WorldWideScience

Sample records for radioactive waste 1986 1990

  1. 1990 State-by-State assessment of low-level radioactive wastes received at commercial disposal sites

    International Nuclear Information System (INIS)

    Fuchs, R.L.; Culbertson-Arendts, K.

    1991-09-01

    Each year the National Low-Level Waste Management Program publishes a state-by-state assessment report. This annual report provides both national and state-specific disposal data on low-level radioactive wastes. Data in this report are categorized according to disposal site, generator category, waste class, volume, and activity. Included in this report are tables showing a distribution of wastes by state for 1990 and a comparison of waste volumes by state for 1986 through 1990; also included is a list of all commercial nuclear power reactors in the United States as of December 31, 1990. In this year's report, a distinction has been made between low-level radioactive waste shipped directly by generators for disposal and that which was handled by an intermediary. 5 refs., 4 tabs

  2. 1990 State-by-State assessment of low-level radioactive wastes received at commercial disposal sites

    Energy Technology Data Exchange (ETDEWEB)

    Fuchs, R.L.; Culbertson-Arendts, K.

    1991-09-01

    Each year the National Low-Level Waste Management Program publishes a state-by-state assessment report. This annual report provides both national and state-specific disposal data on low-level radioactive wastes. Data in this report are categorized according to disposal site, generator category, waste class, volume, and activity. Included in this report are tables showing a distribution of wastes by state for 1990 and a comparison of waste volumes by state for 1986 through 1990; also included is a list of all commercial nuclear power reactors in the United States as of December 31, 1990. In this year's report, a distinction has been made between low-level radioactive waste shipped directly by generators for disposal and that which was handled by an intermediary. 5 refs., 4 tabs.

  3. Characterization of Class A low-level radioactive waste 1986--1990

    International Nuclear Information System (INIS)

    Dehmel, J.C.; Loomis, D.; Mauro, J.; Kaplan, M.

    1994-01-01

    Under contract to the US Nuclear Regulatory Commission, office of Nuclear Regulatory Research, the firms of S. Cohen ampersand Associates, Inc. (SC ampersand A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG ampersand G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the waste from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 through 7 contain Appendices A through P with supporting information

  4. Characterization of Class A low-level radioactive waste 1986--1990

    International Nuclear Information System (INIS)

    Dehmel, J.C.; Loomis, D.; Mauro, J.; Kaplan, M.

    1994-01-01

    Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen ampersand Associates, Inc. (SC ampersand A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG ampersand G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the waste from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 to 7 contain Appendices A to P with supporting information

  5. Characterization of Class A low-level radioactive waste 1986--1990

    International Nuclear Information System (INIS)

    Dehmel, J.C.; Loomis, D.; Mauro, J.; Kaplan, M.

    1994-01-01

    Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen ampersand Associates, Inc. (SC ampersand A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG ampersand G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the waste from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 through 7 contain Appendices A through P with supporting information

  6. Co-ordinated research and environmental surveillance programme related to sea disposal of radioactive waste CRESP activity report 1986-1990

    International Nuclear Information System (INIS)

    1990-01-01

    The Co-ordinated Research and Environmental Surveillance Programme relevant to sea disposal of radioactive waste (CRESP) was created in 1981 in the framework of the 1977 Decision of the OECD Council establishing a Multilateral Consultation and Surveillance Mechanism for Sea Dumping of Radioactive Waste. The main task of CRESP was to set up a site-specific scientific research programme to increase current knowledge of the processes controlling the transfer of radionuclides in the marine environment, so that impact of past dumping could be monitored and future assessments could be based on more accurate and comprehensive scientific data. The CRESP mandate was extended in 1987 to respond to a request from the Paris Commission to include consideration of radioactive discharges in the maritime area covered by the Convention on the Prevention of Marine Pollution from Land-Based Sources. This report summarizes the CRESP activities carried out during the 1986-1990 five year phase. Concerning the review of deep sea results, the report relates progress achieved above the level of knowledge which was available when the present phase of the CRESP programme was decided and which has been taken into account in the 1985 Site Suitability Review. With respect to coastal discharges, it presents a summary of R and D work undertaken by member countries, including those carried out in other programmes such as MARINA. Finally, it makes proposals for future work within CRESP

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

    International Nuclear Information System (INIS)

    Brennecke, P.; Schumacher, J.

    1987-05-01

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

  8. Radioactive waste management information for 1990 and record-to-date

    International Nuclear Information System (INIS)

    Litteer, D.L.; Peterson, C.N.; Sims, A.M.

    1991-07-01

    This document presents detailed data and graphics on volume, radioactivity, isotopic identity, origin, and decay status of radioactive waste for the calendar year 1990. It also summarizes the radioactive waste data records compiled from 1952 to present for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Radioactive Waste Management Information System (RWMIS)

  9. The 1986 United Kingdom radioactive waste inventory

    International Nuclear Information System (INIS)

    Shepherd, J.; Harrison, J.; McNicholas, P.

    1987-11-01

    This report gives information on the radioactive wastes which arise in the United Kingdom, updated to 1 January 1986. It has been compiled from information provided by the principal producers of the wastes, Amersham International plc, British Nuclear Fuels plc, the Central Electricity Generating Board, the South of Scotland Electricity Board, and the United Kingdom Atomic Energy Authority. The report lists the waste types, or streams, which these organisations produce, or will produce, as part of their normal operations or from decommissioning of their plant. For each stream is given the volume (or in a few cases mass) of existing stocks, estimated arisings to the year 2030 (2080 in the case of some decommissioning wastes), specific activity, and conditioning factor (volume change from ''raw'' waste volume to volume conditioned for disposal). Details of the radionuclide compositions of individual waste streams are separately listed. Waste streams are allocated to one of the three categories High, Intermediate or Low-Level, although this does not necessarily imply any commitment to a particular disposal route. The report includes tables summarising the data, arranged in a hierarchical manner to enable totals to be readily extracted as required. Summary tables of both ''raw'' and ''conditioned'' waste volumes are given. Also included are a commentary on the data and important changes from the 1985 inventory, and information on scenarios on which estimates of future arisings are based. (author)

  10. Higher Regional Court Celle, judgment of December 9, 1986 (legal term of radioactive waste)

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    In its decision of December 9, 1986, the Higher Regional Court in Celle deals with the legal term of radioactive waste. The definition does not result from sec. 1 para. 1 of the Waste Disposal Act but from sec. 9 a para. 1 Atomic Energy Act. (WG) [de

  11. Summary of radioactive solid waste received in the 200 Areas during calendar year 1990

    International Nuclear Information System (INIS)

    Anderson, J.D.; McCann, D.C.; Poremba, B.E.

