6 tabs

  11. Design and implementation of a national center for storage and management of radioactive waste

    International Nuclear Information System (INIS)

    RAKOTOMALALA, H.C.

    2009-01-01

    Despite the benefits of the radioactive sources use, waste generated by radioactive sources, may have harmful effects on human health and the environment. According to principle number 9 of the radioactive waste management, 'the safety of facilities for radioactive waste management should be provided as appropriate throughout their lifetime' radioactive waste must be managed safely, because they are potentially dangerous. By remedy this problem, it well necessary for each waste radioactive producer to establish, an infrastructure for waste radioactive management and storage. For this, the knowledge of climatic, meteorological, geological, seismic and hydrological conditions is a prerequisite for achieving the realization of the storage site. The room storage greatness, offices and other rooms depends on the nature of radiation and characteristics of materials used for construction of walls, as part the construction safety.The strictly tell management must be strictly observed during all operations. The acquisition of equipments for measurement, detection, decontamination and accessories for operations management should not be neglected. After performing the inventory and characterizing all the spent sealed radioactive sources existing in Madagascar (about 130 sealed sources), for to achieve such construction, we would need a capital budget that varies between 250 000 and 300 000 USD (including apparatus detection and accessories for the management of the construction). [fr

  12. DOE management of high-level waste at the Hanford Site

    International Nuclear Information System (INIS)

    1993-01-01

    Approximately 60 million gallons of high-level radioactive waste--caustic liquids, slurries, saltcakes, and sludges--are stored in underground tanks at the Department of Energy's Hanford Site. At least one-third of the tanks are known to have leaked waste into the enviroranent, and there are many unresolved tank safety issues. In order to resolve the environmental and safety concerns, the Department plans to retrieve the waste, immobilize it, and dispose of it in a permanent geologic repository. Processing all of the tank waste in this manner could cost $40 billion, including $1.2 billion to construct the Hanford Waste Vitrification Plant. The purpose of our audit was to examine the reasons for cost estimate increases and schedule delays on the Hanford vitrification program. We also wanted to report on outstanding technical, safety, and environmental issues that could make the project even more costly and further delay its completion. We found that the Department managed the Hanford remediation system as a number of separate projects not fully integrated into one major system acquisition. Total costs have, therefore, been obscured, and the Department has not yet clearly defined system requirements or developed overall cost and schedule baselines. This lack of visibility could result in additional cost growth and schedule delays. We also noted a vast array of technical uncertainties, including tank safety and inadequate information about the makeup of tank waste, that could significantly affect the program's cost and ultimate success. To increase visibility of program cost and schedule, we are recommending that all separate projects relating to tank waste be included in a single major system acquisition, and that the Department complete its ongoing baselining effort to the extent practical before making major funding commitments. Management concurred with our finding and recommendations

  13. Safe management of waste from health-care activities

    International Nuclear Information System (INIS)

    Pruess, A.; Giroult, E.; Rushbrook, P.

    1999-01-01

    The waste produced in the course of health-care activities, from contaminated needles to radioactive isotopes, carries a greater potential for causing infection and injury than any other type of waste, and inadequate or inappropriate management is likely to have serious public health consequences and deleterious effects on the environment. This handbook - the result of extensive international consultation and collaboration - provides comprehensive guidance on safe, efficient, and environmentally sound methods for the handling and disposal of health-care wastes. The various categories of waste are clearly defined and the particular hazards that each poses are described. Considerable prominence is given to the careful planning that is essential for the success of waste management; workable means of minimizing waste production are outlined and the role of reuse and recycling of waste is discussed. Most of the text, however, is devoted to the collection, segregation, storage, transport, and disposal of wastes. Details of containers for each category of waste, labelling of waste packages, and storage conditions are provided, and the various technologies for treatment of waste and disposal of final residues are discussed at length. Advice is given on occupational safety for all personnel involved with waste handling, and a separate chapter is devoted to the closely related topic of hospital hygiene and infection control. The handbook pays particular attention to basic processes and technologies that are not only safe but also affordable, sustainable, and culturally appropriate. For health-care settings in which resources are severely limited there is a separate chapter on minimal programmes; this summarizes all the simplest and least costly techniques that can be employed for the safe management of health-care wastes. The guide is aimed at public health managers and policy-makers, hospital managers, environmental health professionals, and all administrators with an

  14. Management of radioactive waste in Belgium: ONDRAF/NIRAS and Belgoprocess as major actors of the waste acceptance system

    International Nuclear Information System (INIS)

    Zaelen, Gunter van; Verheyen, Annick

    2007-01-01

    The management of radioactive waste in Belgium is undertaken by the national agency for radioactive waste and enriched fissile materials, ONDRAF/NIRAS, and its industrial partner Belgoprocess. ONDRAF/NIRAS has set up a management system designed to guarantee that the general public and the environment are protected against the potential hazards arising from radioactive waste. Belgoprocess is a private company, founded in 1984 and located in Dessel, Belgium. It is a subsidiary of ONDRAF/NIRAS and its activities focus on the safe processing and storage of radioactive waste. The management system of ONDRAF/NIRAS includes two aspects: a) an integrated system and b) an acceptance system. The integrated system covers all aspects of management ranging from the origin of waste to its transport, processing, interim storage and long-term management. The safety of radioactive waste management not only depends on the quality of the design and construction of the processing, temporary storage or disposal infrastructure, but also on the quality of the waste accepted by ONDRAF/NIRAS. In order to be manage d safely, both in the short and the long term, the waste transferred to ONDRAF/NIRAS must meet certain specific requirements. To that end, ONDRAF/NIRAS has developed an acceptance system. (authors)

  15. WNA's Policy Document : sustaining global best practices in uranium, mining and processing, principles for managing radiation, health and safety, waste and the environment

    International Nuclear Information System (INIS)

    Saint-Pierre, S.; Waste Management and Decommissioning Working Group-WM and DW

    2008-01-01

    The worldwide community of uranium mining and processing recognizes that managing radiation, health and safety, waste and the environment is paramount. Such responsible management applies at all stages of planning and activities. Today we are acting to ensure that all parties directly involved in uranium mining and processing strive to achieve the highest levels of excellence in these fields. We are doing so by sustaining a strong safety culture based on a commitment to common, internationally shared principles. This paper sets out principles for the management of radiation, health and safety, waste and the environment applicable to sites throughout the world. In national and regional settings where nuclear fuel cycle activities are well developed, these principles already serve as the underpinning for 'Codes of Practice' that govern uranium mining and processing. In any given setting, a Code of Practice is needed to guide practical implementation of these principles according to the regional, national or site-specific context. These principles are published in the belief that they hold special relevance for emerging uranium producing countries that do not yet have fully developed regulations for the control of radiation, health and safety, waste and the environment associated with uranium mining and processing. The principles are equally relevant for operators, contractors, and regulators newly engaged in uranium mining and processing. Once national regulations are fully developed, they can be expected to embody these principles. Each principle affirmed here will not apply to the same extent for each party. Ultimately, the precise allocation of responsibilities must be set at the national and local levels. This document holds the status of a policy and ethical declaration by the full WNA membership, which the global nuclear industry. The principles affirmed here are supported by key relevant international organizations, including the IAEA and the global mining

  16. Improvement of the material and transport component of the system of construction waste management

    Science.gov (United States)

    Kostyshak, Mikhail; Lunyakov, Mikhail

    2017-10-01

    Relevance of the topic of selected research is conditioned with the growth of construction operations and growth rates of construction and demolition wastes. This article considers modern approaches to the management of turnover of construction waste, sequence of reconstruction or demolition processes of the building, information flow of the complete cycle of turnover of construction and demolition waste, methods for improvement of the material and transport component of the construction waste management system. Performed analysis showed that mechanism of management of construction waste allows to increase efficiency and environmental safety of this branch and regions.

  17. Application of the risk-based strategy to the Hanford tank waste organic-nitrate safety issue

    International Nuclear Information System (INIS)

    Hunter, V.L.; Colson, S.D.; Ferryman, T.; Gephart, R.E.; Heasler, P.; Scheele, R.D.