    1991-04-01

    Westinghouse Hanford Company manages and operates the Hanford Site 200 Areas radioactive solid waste storage and disposal facilities for the US Department of Energy-Richland Operations Office under contract AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Areas radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1990. This report does not include solid radioactive wastes in storage or disposal in other areas or facilities such as the underground tank farms. Unless packaged within the scope of Hanford Site radioactive solid waste acceptance criteria, liquid waste data are not included in this document. 10 refs., 1 tab

  12. Characterization of radioactive waste forms. Progress report for 1986 Volume 1

    International Nuclear Information System (INIS)

    Glasser, F.P.; McCulloch, C.

    1988-01-01

    The Council of Ministers of the European Communities adopted the third five-year EC programme of research on radioactive waste management and disposal in March 1985. It was recognized that the inevitable production of radioactive waste required perfecting and demonstrating systems for managing the waste produced by the nuclear industry, ensuring at the various stages the best possible protection of man and the environment. Task 3 of the programme 'evaluation of conditioned waste and qualification of engineered barriers' is subdivided into five sections. This book, in two volumes, is a compilation of reports on the progress achieved in four of the sections during 1986, the first year of the third programme. Volume 1 is concerned with Sections 1 and 5, 'Research on low -and medium- active waste' and 'Quality control methods'. Volume 2 covers Section 2 'HLW form characterization' and Section 3 'Other engineered barriers'. Section 4 'Development of standard test methods' is not included in this edition, as results from an interlaboratory round robin test now in progress will only be available for inclusion for the year 1988

  13. Characterization of radioactive waste forms. Progress report for 1986 Volume 2

    International Nuclear Information System (INIS)

    Reed, D.L.; Mallinson, L.G.

    1988-01-01

    The Council of Ministers of the European Communities adopted the third five-year EC programme of research on radioactive waste management and disposal in March 1985. It was recognized that the inevitable production of radioactive waste required perfecting and demonstrating systems for managing the waste produced by the nuclear industry, ensuring at the various stages the best possible protection of man and the environment. Task 3 of the programme 'evaluation of conditioned waste and qualification of engineered barriers' is subdivided into five sections. This book, in two volumes, is a compilation of reports on the progress achieved in four of the sections during 1986, the first year of the third programme. Volume 1 is concerned with Sections 1 and 5, 'Research on low-and medium- active waste' and 'Quality control methods'. Volume 2 covers Section 2 'HLW form characterization' and Section 3 'Other engineered barriers' Section 4 'Development of standard test methods' is not included in this edition, as results from an interlaboratory round robin test now in progress will only be available for inclusion for the year 1988

  14. Historically Black Colleges and Universities Radioactive Waste Management Research Program: Summary of activities, 1985-1986

    International Nuclear Information System (INIS)

    1986-01-01

    This report summarizes the 1985 to 1986 activities of the Historically Black Colleges and Universities (HBCUs) Radioactive Waste Management Research Program sponsored by the Office of Civilian Radioactive Waste Management of the US Department of Energy (DOE). The first set of three awards was made in September,1984. In September, 1985, two of these projects were renewed and a new proposal was funded. The program has been enthusiastically received by the community of HBCUs and the program sponsor

  15. Characterization of Class A low-level radioactive waste 1986--1990. Volume 7: Appendices K--P

    Energy Technology Data Exchange (ETDEWEB)

    Dehmel, J.C.; Loomis, D.; Mauro, J. [S. Cohen & Associates, Inc., McLean, VA (United States); Kaplan, M. [Eastern Research Group, Inc., Lexington, MA (United States)

    1994-01-01

    Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen & Associates, Inc. (SC&A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG&G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the waste from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 through 7 contain Appendices A through P with supporting information.

  16. U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1986-1990

    Science.gov (United States)

    Trask, N.J.; Stevens, P.R.

    1991-01-01

    The report summarizes progress on geologic and hydrologic research related to the disposal of radioactive wastes. The research efforts are categorized according to whether they are related most directly to: (1) high-level wastes, (2) transuranic wastes, (3) low-level and mixed low-level and hazardous wastes, or (4) uranium mill tailings. Included is research applicable to the identification and geohydrologic characterization of waste-disposal sites, to investigations of specific sites where wastes have been stored, to development of techniques and methods for characterizing disposal sites, and to studies of geologic and hydrologic processes related to the transport and/or retention of waste radionuclides.

  17. Report to Congress in response to Public Law 99-240: 1990 Annual report on low-level radioactive waste management progress

    International Nuclear Information System (INIS)

    1991-09-01

    This report summarizes the progress during 1990 of states and compact regions in establishing new low-level radioactive waste disposal facilities. It also provides summary information on the volume of low-level radioactive waste received for disposal in 1990 by commercially operated low-level radioactive waste disposal facilities. This report is in response to section 7 (b) of the Low-Level Radioactive Waste Policy Act, as amended by Public Law 99-240

  18. The 1986 state-by-state assessment of low-level radioactive wastes received at commercial disposal sites

    International Nuclear Information System (INIS)

    1987-12-01

    The data are grouped and presented by compact regions. The data include activity and volume by waste classes, generator type, and disposal site. The report uses the volume of low-level waste reported as received at each commercial disposal site as the national baseline figure. A volume of 1,804,998 cubic feet (51,113 cubic meters) of radioactive waste containing 233,726 curies of activity was reported disposed at the commercial sites in 1986. The total volume and curie values tabulated for each state were obtained directly from the commercial disposal site operators. The total is the sum of the volume and radioactivity reported by Chem Nuclear Systems, Inc., and US Ecology for each state. Sixty-three percent of low-level waste volumes disposed at commercial sites was assigned to the state of origin. These volumes represent those disposed at Beatty and Barnwell disposal sites. Thirty-seven percent, or 665,066 cubic feet (18,831 cubic meters), of the waste disposed in the US in 1986 went to the Richland site. 8 refs., 75 figs., 4 tabs

  19. Characterization of Class A low-level radioactive waste 1986--1990. Volume 3: Main report -- Part B

    Energy Technology Data Exchange (ETDEWEB)

    Dehmel, J.C.; Loomis, D.; Mauro, J. [S. Cohen & Associates, Inc., McLean, VA (United States); Kaplan, M. [Eastern Research Group, Inc., Lexington, MA (United States)

    1994-01-01

    Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen & Associates, Inc. (SC&A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG&G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the waste from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 to 7 contain Appendices A to P with supporting information.

  20. Radioactive waste below regulatory concern

    International Nuclear Information System (INIS)

    Neuder, S.M.