    1997-12-01

    This report describes the results from application of the Risk-Based Decision Management Approach for Justifying Characterization of Hanford Tank Waste to the organic-nitrate safety issue in Hanford single-shell tanks (SSTs). Existing chemical and physical models were used, taking advantage of the most current (mid-1997) sampling and analysis data. The purpose of this study is to make specific recommendations for planning characterization to help ensure the safety of each SST as it relates to the organic-nitrate safety issue. An additional objective is to demonstrate the viability of the Risk-Based Strategy for addressing Hanford tank waste safety issues

  18. Application of the risk-based strategy to the Hanford tank waste organic-nitrate safety issue

    Energy Technology Data Exchange (ETDEWEB)

    Hunter, V.L.; Colson, S.D.; Ferryman, T.; Gephart, R.E.; Heasler, P.; Scheele, R.D.

    1997-12-01

    This report describes the results from application of the Risk-Based Decision Management Approach for Justifying Characterization of Hanford Tank Waste to the organic-nitrate safety issue in Hanford single-shell tanks (SSTs). Existing chemical and physical models were used, taking advantage of the most current (mid-1997) sampling and analysis data. The purpose of this study is to make specific recommendations for planning characterization to help ensure the safety of each SST as it relates to the organic-nitrate safety issue. An additional objective is to demonstrate the viability of the Risk-Based Strategy for addressing Hanford tank waste safety issues.

  19. Office of River Protection Integrated Safety Management System Description

    Energy Technology Data Exchange (ETDEWEB)

    CLARK, D.L.

    1999-08-09

    Revision O was never issued. Finding safe and environmentally sound methods of storage and disposal of 54 million gallons of highly radioactive waste contained in 177 underground tanks is the largest challenge of Hanford cleanup. TWRS was established in 1991 and continues to integrate all aspects of the treatment and management of the high-level radioactive waste tanks. In fiscal Year 1997, program objectives were advanced in a number of areas. RL TWRS refocused the program toward retrieving, treating, and immobilizing the tank wastes, while maintaining safety as first priority. Moving from a mode of storing the wastes to getting the waste out of the tanks will provide the greatest cleanup return on the investment and eliminate costly mortgage continuance. There were a number of safety-related achievements in FY1997. The first high priority safety issue was resolved with the removal of 16 tanks from the ''Wyden Watch List''. The list, brought forward by Senator Ron Wyden of Oregon, identified various Hanford safety issues needing attention. One of these issues was ferrocyanide, a chemical present in 24 tanks. Although ferrocyanide can ignite at high temperature, analysis found that the chemical has decomposed into harmless compounds and is no longer a concern.

  20. Disposal of Radioactive Waste. Specific Safety Requirements

    International Nuclear Information System (INIS)

    2011-01-01

    This publication establishes requirements applicable to all types of radioactive waste disposal facility. It is linked to the fundamental safety principles for each disposal option and establishes a set of strategic requirements that must be in place before facilities are developed. Consideration is also given to the safety of existing facilities developed prior to the establishment of present day standards. The requirements will be complemented by Safety Guides that will provide guidance on good practice for meeting the requirements for different types of waste disposal facility. Contents: 1. Introduction; 2. Protection of people and the environment; 3. Safety requirements for planning for the disposal of radioactive waste; 4. Requirements for the development, operation and closure of a disposal facility; 5. Assurance of safety; 6. Existing disposal facilities; Appendices.

  1. Nuclear-waste-management. Quarterly progress report, July-September 1981

    Energy Technology Data Exchange (ETDEWEB)

    Chikalla, T.D.; Powell, J.A. (comps.)

    1981-12-01

    Progress reports and summaries are presented for the following: high-level waste process development, alternate waste forms; TMI zeolite vitrification demonstration program; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton implantation; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclides in soils; handbook of methods to decrease the generation of low-level waste; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; analysis of spent fuel policy implementation; spent fuel and fuel pool component integrity program; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium mill tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing uranium tailings; application of long-term chemical biobarriers for uranium tailings; and revegetation of inactive uranium tailings sites.

  2. CONRRAD Project: how CNEA is managing radioactive waste knowledge

    International Nuclear Information System (INIS)

    Vetere, Claudia L.; Gomiz, Pablo R.

    2009-01-01

    The aim of this paper is to introduce CONRRAD Project, which is an initiative of the Knowledge Management Group (GesCon) belonged to the Nuclear Safety and Environment Area, for knowledge preservation of Radioactive Waste Management. It discusses the methodology and the results that have been achieved at present. (author)

  3. Waste management

    International Nuclear Information System (INIS)

    Soule, H.F.

    1975-01-01

    Current planning for the management of radioactive wastes, with some emphasis on plutonium contaminated wastes, includes the provision of re-positories from which the waste can be safely removed to permanent disposal. A number of possibilities for permanent disposal are under investigation with the most favorable, at the present time, apparently disposal in a stable geological formation. However, final choice cannot be made until all studies are completed and a pilot phase demonstrates the adequacy of the chosen method. The radioactive wastes which result from all portions of the fuel cycle could comprise an important source of exposure to the public if permitted to do so. The objectives of the AEC waste management program are to provide methods of treating, handling and storing these wastes so that this exposure will not occur. This paper is intended to describe some of the problems and current progress of waste management programs, with emphasis on plutonium-contaminated wastes. Since the technology in this field is advancing at a rapid pace, the descriptions given can be regarded only as a snapshot at one point in time. (author)

  4. Inquiry relating to safety due to modification of usage of nuclear fuel material (establishment of waste safety testing facility) in Tokai Laboratory, Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    1979-01-01

    Application was made to the director of the Science and Technology Agency (STA) for the license relating to the modification of usage of nuclear fuel material (the establishment of waste safety testing facility) from the director of the Japan Atomic Energy Research Institute on November 30, 1978. After passing through the safety evaluation in the Nuclear Safety Bureau of STA, inquiry was conducted to the head of the Atomic Energy Safety Commission (AESC) on June 6, 1979, from the director of the STA. The head of AESC directed to conduct the safety examination to the head of the Nuclear Fuel Safety Examination Specialist Committee on June 7, 1979. The content of the modification of usage of nuclear fuel material is the establishment of waste safety testing facility to study and test the safety relating to the treatment and disposal of high level radioactive liquid wastes due to the reprocessing of spent fuel. As for the results of the safety examination, the siting of the waste safety testing facility which is located in the Tokai Laboratory, Japan Atomic Energy Research Institute (JAERI), and the test plan of the glass solidification of high level radioactive liquid are presented as the outline of the study plan. The building, main equipments including six cells, the isolation room and the glove box, the storage, and the disposal facilities for gas, liquid and solid wastes are explained as the outline of the facilities. Concerning the items from the viewpoint of safety, aseismatic design, slightly vacuum operation, shielding, decay heat removal, fire protection, explosion protection, criticality management, radiation management and environmental effect were evaluated, and the safety was confirmed. (Nakai, Y.)

  5. Publicly administrated nuclear waste management research programme 1994-1996. General plan for the research programme and research plan for 1994

    International Nuclear Information System (INIS)

    1994-01-01

    The nuclear energy legislation of Finland includes detailed stipulations concerning nuclear waste management. Each producer of nuclear waste is responsible for the safe handling, management and disposal of the waste, and for the financing of these operations. The authorities supervise and control the implementation of the national waste management programme and set the necessary safety and other requirements. The principal goal of the JYT programme is to provide the authorities with information and research results relevant for the safety of nuclear waste management in order to support the various activities of the authorities. The whole field of the research programme is subdivided into the following main topic areas: (1) bedrock structure and stability, rock investigation methods, and characteristics and flow of groundwater, (2) release of radionuclides from a repository and subsequent migration in the bedrock, (3) performance and safety assessment of repositories and other phases of nuclear waste management (4) natural analogue studies, (5) waste management technology and costs and (6) sociopolitical and other societal issues and environmental impact assessment

  6. Safety guidebook relative to the disposal of radioactive wastes in deep geologic formation

    International Nuclear Information System (INIS)

    2008-01-01

    The French nuclear safety authority (ASN) initiated in 2003 a revision process of the objectives to be considered during the research and work steps of the implementation of a radioactive waste storage facility in deep geologic formations. The purpose of this document is to define the safety objectives that have to be retained at each step of this implementation, from the site characterization to the closure of the facility. This update takes into account the works carried out by the ANDRA (French national agency of radioactive wastes) in the framework of the law from December 30, 1991, and the advices of the permanent experts group about these works. It takes also into consideration the international research works in this domain and the choices defined in the program law no 2006-739 from June 28, 2006 relative to the sustainable management of radioactive materials and wastes. The main modifications concern: the notion of reversibility, the definition of the safety functions of disposal components, the safety goals and the design principles assigned to waste packages, the control of nuclear materials and the monitoring objectives of the facility. The documents treats of the following points: 1 - the objectives of public health and environment protection; 2 - the safety principles and the safety-related design bases of the facility; and 3 - the method used for demonstrating the disposal safety. (J.S.)