    1987-01-01

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

  1. IAEA's radioactive waste management programme a change in direction for the 1990's

    International Nuclear Information System (INIS)

    Saire, Donald E.

    1991-01-01

    The IAEA has been assisting Member States in the management and disposal of radioactive wastes for almost three decades. This assistance has largely been in the form of providing an international form for the exchange of information on subjects of mutual interest and in offering technical assistance from developed Member States to developing Member States. In the 1980's, the Agency's programme concentrated on the collection, review and publication of state-of-the-art technology covering such subject fields as handling and processing of wastes from nuclear power plants and fuel cycle facilities, gaseous waste management, near-surface disposal of low-and intermediate-level radioactive wastes, deep geological disposal of high-level and transuranic wastes, radiological and environmental effects of waste disposal and the decontamination and decommissioning of nuclear installations. While the Agency still plans to serve as the main forum for the exchange of information on radioactive waste management two new areas of activity will receive emphasis in the 1990's

  2. Idaho National Engineering Laboratory hazardous and radioactive mixed waste identification and characterization report for CY 1986

    International Nuclear Information System (INIS)

    Nishimoto, D.D.

    1987-05-01

    This report provides updated tabulations of the hazardous and radioactive mixed wastes generated and/or handled during CY 1986 at each INEL facility operated by EG and G, or any other operating contractor at the Site. These wastes are described in tabular form, providing information such as composition, generating process, contact person, EPA hazardous waste designation, quantity shipped off site (if applicable), and quantity in storage. Waste generation projections for the next ten years are also included for all INEL facilities. Finally, since many of EG and G's inactive disposal sites may prove to be significant sources of either hazardous or radioactive mixed wastes as remedial action activities under RCRA or CERCLA progress, information on these sites is provided. 2 refs., 1 fig., 8 tabs

  3. 1986 Annual report on Low-Level Radioactive Waste Management progress

    International Nuclear Information System (INIS)

    1987-06-01

    This report summarizes the progress of states and compact regions without low-level waste disposal sites (non-sited compact regions and nonmember states) in 1986 in siting new low-level waste disposal facilities. It also reports the volume of low-level waste received for disposal in 1986 by commercially operated low-level waste disposal facilities. 6 figs., 7 tabs

  4. Savannah River solid radioactive waste forecast, FY 1986

    International Nuclear Information System (INIS)

    Thomas, S.D.

    1986-07-01

    The 1986 Solid Waste Forecast considers two types of waste: nonretrievable and retrievable (transuranic) waste. The effect of new facilities (DWPF, Naval Fuels, etc.) beginning operation coupled with plant-wide efforts to compact or reduce the volume of waste sent to 643-7G will tend to stabilize the solid waste generation rate over the forecast period (CY 1986--1995). Volume reduction by incineration and compaction, which is expected to increase during the forecast period, could reduce the volume of nonretrievable waste requiring burial by 50%. The volume of transuranic (TRU) waste generated each year is expected to increase to approximately 32,000 ft 3 /yr in 1987 and then decrease and stabilize at 17,000 ft 3 /yr TRU during the forecast period. A program is underway to process and dispose of all retrievably stored TRU waste and newly generated waste over approximately a 16-year period beginning in 1993. This program will reduce the amount of waste that must be shipped to the Waste Isolation Pilot Plant (WIPP) for permanent disposal and process that waste which is not certifiable for the WIPP. 9 figs., 7 tabs

  5. Information about the field of nuclear waste 1986

    International Nuclear Information System (INIS)

    1986-01-01

    The Consultative Committee for Nuclear Waste Management (KASAM) reports about the knowledge 1986 concerning the management and the ultimate storage of radioactive wastes. In the report discusses ethical aspects, technical and scientific problems related to the radioactive waste disposal. Still there is no plant in the world build for ultimate storage of high-level radioactive wastes, but many states have plans for building such plants. The report gives a survey of different storage technics, chemical, hydrochemical and radioecological problems. Some international and national programs are reviewed. (K.A.E.)

  6. The fourth radioactive waste management program of the Commission of the European Communities (1990-1994)

    International Nuclear Information System (INIS)

    Orlowski, S.; Schaller, K.H.; Simon, R.

    1992-01-01

    The fourth radioactive waste management program 1990-1994 is aimed at perfecting and demonstrating a system of management of radioactive waste, including unprocessed irradiated fuels where these are considered as waste, which will ensure, at the various stages, the best possible protection of man and the environment. In particular, research continues on the characterization and qualification of the various barriers, both engineered and natural (geological) considered in the multiple barrier disposal concept, and the findings are used to evaluate the long-term safety of this waste disposal concept. The program is implemented mainly through shared-cost research contracts with appropriate organizations, undertakings and companies - public or private - established in the European Community Member States. It is composed of two parts; Part A deals with waste management studies and associated research and development actions, whereas in Part B, the construction and operation of underground pilot and/or site validation facilities for deep geological disposal of radioactive waste open to Community joint activities are covered. (author)

  7. Incineration of low level and mixed wastes: 1986

    International Nuclear Information System (INIS)

    Anon.

    1986-01-01

    The University of California at Irvine, in cooperation with the Department of Energy, American Society of Mechanical Engineers, and chapters of the Health Physics Society, coordinated this conference on the Incineration of Low-Level Radioactive and Mixed Wastes, with the guidance of professionals active in the waste management community. The conference was held in April 22-25, 1986 at Sheraton airport hotel Charlotte, North Carolina. Some of the papers' titles were: Protection and safety of different off-gas treatment systems in radioactive waste incineration; performance assessment of refractory samples in the Los Alamos controlled-Air incinerator; incineration systems for low-level and mixed wastes; incineration of low-level radioactive waste in Switzerland-operational experience and future activities

  8. Commercial low-level radioactive waste management

    International Nuclear Information System (INIS)

    Coleman, J.A.

    1982-01-01

    The goals, objectives and activities of the Department of Energy's Low-Level Radioactive Waste Management program are reviewed. The goal of the overall Program is to support development of an acceptable, nationwide, near surface waste disposal system by 1986. The commercial LLW program has two major functions: (1) application of the technology improvements for waste handling, treatment and disposal, and (2) assistance to states as they carry out their responsibilities under the Low-Level Radioactive Waste Policy Act of 1980. The priorities for the commercial side of the Low-Level Waste Management Program have been established to meet one goal: to support development of an effective commercial management system by 1986. The first priority is being given to supporting state efforts in forming the institutional structures needed to manage the system. The second priority is the state and industry role in transferring and demonstrating treatment and disposal technologies

  9. Summary of expenditures of rebates from the low-level radioactive waste surcharge escrow account for calendar year 1990

    International Nuclear Information System (INIS)

    1991-06-01

    This is the fifth report submitted to Congress under Title 1, section 5(d)(2)(E) of Public Law 99--240, ''The Low-Level Radioactive Waste Policy Amendments Act of 1985'' (the Act). This section of the Act requests the Department of Energy (DOE) to summarize the annual expenditures of funds disbursed from the DOE surcharge escrow account and to assess compliance of these expenditures with the specified limitations. The Act places limitations on the use of these funds and requires the nonsited compact regions and nonmember States to provide DOE with an itemized report of their expenditures on December 31 of each year in which funds are expended. Within 6 months after receiving the individual reports, DOE is to furnish Congress a summary of the reported expenditures and an assessment of compliance with the limitations on the use of these funds specified in the Act. This report fulfills that requirements. DOE disbursed funds totaling $15,006,587.76 to the States and compact regions following the July 1, 1986, January 1, 1988, and January 1, 1990, milestones. Of this amount, $4,328,340.44 was expended during calendar year 1990 and $2,239,205.80 was expended during the prior 4 years. At the end of December 1990, $8,439,041.52 was unexpended. 5 tabs

  10. Hydrologic data for the Weldon Spring radioactive waste-disposal sites, St. Charles County, Missouri; 1984-1986

    Science.gov (United States)

    Kleeschulte, M.J.; Emmett, L.F.; Barks, J.H.

    1986-01-01

    Hydrologic and water quality data were collected during an investigation of the Weldon Spring radioactive waste disposal sites and surroundings area in St. Charles County, Missouri, from 1984 to 1986. The data consists of water quality analyses of samples collected from 45 groundwater and 27 surface water sites. This includes analyses of water from four raffinate pits and from the Weldon Spring quarry. Also included in the report are the results of a seepage run on north flowing tributaries to Dardenne Creek from Kraut Run to Crooked Creek. Mean daily discharge from April 1985 to April 1986 is given for two springs located about 1.5 mi north of the chemical plant. (USGS)

  11. The Mixed Waste Management Facility closure and expansion at the Savannah River Site

    International Nuclear Information System (INIS)

    Bittner, M.F.; Frye-O'Bryant, R.C.

    1992-01-01

    Process wastes containing radioactive and hazardous constituents have been generated throughout the operational history of the Savannah River Site. Solid wastes containing low level radionuclides were buried in Low Level Radioactive Disposal Facility (LLRWDF). Until 1986, waste containing lead and cadmium was disposed of in the Mixed Waste Management Facility (MWMF) portion of LLRWDF. Between 1986 and 1990, waste containing F-listed hazardous rags were buried. Current Resource Conservation and Recovery Act (RCRA) regulations prohibit the disposal of these hazardous wastes at nonpermitted facilities. This paper describes the closure activities for the MWMF, completed in 1990 and plans proposed for the expansion of this closure to include the LLRWDF suspect solvent rag trenches

  12. Disposal of low-level radioactive wastes

    International Nuclear Information System (INIS)

    Hendee, W.R.

    1986-01-01

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

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

    International Nuclear Information System (INIS)

    1994-08-01

    This report presents a history of commercial low-level radioactive waste disposal in the United States, with emphasis on the history of six commercially operated low-level radioactive waste disposal facilities. The report includes a brief description of important steps that have been taken during the last decade to ensure the safe disposal of low-level radioactive waste in the 1990s and beyond. These steps include the issuance of comprehensive State and Federal regulations governing the disposal of low-level radioactive waste, and the enactment of Federal laws making States responsible for the disposal of such waste generated within their borders

  14. The Swedish programme for radioactive waste management

    International Nuclear Information System (INIS)

    Bjurstroem, S.; Forsstroem, H.

    1986-10-01

    The following systems and facilities are currently in operation and under implementation: a sea transportation system for all kinds of nuclear waste, a central facility for interim storage of spent fuel (CLAB) and a central underground repository for final disposal of low and medium level reactor waste (SFR). For the remaining steps - final disposal of highly active and longlived radioactive residues - a concept, based on encapsulation of the fuel elements in copper canisters and final storage of the canisters in a repository situated 500 m down in crystalline rock (KBS-3), has been developed and approved by the government in accordance with the Swedish nuclear legislation. Although a feasible method for final disposal of the highly active residues has been shown, the Swedish legislation requires that research be carried out to reach the best possible base for the final decision around the year 2000. In parallel with this a geological investigation programme is carried out to find a suitable site for a final repository. The final site selection is foreseen at the end of the 1990's. All costs for the management of radioactive waste from the nuclear power plants are carried by a fee determined annually. The fee is 0.019 SEK/kWh for 1986

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

    International Nuclear Information System (INIS)

    1990-10-01

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

  16. Radioactive waste in Federal Germany

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  17. Disposal of low-level and mixed low-level radioactive waste during 1990

    International Nuclear Information System (INIS)

    1993-08-01

    Isotopic inventories and other data are presented for low-level radioactive waste (LLW) and mixed LLW disposed (and occasionally stored) during calendar year 1990 at commercial disposal facilities and Department of Energy (DOE) sites. Detailed isotopic information is presented for the three commercial disposal facilities located near Barnwell, SC, Richland, WA, and Beatty, NV. Less information is presented for the Envirocare disposal facility located near Clive, UT, and for LLW stored during 1990 at the West Valley site. DOE disposal information is included for the Savannah River Site (including the saltstone facility), Nevada Test Site, Los Alamos National Laboratory, Idaho National Engineering Laboratory, Hanford Site, Y-12 Site, and Oak Ridge National Laboratory. Summary information is presented about stored DOE LLW. Suggestions are made about improving LLW disposal data

  18. The low-level radioactive waste crisis

    International Nuclear Information System (INIS)

    Bord, R.J.

    1988-01-01

    According to the author, the goals of the 1980 Low-Level Radioactive Waste Policy Act have not been met. That act stipulated that regional disposal sites were to be established by 1986. To date, no new sites have been established and none are anywhere near the construction phase. Congress, responding to existing impasse, has extended the deadline to the end of 1992 with the passage of the Low-Level Radioactive Waste Policy Act. The reasons for the impasse are no mystery: local intransigence regarding waste of any kind, public fears of radiation hazards, and politicians' anxieties about their constituents' fears. The focus of this paper is the viability of ongoing attempts to overcome public intransigence in the case of disposal siting for low-level radioactive waste (LLRW)

  19. 1990 waste tank inspection program

    International Nuclear Information System (INIS)

    McNatt, F.G.