  7. Activation/waste management

    International Nuclear Information System (INIS)

    Maninger, C.

    1984-10-01

    The selection of materials and the design of the blankets for fusion reactors have significant effects upon the radioactivity generated by neutron activation in the materials. This section considers some aspects of materials selection with respect to waste management. The activation of the materials is key to remote handling requirements for waste, to processing and disposal methods for waste, and to accident severity in waste management operations. In order to realize the desirable evnironmental potentials of fusion power systems, there are at least three major goals for waste management. These are: (a) near-surface burial; (b) disposal on-site of the fusion reactor; (c) acceptable radiation doses at least cost during and after waste management operations

  8. Managing Uncertainties Associated With Radioactive Waste Disposal: Task Group 4 Of The IAEA PRISM Project

    International Nuclear Information System (INIS)

    Seitz, R.

    2011-01-01

    It is widely recognized that the results of safety assessment calculations provide an important contribution to the safety arguments for a disposal facility, but cannot in themselves adequately demonstrate the safety of the disposal system. The safety assessment and a broader range of arguments and activities need to be considered holistically to justify radioactive waste disposal at any particular site. Many programs are therefore moving towards the production of what has become known as a Safety Case, which includes all of the different activities that are conducted to demonstrate the safety of a disposal concept. Recognizing the growing interest in the concept of a Safety Case, the International Atomic Energy Agency (IAEA) is undertaking an intercomparison and harmonization project called PRISM (Practical Illustration and use of the Safety Case Concept in the Management of Near-surface Disposal). The PRISM project is organized into four Task Groups that address key aspects of the Safety Case concept: Task Group 1 - Understanding the Safety Case; Task Group 2 - Disposal facility design; Task Group 3 - Managing waste acceptance; and Task Group 4 - Managing uncertainty. This paper addresses the work of Task Group 4, which is investigating approaches for managing the uncertainties associated with near-surface disposal of radioactive waste and their consideration in the context of the Safety Case. Emphasis is placed on identifying a wide variety of approaches that can and have been used to manage different types of uncertainties, especially non-quantitative approaches that have not received as much attention in previous IAEA projects. This paper includes discussions of the current results of work on the task on managing uncertainty, including: the different circumstances being considered, the sources/types of uncertainties being addressed and some initial proposals for approaches that can be used to manage different types of uncertainties.

  9. Reportable Nuclide Criteria for ORNL Radioactive Waste Management Activities - 13005

    International Nuclear Information System (INIS)

    McDowell, Kip; Forrester, Tim; Saunders, Mark

    2013-01-01

    The U.S. Department of Energy's Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee generates numerous radioactive waste streams. Many of those streams contain a large number of radionuclides with an extremely broad range of concentrations. To feasibly manage the radionuclide information, ORNL developed reportable nuclide criteria to distinguish between those nuclides in a waste stream that require waste tracking versus those nuclides of such minimal activity that do not require tracking. The criteria include tracking thresholds drawn from ORNL onsite management requirements, transportation requirements, and relevant treatment and disposal facility acceptance criteria. As a management practice, ORNL maintains waste tracking on a nuclide in a specific waste stream if it exceeds any of the reportable nuclide criteria. Nuclides in a specific waste stream that screen out as non-reportable under all these criteria may be dropped from ORNL waste tracking. The benefit of these criteria is to ensure that nuclides in a waste stream with activities which meaningfully affect safety and compliance are tracked, while documenting the basis for removing certain isotopes from further consideration. (authors)

  10. FOOD QUALITY AND SAFETY ASSURANCE IN TERMS OF LOSS AND WASTE LIMITATION

    Directory of Open Access Journals (Sweden)

    Maria Śmiechowska

    2016-06-01

    Full Text Available One of the greatest challenges of 21st century is satisfying the food needs of the fast growing population of the world. Food must fulfill quality and safety standards.  The access to safe and appropriate food is not the same everywhere.  Food excess and, in consequence, food waste is present in many regions of the world. This study is meant to explain the causes of food waste on the basis of the author’s own research and study results of other scientists. The lack of authenticity and falsification belong to the new factors endangering food safety and food waste related thereto. This analysis proves that the authenticity of food improves its safety through the implementation of quality management systems, the appropriate system of food labelling and food identification by means of applicable law regulations, supervision and control systems. Main aim of this study is to address why, even though there are so many quality standards and systems, a significant problem with food loss and waste constantly occurs. Waste-causing factors have been determined on the example of bread and the handling of unconsumed bread has been attempted in this study. Waste limiting actions are necessary as food production is significantly overburdening the natural environment and generating increasing amount of waste, hazardous to the clean air. 

  11. 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

  12. Development and problems of radioactive waste management infrastructure in Estonia

    International Nuclear Information System (INIS)

    Putnik, H.; Realo, E.

    2001-01-01

    Estonia is one of a few countries where the establishment of radiation protection and radioactive waste management infrastructure started only recently, soon after regaining independence in the beginning of 1990's. Both legislative and regulatory infrastructure had to be built from scratch, in parallel with the beginning of urgent activities and practices to manage waste streams inherited from the past. Despite significant deficiency of local expertise and specialists in the field, the main objectives of the establishment were set up: to enforce national legislation basing on contemporary international principles, criteria, requirements and to implement structures and procedures for an efficient regulation of radiation safety issues, including practices involving radioactive waste management and decommissioning

  13. Radioactive waste disposal programme 2008 of the waste-management-compelled bodies. Technical report 08-01

    International Nuclear Information System (INIS)

    2008-10-01

    Important steps in the management of radioactive waste have already been implemented in Switzerland and there is now wide experience in carrying out the associated activities. In terms of preparing for deep geological disposal, the necessary scientific and technical work is well advanced and the feasibility of implementing geological repositories that provide the required long-term safety has been successfully demonstrated for all wastes arising in Switzerland. Test feasibility demonstrations have also been approved by the Federal Council. Sufficient knowledge is available to allow the next steps in the selection of repository sites to be performed. The legal framework and organisational measures are also in place. The conceptual part of the Sectoral Plan for deep geological repositories regulates the details of the site selection process to be conducted over the next years. The origin, types and volumes of radioactive waste to be disposed of in Switzerland are known. The reference case assumes operation of the existing nuclear power plants for a period of 50 years and a collection period up to around 2050 for radioactive waste from medicine, industry and research. The types and volumes of radioactive waste that would arise in the case of extension of the operating lifetime of the existing power plants and the collection period for waste from medicine, industry and research by 10 years are included for planning purposes. Also considered are the wastes to be expected in the case of an additional production of 5 GW e for a period of 60 years. The resulting wastes are conditioned, characterised and inventoried on an ongoing basis. Before conditioning of a waste stream begins, the proposed conditioning procedure is evaluated by Nagra in terms of the suitability for disposal of the resulting waste packages. A model inventory of waste that will arise in the future has also been compiled. This provides a reliable basis for planning and implementing geological repositories

  14. Management of radioactive wastes at nuclear power plants

    International Nuclear Information System (INIS)

    2008-03-01

    This Regulation refers to the requirements of the Regulation CNEN-NE.1.26, 'Safety Operation of Nuclear Power Plants', as expressed in the section 13, specifically in the subsection 13.4, relatives to the management of radioactive wastes at nuclear power plants

  15. Radioactive Waste Management Objectives

    International Nuclear Information System (INIS)

    2011-01-01

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

  16. Radioactive Waste Management in the European Union: Initiatives for New Legislation

    International Nuclear Information System (INIS)

    Taylor, D.

    2003-01-01

    Improving the management of radioactive waste in the European Union is a major theme of the ''nuclear package'' recently adopted by the European Commission. Included in the package are proposals for new legislation that would bring about the development of common safety standards in Europe covering the full nuclear sector, segregated funds to cover all nuclear liabilities that remain after the operating lifetime of an installation and clearly defined waste programs for radioactive waste management in each of the Member States of the Union. Included in these programs must be firm dates for a number decision points leading to disposal of all forms of radioactive waste. The package also puts significant emphasis on more, and better coordinated, research on radioactive waste management as the present levels are thought to be inadequate

  17. Radioactive waste management in the European Union: initiatives for new legislation

    International Nuclear Information System (INIS)

    Taylor, Derek M.