    1990-01-01

    Aqueous radioactive wastes from Savannah River Site separations processes are contained in large underground carbon steel tanks. Tank conditions are evaluated by inspection using periscopes, still photography, and video systems for visual imagery. Inspections made in 1990 are the subject of this report

  20. Radioactive waste management

    International Nuclear Information System (INIS)

    Tsoulfanidis, N.

    1991-01-01

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

  1. Managing low-level radioactive waste in Massachusetts. Final report

    International Nuclear Information System (INIS)

    Bander, S.R.; Goldstein, M.E.

    1983-12-01

    As one of the country's largest generators of low-level radioactive waste, Massachusetts has begun independently seeking solutions to the questions surrounding low-level waste management issues. The Massachusetts Department of Public Health, Radiation Control Program, obtained funding from the U.S. Department ofEnergy through EG and G, Idaho, Inc. to develop a low-level waste management strategy for the Commonwealth. The Working Group was made up of individuals from various waste generating industries, environmental and public interest groups, medical and academic institutions, and affected state agencies. This final report document contains the following staff project reports: Proposed Low-Level Radioactive Waste Management Plan for The Commonwealth of Massachusetts, February 1983 and Low-Level Radioactive Waste Management in Massachusetts - Actions to be Considered for Implementation in 1984-1986, December 1983. These two staff reports represent the completion of the Massachusetts Low-Level Radioactive Waste Management Project. The first report provides some of the background material to the issues and some of the alternative courses of action which can be considered by state policy-makers. The second report provides the next phase in the process by delineating specific steps which may be taken before 1986 in order to address the low-level waste problem, and the estimated amount of time needed to complete each step

  2. A process for treating radioactive water-reactive wastes

    International Nuclear Information System (INIS)

    Dziewinski, J.; Lussiez, G.; Munger, D.

    1995-01-01

    Los Alamos National Laboratory and other locations in the complex of experimental and production facilities operated by the United States Department of Energy (DOE) have generated an appreciable quantity of hazardous and radioactive wastes. The Resource Conservation and Recovery Act (RCRA) enacted by the United States Congress in 1976 and subsequently amended in 1984, 1986, and 1988 requires that every hazardous waste must be rendered nonhazardous before disposal. Many of the wastes generated by the DOE complex are both hazardous and radioactive. These wastes, called mixed wastes, require applying appropriate regulations for radioactive waste disposal and the regulations under RCRA. Mixed wastes must be treated to remove the hazardous waste component before they are disposed as radioactive waste. This paper discusses the development of a treatment process for mixed wastes that exhibit the reactive hazardous characteristic. Specifically, these wastes react readily and violently with water. Wastes such as lithium hydride (LiH), sodium metal, and potassium metal are the primary wastes in this category

  3. Cost for the radioactive wastes from nuclear power

    International Nuclear Information System (INIS)

    1989-06-01

    The future cost for handling, storing and disposing of radioactive wastes from the Swedish nuclear power plants are calculated in this report. The following plants and systems are already operating: - Transportsystem for radioactive wastes. - A control spent fuel intermediate storage plant. - A repository for low and medium level wastes. These are planned: - A treatment plant for used fuels. A repository for high-level wastes and repository for decommissioning wastes. The costs include Rand D and decommissioning. Total future costs from 1990 are estimated to be 43 billion SEK (6,5 billion dollars), during 60 years. Up to 1990 7,4 billion SEK (1,1 billion dollars) have been spent. (L.E.)

  4. Savannah River Interim Waste Management Program Plan - FY 1986

    International Nuclear Information System (INIS)

    1985-09-01

    This document provides the program plan as requested by the Savannah River Operations Office of the Department of Energy. The plan was developed to provide a working knowledge of the nature and extent of the interim waste management programs being undertaken by Savannah River (SR) contractors for the Fiscal Year 1986. In addition, the document projects activities for several years beyond 1986 to adequately plan for safe handling and storage of radioactive wastes generated at Savannah River and for developing technology for improved management of low-level solid wastes. A revised plan will be issued prior to the beginning of the first quarter of each fiscal year. In this document, work descriptions and milestone schedules are current as of the date of publication. Budgets are based on available information as of May 1985

  5. Radioactivity in surface and coastal waters of the British Isles, 1986

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1987-01-01

    The report presents the results of the environmental monitoring programme carried out during 1986 by staff of the Directorate of Fisheries Research, Lowestoft, United Kingdom. The programme was set up to verify the satisfactory control of liquid radioactive waste discharges to the aquatic environment, and to ensure that the resulting public radiation exposure is within nationally-accepted limits. The environmental programme includes monitoring the environmental consequences of discharges of liquid radioactive wastes from four British Nuclear Fuels plc sites - at Sellafield, Springfield, Capenhurst and Chapelcross, and monitoring the environment impact of liquid radioactive discharges from Winfrith and Dounraey. Monitoring is also carried out near nuclear power stations operated by the electricity boards, near Naval establishments, near Amersham International plc, and the marine environment of the Channel Islands States. Results are also presented on the monitoring of the freshwater environment for radioactivity from the Chernobyl reactor accident. (U.K.)

  6. ICRP guidance on radioactive waste disposal

    International Nuclear Information System (INIS)

    Cooper, J.R.

    2002-01-01

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

  7. Environmental radioactivity in Canada 1986

    International Nuclear Information System (INIS)

    1987-01-01

    The radiological surveillance program of the Department of National Health and Welfare is conducted for the purpose of determining levels of environmental radioactivity in Canada and assessing the resulting population exposures. During 1986 the program was strongly influenced by radioactive fallout on Canada resulting from the Chernobyl nuclear reactor accident on April 26, 1986 in the Soviet Ukraine. The Environmental Radiation Hazards Division (ERHD) increased its frequency of analyses of environmental samples immediately following the accident. Interim screening limits for foodstuffs were developed. A measurement program for radioactivity in domestic and imported foods was implemented. The ERHD measurement program was supplemented by additional measurements conducted by many other private and government laboratories. Radiation doses to Canadian from Chernobyl fallout were extremely low with no group in the population receiving more than 10 microsieverts

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

    International Nuclear Information System (INIS)

    Bealby, J.

    1989-03-01

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

  9. Greater-than-Class-C low-level radioactive waste management concepts

    International Nuclear Information System (INIS)

    Knecht, M.A.

    1988-01-01

    In 1986, Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985 assigned to the Federal Government responsibility for the disposal of commercial greater-than-Class-C (GTCC) low-level radioactive waste (LLW). In 1987, DOE committed to Congress to accept GTCC LLW and provide storage and other waste management as necessary until disposal capacity is available. Current estimates are that about 6,000 m 3 of unpackaged GTCC LLW will be generated to the year 2020. Generators estimate that 100 m 3 of raw GTCC LLW might exceed planned storage capacity to the year 2020. This paper reports the activities of the National Low-Level Waste Program to manage GTCC low-level radioactive waste

  10. Radioactive waste from nuclear power stations and other nuclear facilities

    International Nuclear Information System (INIS)

    Jelinek-Fink, P.