    2003-01-01

    Improving the management of radioactive waste in the European Union is a major theme of the 'nuclear package' recently adopted by the European Commission. Included in the package are proposals for new legislation that would bring about the development of common safety standards in Europe covering the full nuclear sector, segregated funds to cover all nuclear liabilities that remain after the operating lifetime of an installation and clearly defined waste programmes for radioactive waste management in each of the Member States of the Union. Included in these programmes must be firm dates for a number decision points leading to disposal of all forms of radioactive waste. The package also puts significant emphasis on more, and better coordinated, research on radioactive waste management as the present levels are thought to be inadequate. (author)

  18. Safety and radiation protection in waste management. Final report

    International Nuclear Information System (INIS)

    Broden, K.; Carugati, S.; Brodersen, K.; Lipponen, M.; Vuori, S.; Ruokola, E.; Palsson, S.E.; Sekse, T.; Ramsoey, T.

    2001-12-01

    During 1998-2001, a project on the management of radioactive waste was carried out as part of the NKS programme. The project was called NKS/SOS-3 and was divided into three sub-projects: SOS-3.1 (Environmental Impact Assessment; EIA), SOS-3.2 (Intermediate storage) and SOS-3.3 (Contamination levels in metals). SOS-3.1 included four EIA seminars on the use of EIA in the Nordic countries. The seminars were held in Norway in 1998, Denmark in 1999, Iceland in 2000 and Finland in 2001. (The last seminar was performed in co-operation with the NKS project SOS-1.) The seminars focused on experiences from EIA procedures for the disposal of radioactive waste, and other experiences from EIA processes. SOS-3.2 included a study on intermediate storage of radioactive waste packages in the Nordic countries. An overview of experiences was compiled and recommendations were made regarding different intermediate storage options as well as control and supervision. SOS-3.3 included investigation of contamination levels in steel, aluminium and magnesium samples from smelting facilities and an overview of current practice for clearance in the Nordic countries. Clearance, clearance levels, naturally occurring radioactive materials, radioactive waste, radioactive material, intermediate storage, waste disposal, environmental impact assessment, gamma spectrometric measurements, beta measurements, neutron activation analyses. (au)

  19. Long term management of wastes contaminated by plutonium

    International Nuclear Information System (INIS)

    Marque, Y.

    1983-01-01

    For the different categories of wastes, the evolution of the cumulated production until the year 2000 is described by curves and the general situation of production points is presented, all that in France. The storage conditions are specified according to the type of wastes, category A, B, or C; the threshold under which the waste is classified in A category being fixed by the safety authorities at 2.10 4 CMA (maximum permissible concentration), that is to say for plutonium 1Ci/m 3 . The knowledge of waste activity is another basic element of the management of such wastes, the fixing of the threshold, above which wastes contaminated by plutonium have to be stored underground, still keeping to be specified [fr

  20. Handbook of hazardous waste management

    International Nuclear Information System (INIS)

    Metry, A.A.

    1980-01-01

    The contents of this work are arranged so as to give the reader a detailed understanding of the elements of hazardous waste management. Generalized management concepts are covered in Chapters 1 through 5 which are entitled: Introduction, Regulations Affecting Hazardous Waste Management, Comprehensive Hazardous Waste Management, Control of Hazardous Waste Transportation, and Emergency Hazardous Waste Management. Chapters 6 through 11 deal with treatment concepts and are entitled: General Considerations for Hazardous Waste Management Facilities, Physical Treatment of Hazardous Wastes, Chemical Treatment of Hazardous Wastes, Biological Treatment of Hazardous Wastes, Incineration of Hazardous Wastes, and Hazardous Waste Management of Selected Industries. Chapters 12 through 15 are devoted to ultimate disposal concepts and are entitled: Land Disposal Facilities, Ocean Dumping of Hazardous Wastes, Disposal of Extremely Hazardous Wastes, and Generalized Criteria for Hazardous Waste Management Facilities

  1. Mine waste management

    International Nuclear Information System (INIS)

    Hutchinson, I.P.G.; Ellison, R.D.

    1992-01-01

    This book reports on mine waste management. Topics covered include: Performance review of modern mine waste management units; Mine waste management requirements; Prediction of acid generation potential; Attenuation of chemical constituents; Climatic considerations; Liner system design; Closure requirements; Heap leaching; Ground water monitoring; and Economic impact evaluation

  2. TWRS safety and technical integration risk management plan

    International Nuclear Information System (INIS)

    Fordham, R.A.

    1996-01-01

    The objectives of the Tank Waste Remediation System (TWRS) Safety and Technical Integration (STI) programmatic risk management program are to assess, analyze, and handle risks associated with TWRS STI responsibilities and to communicate information about the actions being taken and the results to enable decision making. The objective of this TWRS STI Risk Management Plan is to communicate a consistent approach to risk management that will be used by the organization

  3. Regulatory aspects of the radioactive waste management in Argentina

    International Nuclear Information System (INIS)

    Siraky, Graciela

    2000-01-01

    This paper describes briefly the legislative and regulatory framework in which the radioactive waste management is carried out in Argentina. The activities of the Nuclear Regulatory Authority (NRA) and the applied approaches in relation to inspection of facilities, safety assessments of associated systems and collaboration in the matter with international agencies are also exposed. The 'National Law of the Nuclear Activity' (No. 24804), in force since April 1997, assigns to NRA the following functions: to regulate and to inspect nuclear activities regarding radiological and nuclear safety, physical protection of nuclear materials, in order to verify that such materials are used exclusively with peaceful purposes and also, to advise the National Executive Power in matters of its competence. For the fulfilment of these functions the Law grants to NRA the necessary legal competence to develop, to establish and to apply a regulatory system to all nuclear activities carried out in Argentina. The activity of NRA is carried out in the framework of a regulatory system whose fundamental aspect in the approach adopted to establish the requirements of safety, which is know as 'of performance'. This system has a group of rules known as 'AR Standards' (AR: abbreviation of Regulatory Authority) that, among other requirements, establish that the construction, operation and decommissioning of a nuclear installation can not start without the corresponding construction, operation or decommissioning license. In that sense, besides having the legal competence in the topic, NRA has developed its necessary technical competence to evaluate, with own criteria, all radiological and nuclear safety aspects involved in the grant of licenses and to guarantee an appropriate level of control in the facilities. In relation to the radioactive waste management, NRA has developed some basic criteria. These criteria underline the requirements put to the 'Responsible Entity' that generates or manages

  4. Radioactive Waste Management in Central Asia - 12034

    Energy Technology Data Exchange (ETDEWEB)

    Zhunussova, Tamara; Sneve, Malgorzata; Liland, Astrid [Norwegian Radiation Protection Authority (Norway)

    2012-07-01

    After the collapse of the Soviet Union the newly independent states in Central Asia (CA) whose regulatory bodies were set up recently are facing problems with the proper management of radioactive waste and so called 'nuclear legacy' inherited from the past activities. During the former Soviet Union (SU) period, various aspects of nuclear energy use took place in CA republics of Kazakhstan, Kyrgyzstan, Tajikistan and Uzbekistan. Activities range from peaceful use of energy to nuclear testing for example at the former Semipalatinsk Nuclear Test Site (SNTS) in Kazakhstan, and uranium mining and milling industries in all four countries. Large amounts of radioactive waste (RW) have been accumulated in Central Asia and are waiting for its safe disposal. In 2008 the Norwegian Radiation Protection Authority (NRPA), with the support of the Norwegian Ministry of Foreign Affairs, has developed bilateral projects that aim to assist the regulatory bodies in Kazakhstan, Kyrgyzstan Tajikistan, and Uzbekistan (from 2010) to identify and draft relevant regulatory requirements to ensure the protection of the personnel, population and environment during the planning and execution of remedial actions for past practices and radioactive waste management in the CA countries. The participating regulatory authorities included: Kazakhstan Atomic Energy Agency, Kyrgyzstan State Agency on Environmental Protection and Forestry, Nuclear Safety Agency of Tajikistan, and State Inspectorate on Safety in Industry and Mining of Uzbekistan. The scope of the projects is to ensure that activities related to radioactive waste management in both planned and existing exposure situations in CA will be carried out in accordance with the international guidance and recommendations, taking into account the relevant regulatory practice from other countries in this area. In order to understand the problems in the field of radioactive waste management we have analysed the existing regulations through

  5. Policies and strategies for radioactive waste management

    International Nuclear Information System (INIS)