    1976-01-01

    After estimating the amounts of liquid and solid radioactive wastes that will be produced in nuclear power plants, reprocessing plants, by the fuel cycle industry, and in the nuclear research centers in the FRG until 1990, it is reported on the state of technology and on the tendencies in the development of processing radioactive waste. The paper also describes, how waste disposal is managed by those producing radioactive waste (see above), and discusses the future development of the complex of waste disposal from the industry's point of view. (HR/LN) [de

  11. Low-level radioactive waste management in New York State: Meeting the milestones

    International Nuclear Information System (INIS)

    White, I.L.

    1987-01-01

    The federal Low-Level Radioactive Waste Policy Act of 1980 made the states responsible for disposal of low-level radioactive waste (LLRW) generated within their borders. After extensive hearings and public participation, New York State enacted a Radioactive Waste Management Act (State LLRWMA) in July 1986. This paper describes New York's program and reviews the State's progress in complying with the milestone established by Public Law 99-240. A number of concerns about LLRW disposal and the schedule calling for a facility to be operational by January 1, 1993, are also discussed

  12. Radioactive waste in the Federal Republic of Germany. Systems study. Vol. 1

    International Nuclear Information System (INIS)

    Dyroff, H.; Fleischmann, F.K.

    1976-01-01

    Taking the probable developments in the fields of nuclear technology, and the data specific for the wastes of certain plants, the overall rate of radioactive wastes in the FRG from 1975 till 1990 is estimated and some prognostications are made up till the year 2000. The analysis of the waste rate in the FRG from 1975 till 1990 shows that the wastes of nuclear power plants, compared with those of the reprocessing plants, predominate quantitatively, but looking at it from the radiological properties it becomes obvious that almost all radioactivity released in nuclear technology is contained in reprocessing wastes. With regard to the fuel cycle industry, those substances from the U/Pu fuel production which emit alpha radiation present a special problem. Radioactive wastes from large research centres, from industry research, collecting depots of the Laender, and isotope technology are of no significance, neither with regard to the quantity nor from the point of view of radioactivity. (orig./HR) [de

  13. HMIP Monitoring Programme radioactive substances report for 1990

    International Nuclear Information System (INIS)

    1992-03-01

    The programme of environmental monitoring of radioactive substances in England and Wales during 1990, was completed satisfactorily under the auspices of Her Majesty's Inspectorate of Pollution. The programme concentrates on monitoring activity levels in environmental materials which might result in radiation exposure of the public from non-food pathways. The programme acts as a check on site operator's returns and provides independent data on the environmental impact of authorised disposals of radioactive wastes and on radiation doses to critical groups of the public. This report presents the data from this continuing monitoring programme. The monitoring was carried out at installations controlled by British Nuclear Fuels PLC, Nuclear Electric the United Kingdom Atomic Energy Authority, Amersham International PLC, the Ministry of Defence, at two non-nuclear sites which use tritium, the works of Capper Pass Ltd who carry out lead smelting and at several landfill sites where controlled buried of low-level radioactive wastes is carried out. (Author)

  14. Photonuclear data index 1986-1990

    Energy Technology Data Exchange (ETDEWEB)

    Varlamov, V A; Stepanov, M E; Sapunenko, V V [Moscow State University, Institute of Nuclear Physics, Centre for Photonuclear Experimental Data, Moscow (Russian Federation)

    1992-07-01

    This issue presents a bibliographic index to experimental photonuclear data published in periodical scientific literature during the years 1986-1990. The main tabulation is sorted by nucleus and reaction. It is supplemented by a reference index, an author index, explanatory tables of terms and abbreviations used, and a table of isotopic abundances and nucleon separation energies. The index is in English with an introduction in Russian and English. (author)

  15. Radioactive waste management profiles

    International Nuclear Information System (INIS)

    1991-10-01

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

  16. Radioactive waste management: Spanish experiences

    International Nuclear Information System (INIS)

    Beceiro, A. R.

    1996-01-01

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

  17. Appalachian States Compact Low-Level Radioactive Waste management survey, 1987

    International Nuclear Information System (INIS)

    Singh, K.N.

    1989-03-01

    Since the enactment of the Low-Level Radioactive Waste Disposal Act in February 1988, the Commonwealth of Pennsylvania has undertaken major steps to develop a Low-Level Radioactive Waste (LLRW) Disposal Facility within its borders for the exclusive use of radioactive material licensees in the Appalachian States Compact. In order to adequately plan for the design and development of that facility, it is essential to obtain accurate data on LLRW being generated in the Compact. To that end, the Division of Nuclear Safety of the Pennsylvania Bureau of Radiation Protection (BRP) conducted a survey to determine volume and activity of LLRW shipped and stored in 1987 by the licensees in the Appalachian States Compact. The 1986 LLRW survey included licensees in Pennsylvania and Maryland, while surveys conducted prior to 1986 involved only Pennsylvania licensees. So this is the first survey conducted by BRP that has included all four states of the Compact

  18. Radioactive wastes in the Malargue district

    International Nuclear Information System (INIS)

    Moyano, Alejandro

    2004-01-01

    After a short description of the Malargue district and the site of the radioactive mineral wastes accumulated till 1986, as a result of the uranium ores treatment, the book describes the regulatory framework and criticizes the process of approval of the environmental restoration project. Deficiencies in the public opinion consultation are pointed out. The urgency of a prompt execution of the restoration works is stressed

  19. Radioactive liquid wastes lines removal project at Los Alamos (1981-1986)

    International Nuclear Information System (INIS)

    Elder, J.C.; Cox, E.J.; Hohner, D.P.; Valentine, A.M.

    1986-09-01

    This report describes the abandoned liquid waste lines removal operations conducted at Los Alamos in the period 1981 to 1986. Particular emphasis has been placed on as-left conditions, that is, on the location of sections of waste lines or contaminated soil which were left in place on the basis of ALARA decisions. Contaminated items were left when interfering utilities, roads, structures, or great depth made complete removal not cost effective or not safe. Left items were either not highly contaminated or they were not near the surface. Total cost of the project was $4.2 million. Approximately 5800 m 3 of contaminated waste was placed in the Solid Waste Management Site at TA-54 Area G. The project accomplished the removal of approximately 34,500 ft (6.5 miles) of abandoned waste lines under carefully controlled conditions. Procedures for excavation, waste disposal, personnel protection, and radiation monitoring are described. Environmental monitoring criteria and methods for determining acceptable levels of contamination in soils and on surfaces are discussed

  20. 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

  1. RADIOACTIVE WASTE MANAGEMENT IN THE USSR: A REVIEW OF UNCLASSIFIED SOURCES, 1963-1990

    Energy Technology Data Exchange (ETDEWEB)

    Bradley, D. J.; Schneider, K. J.

    1990-03-01

    volume of 100-150 liters/MT of fuel reprocessed); 3) set it aside in air-cooled storage for 30-50 years; and 4} provide for its final disposal in a deep geologic repository. High-level waste solidification research started in the 1950s, and a pilot vitrification facility has operated for 10 years at Kyshtym. A fully radioactive unit also operated there for about two years until 1988 and produced 160 MT of HLW phosphate glass, containing 3.9 x 106 curies of radioactivity. [This corresponds to radioactivity in about 10 MT of 10-year-old power reactor fuel.] Problems with the glass melter electrodes have caused this latter plant to shut down, but a new design and plant are being developed. A site near Krasnoyarsk has also recently been referred to as a disposal site for low- and intermediate-level waste streams and possibly for vitrified wastes from Kyshtym. Deep geologic disposal of vitrified high-level waste has been studied, at a modest level of effort, over the last decade in the Soviet Union. Key disposal concepts under consideration include mining shafts, deep drill holes, and underground excavations. Although a variety of host rock types have been addressed, the emphasis appears to be on salt, clay, and granite. The Soviet Union appears to require the use of man-made barriers and waste packages in permanent disposal, but the geologic formation will be relied upon as the primary protective barrier. The construction schedule for a Soviet repository has not been stated. Meanwhile, a decision on the first repository site may be made in 1990, with a candidate site being at Chelyabinsk.

  2. 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

  3. Hazardous waste minimization report for CY 1986

    International Nuclear Information System (INIS)

    Kendrick, C.M.

    1990-12-01

    Oak Ridge National Laboratory (ORNL) is a multipurpose research and development facility. Its primary role is the support of energy technology through applied research and engineering development and scientific research in basic and physical sciences. ORNL also is a valuable resource in the solution of problems of national importance, such as nuclear and chemical waste management. In addition, useful radioactive and stable isotopes which are unavailable from the private sector are produced at ORNL. As a result of these activities, hazardous, radioactive, and mixed wastes are generated at ORNL. A formal hazardous waste minimization program for ORNL was launched in mid 1985 in response to the requirements of Section 3002 of the Resource Conservation and Recovery Act (RCRA). During 1986, a task plan was developed. The six major tasks include: planning and implementation of a laboratory-wide chemical inventory and the subsequent distribution, treatment, storage, and/or disposal (TSD) of unneeded chemicals; establishment and implementation of a distribution system for surplus chemicals to other (internal and external) organizations; training and communication functions necessary to inform and motivate laboratory personnel; evaluation of current procurement and tracking systems for hazardous materials and recommendation and implementation of improvements; systematic review of applicable current and proposed ORNL procedures and ongoing and proposed activities for waste volume and/or toxicity reduction potential; and establishment of criteria by which to measure progress and reporting of significant achievements. 8 refs., 1 fig., 5 tabs

  4. Determining ''Best Practicable Environmental Options'' for final waste disposal of radioactive waste

    International Nuclear Information System (INIS)

    Smith, Graham

    1999-01-01

    This presentation discusses some ideas on what the Best Practical Environmental Option (BPEO) process should include. A BPEO study to help develop a radioactive waste management strategy should not only look at post-closure safety of a facility. In the UK there was a 1986 Study of BPEOs for management of low and intermediate level radioactive wastes. This study tried to answer important questions such as (1) What are the practical options, (2) Which wastes should go to shallow burial, (3) Which wastes should go to sea disposal, (4) How does storage compare with disposal and (5) What are the cost and environmental trade-offs. The presentation discusses what was done to answer the questions. The BPEO Study resulted in major improved effort to characterise waste, much greater quantitative understanding of where and when the real costs, and environmental and radiological impacts arise. All options would be useful within a national strategy. But there was clearly a need for resolution of political acceptance problems, integration of policy with other hazardous waste management, and stronger legal framework

  5. Beatty, Nevada: A section in U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1986-1990 (WRI 91-4084)

    Science.gov (United States)

    Andraski, Brian J.; Fisher, Jeffrey M.; Prudic, David E.; Trask, N.J.; Stevens, P.R.

    1991-01-01

    A low-level radioactive-waste disposal facility in the Amargosa Desert of Nevada, about 17 km southeast of Beatty and 169 km northwest of Las Vegas, has been operating since 1962. This was the first commercially operated radioactive waste disposal facility in the United States. Wastes at the facility are emplaced in 2 to 15-m deep trenches and covered by backfilling with previously excavated materials. Annual precipitation in the area averages about 112 mm. Vegetation is sparse with creosote bush (Larrea tridentata) being the dominant species. Soils in the area are skeletal and are underlain by more than 170 m of unconsolidated alluvial-fan, fluvial, and ephemeral-lake deposits. Depth to water is about 85 m.Initial field investigations (1976-1980) included monitoring of soil-water content and water potential in an unvegetated soil profile, and collection of meteorological data at the disposal facility. Design of additional hydrogeologic investigations and long-term studies of soil-water movement in a vegetated soil profile began in 1982 and field data collection has been ongoing since 1984. Studies to evaluate the modifying effects of trench construction on the natural site environment and to determine changes in trench structural stability began in 1987. Design of studies to measure gas and vapor movement in the trenches at the facility began in 1989.