    2009-01-01

    A policy for spent fuel and radioactive waste management should include a set of goals or requirements to ensure the safe and efficient management of spent fuel and radioactive waste in the country. Policy is mainly established by the national government and may become codified in the national legislative system. The spent fuel and radioactive waste management strategy sets out the means for achieving the goals and requirements set out in the national policy. It is normally established by the relevant waste owner or nuclear facility operator, or by government (institutional waste). Thus, the national policy may be elaborated in several different strategy components. To ensure the safe, technically optimal and cost effective management of radioactive waste, countries are advised to formulate appropriate policies and strategies. A typical policy should include the following elements: defined safety and security objectives, arrangements for providing resources for spent fuel and radioactive waste management, identification of the main approaches for the management of the national spent fuel and radioactive waste categories, policy on export/import of radioactive waste, and provisions for public information and participation. In addition, the policy should define national roles and responsibilities for spent fuel and radioactive waste management. In order to formulate a meaningful policy, it is necessary to have sufficient information on the national situation, for example, on the existing national legal framework, institutional structures, relevant international obligations, other relevant national policies and strategies, indicative waste and spent fuel inventories, the availability of resources, the situation in other countries and the preferences of the major interested parties. The strategy reflects and elaborates the goals and requirements set out in the policy statement. For its formulation, detailed information is needed on the current situation in the country

  6. Municipal Solid Waste management

    OpenAIRE

    Mirakovski, Dejan; Hadzi-Nikolova, Marija; Doneva, Nikolinka

    2010-01-01

    Waste management covers newly generated waste or waste from an onging process. When steps to reduce or even eliminate waste are to be considered, it is imperative that considerations should include total oversight, technical and management services of the total process.From raw material to the final product this includes technical project management expertise, technical project review and pollution prevention technical support and advocacy.Waste management also includes handling of waste, in...

  7. Order of magnitude cost appraisal for selected aspects of clad waste management

    International Nuclear Information System (INIS)

    Zima, G.E.

    1977-02-01

    A simple formula, incorporating the fixed charge rate principle, is applied to a clad waste management exercise involving densification, canning, transportation and salt disposal. For the purpose of comparison with the bulk of published nuclear waste management costs, cost and fixed charge rate data appropriate to roughly the period 1970 to 1973 are used. Within the context of this order of magnitude appraisal, densification displays some cost advantage, reflected principally in the transportation cost. Dependent on the degree of densification, above a certain clad waste generation rate the transportation savings may be expected to exceed reasonable densification costs. There is no explicit consideration of the decontamination step in this appraisal. The limited accessibility of surface effect decontamination to internal transuranic and activation product contamination suggests a quite small influence of decontamination on the transportation and disposal costs. Decontamination may, however, have a significant effect on the ease of establishing a practicable containment envelope of high reliability throughout the clad waste history. A brief comparison is made of clad waste management costs with the major costs of the nuclear power economy. This comparison implies a virtually unlimited technical latitude for clad waste treatment in accommodating the public safety without significant perturbation of nuclear power costs. It is submitted that clad waste management optimization will be under the primal constraint of maximizing thelong term public safety, with economic analysis useful only as a discriminator between waste handling alternatives of sensibly equivalent containment qualities. Some areas of clad waste treatment meriting increased attention are noted

  8. 18th GRS experts' meeting 1994. Seminar B: Safety of facilities and waste management. Technical papers

    International Nuclear Information System (INIS)

    1994-01-01

    The six papers deal with the scanning, recording and assessment of long-standing soil pollution emanating from mining activities in Saxonia, Sachsen-Anhalt and Thuringia, the computation of radioactivity levels of structural core components destined for ultimate disposal, and with safety aspects and safety criteria applied to waste repositories in Germany and abroad. Nuclide transport models used for providing evidence of safe radiological containment of waste repositories are presented and discussed. (DG) [de

  9. Harmonizing nuclear safety practices in Europe: WENRA activities in the area of waste management

    International Nuclear Information System (INIS)

    Theis, St.; Dandrieux, G.; Feron, F.

    2011-01-01

    The Western European Nuclear Regulators Association (WENRA) was created in 1999. It originally consisted of the heads of the nuclear safety authorities of the member countries of the European Union (E.U.), plus Switzerland. The original objectives of the Association were: -) to develop a common approach to nuclear safety and regulation, in particular within the E.U.; -) to provide the E.U. with an independent capability to examine nuclear safety and regulation in candidate countries; -) to evaluate and achieve a common approach to nuclear safety and regulatory issues which arise. For the detailed work WENRA set up two working groups, for reactor safety (RHWG: reactor harmonization working group) and a little later for waste and decommissioning (WGWD: working group on waste and decommissioning). The basis for all WENRA work is the WENRA policy statement which as a major promoter of developments contains a self commitment of all WENRA member states to implement without undue delay harmonized requirements produced by the working groups after approval of the WENRA plenary. First WENRA publications receiving much public interest were mainly dedicated to the safety of power reactor, and more recently on new reactors and on long term operation of currently operating reactors. (authors)

  10. Research and technology programmes supporting waste management in BNFL

    International Nuclear Information System (INIS)

    Fairhall, G.A.; Horner, A.M.

    2000-01-01

    Waste Management is a major activity of BNFL in the UK and at various locations internationally. To support these activities extensive programmes of Research and Technology have been undertaken for many years. This involves practical studies involving active and non-active work at laboratory and pilot plant scale. Extensive use is also made of theoretical and modelling techniques. Current work is aimed at underpinning and improving current operations supporting the design and safety cases of new plant and addressing waste management activities of the future including decommissioning. (authors)

  11. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Rummery, T.E.; Rosinger, E.L.J.

    1983-05-01

    The Canadian Nuclear Fuel Waste Management Program is now well established. This report outlines the generic research and technological development underway in this program to assess the concept of immobilization and subsequent disposal of nuclear fuel waste deep in a stable plutonic rock in the Canadian Shield. The program participants, funding, schedule and associated external review processes are briefly outlined. The major scientific and engineering components of the program, namely, immobilization studies, geoscience research and environmental and safety assessment, are described in more detail

  12. High-level Waste Long-term management technology development

    International Nuclear Information System (INIS)

    Choi, Jong Won; Kang, C. H.; Ko, Y. K.

    2012-02-01

    The purpose of this project is to develop a long-term management system(A-KRS) which deals with spent fuels from domestic nuclear power stations, HLW from advanced fuel cycle and other wastes that are not admitted to LILW disposal site. Also, this project demonstrate the feasibility and reliability of the key technologies applied in the A-KRS by evaluating them under in-situ condition such as underground research laboratory and provide important information to establish the safety assessment and long-term management plan. To develop the technologies for the high level radioactive wastes disposal, demonstrate their reliability under in-situ condition and establish safety assessment of disposal system, The major objects of this project are the following: Ο An advanced disposal system including waste containers for HLW from advanced fuel cycle and pyroprocess has been developed. Ο Quantitative assessment tools for long-term safety and performance assessment of a radwaste disposal system has been developed. Ο Hydrological and geochemical investigation and interpretation methods has been developed to evaluate deep geological environments. Ο The THMC characteristics of the engineered barrier system and near-field has been evaluated by in-situ experiments. Ο The migration and retardation of radionuclides and colloid materials in a deep geological environment has been investigated. The results from this project will provide important information to show HLW disposal plan safe and reliable. The knowledge from this project can also contribute to environmental conservation by applying them to the field of oil and gas industries to store their wastes safe

  13. Demonstration and Dialogue: Mediation in Swedish Nuclear Waste Management. Deliverable D10

    International Nuclear Information System (INIS)

    Elam, Mark; Sundqvist, Goeran; Lidberg, Maria; Soneryd, Linda

    2008-10-01

    This report analyses mediation and mediators in Swedish nuclear waste management. Mediation is about establishing agreement and building common knowledge. It is argued that demonstrations and dialogue are the two prominent approaches to mediation in Swedish nuclear waste management. Mediation through demonstration is about showing, displaying, and pointing out a path to safe disposal for inspection. It implies a strict division between demonstrator and audience. Mediation through dialogue on the other hand, is about collective acknowledgements of uncertainty and suspensions of judgement creating room for broader discussion. In Sweden, it is the Swedish Nuclear Fuel and Waste Management Co. (SKB) that is tasked with finding a method and a site for the final disposal of the nation's nuclear waste. Two different legislative frameworks cover this process. In accordance with the Act on Nuclear Activities, SKB is required to demonstrate the safety of its planned nuclear waste management system to the government, while in respect of the Swedish Environmental Code, they are obliged to organize consultations with the public. How SKB combines these requirements is the main question under investigation in this report in relation to materials deriving from three empirical settings: 1) SKB's safety analyses, 2) SKB's public consultation activities and 3) the 'dialogue projects', initiated by other actors than SKB broadening the public arena for discussion. In conclusion, an attempt is made to characterise the long-term interplay of demonstration and dialogue in Swedish nuclear waste management

  14. Waste minimization fundamental principles used in radioactive waste management plan for decommissioning of a CANDU - 600 nuclear power plant

    International Nuclear Information System (INIS)

    Barariu, Gheorghe; Georgescu, Roxana Cristiana; Sociu, Florin

    2009-01-01

    The objectives of waste minimization are to limit the generation and spread of radioactive contamination and to reduce the amount of wastes for storage and disposal, thereby limiting any consequent environmental impact, as well as the total costs associated with contaminated material management. This objective will be achieved by: reviewing the sources and characteristics of radioactive materials arising from Decontamination and Decommissioning (D and D) activities; reviewing waste minimization principles and current practical applications, together with regulatory, technical, financial and political factors influencing waste minimization practices; and reviewing current trends in improving waste minimization practices during Decontamination and Decommissioning. The main elements of a waste minimization strategy can be grouped into four areas: source reduction, prevention of contamination spread, recycle and reuse, and waste management optimization. For sustaining this objective, the following principles and procedures of wastes management are taken into account: safety and environment protection principles; principles regarding the facility operation; quality assurance procedures; procedures for material classification and releasing. (authors)

  15. Nuclear waste management

    International Nuclear Information System (INIS)

    1982-12-01

    The subject is discussed, with special reference to the UK, under the headings: radiation; origins of the waste (mainly from nuclear power programme; gas, liquid, solid; various levels of activity); dealing with waste (methods of processing, storage, disposal); high-active waste (storage, vitrification, study of means of eventual disposal); waste management (UK organisation to manage low and intermediate level waste). (U.K.)

  16. Quality management system for the disposal of low and medium levels radioactive wastes - RBMN

    Energy Technology Data Exchange (ETDEWEB)

    Azevedo, Antonio Mario P.; Haucz, Maria Judite A.; Fraga, Rosane Rodrigues, E-mail: ampa@cdtn.br, E-mail: hauczmj@cdtn.br, E-mail: rosaner@cdtn.br [Centro de Desenvolvimento de Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    This article compares the standards applied in quality and safety management systems for the Disposal of Radioactive Waste. The comparison will be a contribution to development, maintenance and improvement the safety and quality system of a disposal of low and medium radioactive waste (RBMN) coordinated by CDTN - Brazilian Development Center for Nuclear Technology). (author)

  17. Quality management system for the disposal of low and medium levels radioactive wastes - RBMN

    International Nuclear Information System (INIS)

    Azevedo, Antonio Mario P.; Haucz, Maria Judite A.; Fraga, Rosane Rodrigues

    2011-01-01

    This article compares the standards applied in quality and safety management systems for the Disposal of Radioactive Waste. The comparison will be a contribution to development, maintenance and improvement the safety and quality system of a disposal of low and medium radioactive waste (RBMN) coordinated by CDTN - Brazilian Development Center for Nuclear Technology). (author)

  18. Technical appraisal of the current situation in the field of radioactive waste management

    International Nuclear Information System (INIS)

    1985-01-01

    Industrial activities are regarded as safe even though a small risk always exists. The philosophy of radiation protection accepts this and recognises that some level of risk will also be associated with safe radioactive waste management. Therefore the objective of radioactive waste management is to look for a strategy which, taken as a whole, is considered safe and provides an acceptable balance of all the radiological, technical, social, political and economic considerations. The RWMC's appraisal underlines the need for such a balance while concentrating on radiological and technical factors, particularly on the long term safety aspects of radioactive waste management. The fundamental conclusion is that detailed short and long term safety assessments can now be made which give confidence that radiation protection objectives can be met with currently available technology for most waste types, and at a cost which is only a small fraction of the overall cost of nuclear-generated power

  19. Waste management

    DEFF Research Database (Denmark)

    Bruun Hansen, Karsten; Jamison, Andrew

    2000-01-01

    The case study deals with public accountability issues connected to household waste management in the municipality of Copenhagen, Denmark.......The case study deals with public accountability issues connected to household waste management in the municipality of Copenhagen, Denmark....

  20. Management of tritium contaminated wastes national strategies and practices at some European countries, USA and Canada

    International Nuclear Information System (INIS)

    Mannone, F.

    1992-01-01

    The European Tritium Handling Experiment Laboratory (ETHEL) is the Commission of European Communities facility designed for handling multigram quantities of tritium for safety inherent R and D purposes. Tritium contamined wastes in gaseous, liquid and solid forms will be generated in ETHEL during the experiments as well as during the maintenance operations. All such wastes must be adequately managed under the safest operating conditions to minimize the releases of tritium to the environment and the consequent radiological risks to workers and general population. This safety requirement can be met by carefully defining strategies and practices to be applied for the safe management of these wastes. To this end an adequate background information must be collected which is the intent of this report. Through an exhaustive literature survey current strategies and practices applied in Europe, USA and Canada for managing tritiated wastes from specific tritium handling laboratories and plant have been assessed. For some countries, where only tritium bearing wastes simultaneously contaminated with nuclear fission products are generated, the attention has been focused on the strategies and practices currently applied for managing fission wastes. Operational criteria for waste collection, sorting, classification, conditioning and packaging as well as acceptance criteria for their storage or disposal have been identified. Waste storage or disposal options already applied in various countries or still being investigated in terms of safety have also been considered. Even if the radwaste management strategy is submitted to a nearly continuing process of review, some general comments resulting from the assessment of the present waste management scenario are presented. 60 refs., 16 figs., 13 tabs

  1. The management of radioactive wastes in China

    International Nuclear Information System (INIS)

    Teng Lijun

    2001-01-01

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

  2. The management of intermediate-level radioactive wastes arising from reprocessing operations

    International Nuclear Information System (INIS)

    Elsden, A.D.

    1984-01-01

    The reprocessing of spent nuclear fuel results in the generation of radioactive wastes in the form of liquids, gases and solids. This paper outlines the principles and major elements of the waste management systems currently in use or under development for the category of waste known as intermediate-level wastes. To enable implementation of an optimized waste management system, engineering process evaluations, development and design in the following areas are required: The definition of cost effective options taking account of constraints which may arise from other operations in the overall system, e.g. from transport requirements or from criteria derived from environmental impact assessments of alternative disposal routes; Plant and equipment development to enable acceptable system and active plant operations on an industrial scale; Safety and reliability studies to ensure adequate protection of both the general public and plant operators during all stages of the waste management system including disposal

  3. Development of system for management of radioactive waste from non-nuclear application in Russia

    International Nuclear Information System (INIS)

    Barinov, A.

    2000-01-01

    The 'Radon' system serves for collecting, transporting, conditioning and disposal of radioactive waste with low and intermediate level activity and spent ionizing sources. The technical policy in this field is embodied most completely in the 'Concept of RF Minatom on radioactive waste management', which outlines the activities till 2025. The main organizational and technical measures in enhancing safety in the process of radioactive waste management as well as the organization of radiation control are described. The main statements of the quality assurance programme for the radioactive waste management are presented

  4. Development of system for management of radioactive waste from non-nuclear application in Russia

    Energy Technology Data Exchange (ETDEWEB)

    Barinov, A [SIA ' Radon' , Moskow (Russian Federation)

    2000-07-01

    The 'Radon' system serves for collecting, transporting, conditioning and disposal of radioactive waste with low and intermediate level activity and spent ionizing sources. The technical policy in this field is embodied most completely in the 'Concept of RF Minatom on radioactive waste management', which outlines the activities till 2025. The main organizational and technical measures in enhancing safety in the process of radioactive waste management as well as the organization of radiation control are described. The main statements of the quality assurance programme for the radioactive waste management are presented.

  5. Radioactive waste management registry. A software tool for managing information on waste inventory

    International Nuclear Information System (INIS)

    Miaw, S.T.W.

    2001-01-01

    The IAEA developed a software tool, the RWM Registry (Radioactive Waste Management Registry) which is primarily concerned with the management and recording of reliable information on the radioactive waste during its life-cycle, i.e. from generation to disposal and beyond. In the current version, it aims to assist the management of waste from nuclear applications. the Registry is a managerial tool and offers an immediate overview of the various waste management steps and activities. This would facilitate controlling, keeping track of waste and waste package, planning, optimizing of resources, monitoring of related data, disseminating of information, taking actions and making decisions related to the waste management. Additionally, the quality control of waste products and a Member State's associated waste management quality assurance programme are addressed. The tool also facilitates to provide information on waste inventory as required by the national regulatory bodies. The RWM Registry contains two modules which are described in detail

  6. A strategy for upgrading management of spent fuel and radioactive waste at the Ignalina nuclear power plant

    International Nuclear Information System (INIS)

    Balan, V.; Penkov, V.; Bergman, C.; Gustafsson, B.

    2001-01-01

    The waste management strategy of the former Soviet Union, based on its Norms and Rules, was implemented at Ignalina nuclear power Plant (INPP). This means in brief that the spent nuclear fuel (SNF) should be reprocessed in the Soviet Union and the management of radioactive waste should be done in connection with the eventual decommissioning of the reactors, The major facilities for management of radioactive waste were evaporation of liquid waste and subsequent bitumenisation of the sludge, treatment of liquid with ion-exchange techniques and subsequent storage of the resins in tanks. Solid waste was sorted according to its activity content and stored on site. Following the independence of Lithuania in 1990, Lithuania is successively replacing the former Norms and Rules with Lithuanian laws and regulations. Lithuania has signed both the Convention of Nuclear Safety and the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The paper will give an overview of the work done, in progress and planned, primarily from an operational point of view. It will give examples of practical problems which have to be overcome and how very tough prioritisation has to be made because of lack of resources. Many of the problems are associated with the fact that the waste management strategy successively has to be changed at the same time as the generation of SNF and radioactive waste is continued. A lot has already been achieved, especially regarding the SNF. However, the main work is still to be done until the INPP can declare that its waste is properly managed in full compliance with a national waste management strategy which eventually will end with the disposal in licensed repositories. (author)

  7. Oak Ridge National Laboratory Waste Management Plan, fiscal year 1994. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    Turner, J.W. [ed.

    1993-12-01

    US Department of Energy (DOE) Order 5820.2A was promulgated in final form on September 26, 1988. The order requires heads of field organizations to prepare and to submit updates on the waste management plans for all operations under their purview according to the format in Chap. 6, {open_quotes}Waste Management Plan Outline.{close_quotes} These plans are to be submitted by the DOE Oak Ridge Operations Office (DOE-ORO) in December of each year and distributed to the DP-12, ES&H-1, and other appropriate DOE Headquarters (DOE-HQ) organizations for review and comment. This document was prepared in response to this requirement for fiscal year (FY) 1994. The Oak Ridge National Laboratory (ORNL) waste management mission is reduction, collection, storage, treatment, and disposal of DOE wastes, generated primarily in pursuit of ORNL missions, in order to protect human health and safety and the environment. In carrying out this mission, waste management staff in the Waste Management and Remedial Action Division (WMRAD) will (1) guide ORNL in optimizing waste reduction and waste management capabilities and (2) conduct waste management operations in a compliant, publicly acceptable, technically sound, and cost-efficient manner. Waste management requirements for DOE radioactive wastes are detailed in DOE Order 5820.2A, and the ORNL Waste Management Program encompasses all elements of this order. The requirements of this DOE order and other appropriate DOE orders, along with applicable Tennessee Department of Environment and Conservation and US Environmental Protection Agency (EPA) rules and regulations, provide the principal source of regulatory guidance for waste management operations at ORNL. The objective of this document is compilation and consolidation of information on how the ORNL Waste Management Program is conducted, which waste management facilities are being used to manage wastes, what activities are planned for FY 1994, and how all of the activities are documented.

  8. GEOSAF Part II. Demonstration of the operational and long-term safety of geological disposal facilities for radioactive waste. IAEA international intercomparison and harmonization project

    Energy Technology Data Exchange (ETDEWEB)

    Kumano, Yumiko; Bruno, Gerard [International Atomic Energy Agency, Vienna (Austria). Vienna International Centre; Tichauer, Michael [IRSN, Institut de Radioprotection et de Surete Nucleaire, Fontenay-aux-Roses (France); Hedberg, Bengt [Swedish Radiation Safety Authority, Stockholm (Sweden)

    2015-07-01

    International intercomparison and harmonization projects are one of the mechanisms developed by the IAEA for examining the application and use of safety standards, with a view to ensuring their effectiveness and working towards harmonization of approaches to the safety of radioactive waste management. The IAEA has organized a number of international projects on the safety of radioactive waste management; in particular on the issues related to safety demonstration for radioactive waste management facilities. In 2008, GEOSAF, Demonstration of The Operational and Long-Term Safety of Geological Disposal Facilities for Radioactive Waste, project was initiated. This project was completed in 2011 by delivering a project report focusing on the safety case for geological disposal facilities, a concept that has gained in recent years considerable prominence in the waste management area and is addressed in several international safety standards. During the course of the project, it was recognized that little work was undertaken internationally to develop a common view on the safety approach related to the operational phase of a geological disposal although long-term safety of disposal facility has been discussed for several decades. Upon completion of the first part of the GEOSAF project, it was decided to commence a follow-up project aiming at harmonizing approaches on the safety of geological disposal facilities for radioactive waste through the development of an integrated safety case covering both operational and long-term safety. The new project was named as GEOSAF Part II, which was initiated in 2012 initially as 2-year project, involving regulators and operators. GEOSAF Part II provides a forum to exchange ideas and experience on the development and review of an integrated operational and post-closure safety case for geological disposal facilities. It also aims at providing a platform for knowledge transfer. The project is of particular interest to regulatory

  9. Industrial Program of Waste Management - Cigeo Project - 13033

    Energy Technology Data Exchange (ETDEWEB)

    Butez, Marc [Agence nationale pour la gestion des dechets radioactifs - Andra, 1-7, rue Jean Monnet 92298 Chatenay-Malabry (France); Bartagnon, Olivier; Gagner, Laurent [AREVA NC Tour AREVA 1 place de la Coupole 92084 Paris La Defense (France); Advocat, Thierry; Sacristan, Pablo [Commissariat a l' energie atomique et aux energies alternatives - CEA, CEA-SACLAY 91191 Gif sur Yvette Cedex (France); Beguin, Stephane [Electricite de France - EDF, Division Combustible Nucleaire, 1, Place Pleyel Site Cap Ampere93282 Saint Denis (France)

    2013-07-01

    The French Planning Act of 28 June 2006 prescribed that a reversible repository in a deep geological formation be chosen as the reference solution for the long-term management of high-level and intermediate-level long-lived radioactive waste. It also entrusted the responsibility of further studies and design of the repository (named Cigeo) upon the French Radioactive Waste Management Agency (Andra), in order for the review of the creation-license application to start in 2015 and, subject to its approval, the commissioning of the repository to take place in 2025. Andra is responsible for siting, designing, implementing, operating the future geological repository, including operational and long term safety and waste acceptance. Nuclear operators (Electricite de France (EDF), AREVA NC, and the French Commission in charge of Atomic Energy and Alternative Energies (CEA) are technically and financially responsible for the waste they generate, with no limit in time. They provide Andra, on one hand, with waste packages related input data, and on the other hand with their long term industrial experiences of high and intermediate-level long-lived radwaste management and nuclear operation. Andra, EDF, AREVA and CEA established a cooperation agreement for strengthening their collaborations in these fields. Within this agreement Andra and the nuclear operators have defined an industrial program for waste management. This program includes the waste inventory to be taken into account for the design of the Cigeo project and the structural hypothesis underlying its phased development. It schedules the delivery of the different categories of waste and defines associated flows. (authors)

  10. Industrial Program of Waste Management - Cigeo Project - 13033

    International Nuclear Information System (INIS)

    Butez, Marc; Bartagnon, Olivier; Gagner, Laurent; Advocat, Thierry; Sacristan, Pablo; Beguin, Stephane

    2013-01-01

    The French Planning Act of 28 June 2006 prescribed that a reversible repository in a deep geological formation be chosen as the reference solution for the long-term management of high-level and intermediate-level long-lived radioactive waste. It also entrusted the responsibility of further studies and design of the repository (named Cigeo) upon the French Radioactive Waste Management Agency (Andra), in order for the review of the creation-license application to start in 2015 and, subject to its approval, the commissioning of the repository to take place in 2025. Andra is responsible for siting, designing, implementing, operating the future geological repository, including operational and long term safety and waste acceptance. Nuclear operators (Electricite de France (EDF), AREVA NC, and the French Commission in charge of Atomic Energy and Alternative Energies (CEA) are technically and financially responsible for the waste they generate, with no limit in time. They provide Andra, on one hand, with waste packages related input data, and on the other hand with their long term industrial experiences of high and intermediate-level long-lived radwaste management and nuclear operation. Andra, EDF, AREVA and CEA established a cooperation agreement for strengthening their collaborations in these fields. Within this agreement Andra and the nuclear operators have defined an industrial program for waste management. This program includes the waste inventory to be taken into account for the design of the Cigeo project and the structural hypothesis underlying its phased development. It schedules the delivery of the different categories of waste and defines associated flows. (authors)

  11. Waste management policy and its implementation in Finland

    International Nuclear Information System (INIS)

    Maekipentti, I.

    1984-01-01

    One of the main principles of Finnish nuclear legislation is that the waste producers - i.e. power companies - shall bear the total responsibility for all waste management operations including final disposal and for all the costs of these operations. The government shall assume the responsibility after the final repository has been approved as fulfilling the safety requirements and after sufficient financial assurances covering the costs of continued surveillance have been given to the authorities. The terms of the operation licences prefer the export of high-level waste to a foreign destination, but as an alternative require preparatory activities for final disposal in domestic territory. The spent fuel from two of the four existing units is returned to the fuel supplier country, the Soviet Union, but the management of spent fuel from the two other units is open. In Finland nuclear waste management has become one of the key problems in the public debate relating to the use of nuclear energy and especially to the licensing of additional nuclear power units. The small size of the national economy may cause some additional difficulties in the efforts to solve waste management problems. Public opinion is in favour of plans for waste management arrangements and facilities being prepared in advance of the licensing of new nuclear units, although it might accept the fact that it is not reasonable to carry out the actual management operations until after rather long storage. The small size of the national economy together with the fact that there are only four nuclear power units in Finland essentially limits the ability to allocate major resources to waste management R and D work and to develop Finnish solutions independently. The political situation which prevails as regards back-end operations internationally may even hinder the extended construction of nuclear plants and use of nuclear energy

  12. Investigation of health care waste management in Binzhou District, China

    International Nuclear Information System (INIS)

    Ruoyan, Gai; Xu Lingzhong; Li Huijuan; Zhou Chengchao; He Jiangjiang; Yoshihisa, Shirayama; Tang Wei; Chushi, Kuroiwa

    2010-01-01

    In China, national regulations and standards for health care waste management were implemented in 2003. To investigate the current status of health care waste management at different levels of health care facilities (HCF) after the implementation of these regulations, one tertiary hospital, one secondary hospital, and four primary health care centers from Binzhou District were visited and 145 medical staff members and 24 cleaning personnel were interviewed. Generated medical waste totaled 1.22, 0.77, and 1.17 kg/bed/day in tertiary, secondary, and primary HCF, respectively. The amount of medical waste generated in primary health care centers was much higher than that in secondary hospitals, which may be attributed to general waste being mixed with medical waste. This study found that the level of the HCF, responsibility for medical waste management in departments and wards, educational background and training experience can be factors that determine medical staff members' knowledge of health care waste management policy. Regular training programs and sufficient provision of protective measures are urgently needed to improve occupational safety for cleaning personnel. Financing and administrative monitoring by local authorities is needed to improve handling practices and the implementation of off-site centralized disposal in primary health care centers.

  13. The Management System for the Development of Disposal Facilities for Radioactive Waste

    International Nuclear Information System (INIS)

    2011-01-01

    Currently, many Member States are safely operating near surface disposal facilities and some are in the initial or advanced stages of planning geological repositories. As for other nuclear facilities and their operational phase, all activities associated with the disposal of radioactive waste need to be carefully planned and systematic actions undertaken in order to maintain adequate confidence that disposal systems will meet performance as well as prescribed safety requirements and objectives. The effective development and application of a management system (integrating requirements for safety, protection of health and the environment, security, quality and economics into one coherent system) which addresses every stage of repository development is essential. It provides assurance that the objectives for repository performance and safety, as well as environmental and quality criteria, will be met. For near surface repositories, a management system also provides the opportunity to re-evaluate existing disposal systems with respect to new safety, environmental or societal requirements which could arise during the operational period of a facility. The topic of waste management and disposal continues to generate public interest and scrutiny. Implementation of a formal management system provides documentation, transparency and accountability for the various activities and processes associated with radioactive waste disposal. This information can contribute to building public confidence and acceptance of disposal facilities. The objective of this report is to provide Member States with practical guidance and relevant information on management system principles and expectations for management systems that can serve as a basis for developing and implementing a management system for three important stages; the design, construction/upgrading and operation of disposal facilities. To facilitate the understanding of management system implementation at the different stages of a

  14. Radioactive waste management in the USSR: A review of unclassified sources

    International Nuclear Information System (INIS)

    Bradley, D.J.

    1991-03-01

    The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of contaminated areas. Meanwhile, many treatment, solidification, and disposal options for radioactive waste management are being investigated by the Soviets

  15. Life Management and Safety of Nuclear Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Fabbri, S.; Diluch, A.; Vega, G., E-mail: fabbri@cnea.gov.ar [Comisión Nacional de Energía Atómica, Buenos Aires (Argentina)

    2014-10-15

    The nuclear programme in Argentina includes: nuclear power and related supplies, medical and industrial applications, waste management, research and development and human training. Nuclear facilities require life management programs that allow a safe operation. Safety is the first priority for designers and operators. This can be attained with defence in depth: regular inspections and maintenance procedures to minimize failure risks. CNEA objectives in this area are to possess the necessary capability to give safe and fast technical support. Within this scheme, one of the main activities undertaken by CNEA is to provide technological assistance to the nuclear plants and research reactors. As a consequence of an increasing concern about safety and ageing a Life Management Department for safe operation was created to take care of these subjects. The goal is to elaborate a Safety Evaluation Process for the critical components of nuclear plants and other facilities. The overall objectives of a safety process are to ensure a continuous safe, reliable and effective operation of nuclear facilities and it means the implementation of the defence in deep concept to enhance safety for the protection of the public, the workers and the environment. (author)

  16. Radioactive Waste Management Complex low-level waste radiological performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

    1994-04-01

    This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.

  17. Radioactive Waste Management Complex low-level waste radiological performance assessment

    International Nuclear Information System (INIS)

    Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

    1994-04-01

    This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected

  18. The management of high level waste and its environmental impact

    International Nuclear Information System (INIS)

    Saunders, P.A.H.

    1981-01-01

    This paper summarises the techniques that are used for the management of the radioactive wastes that result from the nuclear generation of electricity and that cannot be released directly into the environment. The quantities and characteristics of the wastes are outlined and a description is given of current and probable future stores and their environmental impact. The research and development programme that is being undertaken to establish the safety and environmental impact of an ultimate repository is discussed and a comparison is made between the activities and toxic potentials of the wastes and those of naturally occurring materials, fossil fuels and fertilisers. It is concluded that the wastes can be managed without undue risk to man or to the environment. (author)

  19. Radioactive Waste Management Basis

    International Nuclear Information System (INIS)

    Perkins, B.K.

    2009-01-01

    The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

  20. Application of SAFRAN Tool for the Knowledge Management at the Stage of Radioactive Waste Retrieval from Historical Radon-type Storage Facility

    International Nuclear Information System (INIS)

    Smetnik, A.; Murlis, D.

    2016-01-01

    Our task was to assess waste retrieval operations from a typical RADON-type historical waste storage facility during decommissioning. Challenges: “Historical radioactive waste” is generated without a complete traceable characterization programme or quality management system in place. Key characteristics of historical waste are: — may be conditioned, partially treated, or raw; — poor or no information/traceability; — cannot conclusively identify originating process/location; — waste streams may be mixed. Conclusions: • SAFRAN uses methodologies agreed upon at the international level, namely, by IAEA standards; • Several experts can work more effectively when performing the same safety assessment. SAFRAN makes it easier to exchange experience through sharing projects and data bases; • It is helpful for systematic and structured safety assessment as per safety standards; • It manages information and data in the same software environment. • SAFRAN can play a significant role in managing records and knowledge on radioactive waste, nuclear facility site, characteristics of geological environment and safety barriers. • It can provide reliable long-term storage and effective management of safety related records for the purposes of safety reassessments, review and supervision.