  6. Disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Dlouhy, Z.

    1982-01-01

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

  7. Report of Activities 1986-1990

    International Nuclear Information System (INIS)

    Pham Duy Hien; Tran Ha Anh; Ton That Con; Nguyen Gia Viet Hoa

    1991-01-01

    The significant progresses reached by the Nuclear research Institute (Dalat) in the period 1986-1990 are presented. Three important areas of activities which have been carried out simultaneously are: 1/to build up suitable infrastructure and laboratories for full exploitation of the newly reconstructed nuclear research reactor (put into operation in 1984); 2/to develop practical application of nuclear techniques related to using the reactor and the Co-60 irradiator; 3/to stimulate and to support the establishment of nationwide laboratories and centres for application of radioisotopes and nuclear techniques. (N.H.A)

  8. 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)

  9. [National Congress of American Indians]: Final 1985-1986 progress report, March 1, 1986-October 7, 1986

    International Nuclear Information System (INIS)

    1986-01-01

    This quarterly report summarizes the activities of the National Congress of American Indians NCAI Fund program to disseminate information and provide technical assistance to American Indian governments regarding nuclear waste management, site selection and transportation issues. The report covers the grant period March 1, 1986, to October 7, 1986, which includes the no-cost extension granted in March of 1986 and the grant amendment for July 3 to October 3, 1986. During this period, the project held three national meetings of the National Indian Nuclear Waste Policy Committee (NINWPC); monitored the DOE Office of Civilian Radioactive Waste Management (OCRWM) program and congressional activity and provided information to the tribes; published five issues of the Sentinel/Bulletin - NCAI News, which included a number of articles on nuclear waste; provided informational mailings to the NINWPC representatives; attended and coordinated meetings between the tribes, Department of Energy (DOE), Nuclear Regulatory Commission (NRC), the Bureau of Indian Affairs (BIA), Environmental Protection Agency (EPA), and Sandia National Laboratories; and provided speakers to conferences and groups

  10. Integrated data base for 1990: US spent fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1990-10-01

    The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1989. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 22 refs., 48 figs., 109 tabs

  11. Results of the CRCPD survey of 1984 low-level radioactive waste: progress to mid-September, 1986

    International Nuclear Information System (INIS)

    Devine, T.L.

    1987-01-01

    The survey of 1984 low-level radioactive waste by the Conference of Radiation Control Program Directors, Inc., is the second such survey. The previous survey was for waste generated during 1982. The CRCPD survey of 1984 LLRW requested information concerning the license, the effluents and other on-site managed wastes, details of exported waste type, the capacity for storing waste prior to shipment and its average utilization during 1984. Details of the exported waste included waste type, processing and packaging, NRC class, burial site or broker to which the waste was sent, and anticipated waste generation by year and by class through 1989. Shortcomings of the questionnaire and preliminary results are discussed. Based on the results of the two surveys of low-level radioactive waste conducted by the CRCPD, and the serious discrepancies which exist between data on waste shipped by generators and that on waste received by disposal sites, the following recommendation is made. That a single, national repository be established for all data on the generation and ultimate disposition of low-level radioactive waste. 1 figure, 1 table

  12. Radioactive solid waste inventories at United States Department of Energy burial and storage sites

    International Nuclear Information System (INIS)

    Watanabe, T.

    1987-06-01

    Radioactive solid waste inventories are given for United States Department of Energy (DOE) burial and storage sites. These data are obtained from the Solid Waste Information Management System (SWIMS) and reflect the inventories as of the end of the calendar year 1986. 4 figs., 7 tabs

  13. 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

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

    International Nuclear Information System (INIS)

    Anon.

    1994-01-01

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

  15. Radioactive wastes

    International Nuclear Information System (INIS)

    Teillac, J.

    1988-01-01

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

  16. Classification of solid wastes as non-radioactive wastes

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  17. Radioactive waste management

    International Nuclear Information System (INIS)

    Blomek, D.

    1980-01-01

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

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

    International Nuclear Information System (INIS)

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

    1977-01-01

    The nature of Canadian nuclear fuel and nuclear generating plant radioactive wastes are summarized. Full exploitation of fission energy resources entails recovery of all fissile and fertile material from spent fuel and separating the fission products as wastes for disposal. A plan for final disposal of all the radioactive wastes is a key component of the waste management scheme. Principles of a scheme for safe, responsible disposal of long-lived radioactive wastes deep underground in isolation from man and the biosphere are outlined. The status of the development and construction program is indicated. We plan to select a site in either a hard rock formation or in a suitable salt bed by 1981 so that a repository can be constructed to begin a demonstration phase in 1986. The repository is to be capable of eventual expansion to accomodate all Canadian nuclear wastes to at least 2050 when in full-scale operation. Extensive geotechnical studies have been initiated in order to select a site, and design and test the repository. We have demonstrated incorporation of fission products in solids that in the short term (17 years) dissolve more slowly than plutonium decays. Investigations of long-term stability are in hand. The principle of retardation of migration of fission products, so that they decay before surfacing, has been tested. Additional capacity for storage of used fuel prior to reprocessing and disposal is required by 1986 and a preliminary design has been prepared for a pool facility to be located at a central fuel recycling and disposal complex. A demonstration of dry storage of fuel in concrete containers is in progress. The quantities of CANDU generating-station wastes and the principles and methods for managing them are summarized. Methods for volume reduction and immobilization by solidification are well advanced. A radioactive-waste operations site is being developed with several different types of surface storage, each with multiple barriers against

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

    International Nuclear Information System (INIS)

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

    1977-01-01

    The nature of Canadian nuclear fuel and nuclear generating plant radioactive wastes is summarized. Full exploitation of fission energy resources entails recovery of all fissile and fertile material from spent fuel and separating the fission products as wastes for disposal. A plan for final disposal of all the radioactive wastes is a key component of the waste management scheme. Principles of a scheme for safe, responsible disposal of long-lived radioactive wastes deep underground, in isolation from man and the biosphere, are outlined. The status of the development and construction programme is indicated. It is planned to select a site in either a hard rock formation or in a suitable salt bed by 1981 so that a repository can be constructed to begin a demonstration phase in 1986. The repository is to be capable of eventual expansion to accomodate all Canadian nuclear wastes to at least 2050 when in full-scale operation. Extensive geotechnical studies have been initiated in order to select a site, and design and test the repository. The incorporation of fission products in solids that in the short term (17 years) dissolve more slowly than plutonium decays has been demonstrated. Investigations of long-term stability are in hand. The principle of retardation of migration of fission products, so that they decay before surfacing, has been tested. Additional capacity for storage of used fuel prior to reprocessing and disposal is required by 1986 and a preliminary design has been prepared for a pool facility to be located at a central fuel recycling and disposal complex. A demonstration of dry storage of fuel in concrete containers is in progress. The quantities of CANDU generating-station wastes and the principles and methods for managing them are summarized. Methods for volume reduction and immobilization by solidification are well advanced. A radioactive-waste operations site is being developed with several different types of surface storage, each with multiple barriers

  20. Community's research and development programme on radioactive waste management and storage shared-cost action (1990-94). Annual progress report 1991

    International Nuclear Information System (INIS)

    1992-01-01

    In december 1989 the Council of Ministers of the European Communities adopted the fourth R and D programme on 'Management and Storage of radioactive waste' for the period 1990-1994. Contract negotiations for selected research proposals lead to the signature of contracts with some 93 bodies in charge of carrying out the working programme. This annual report, covering the year 1991 presents for each contract the objectives, the whole research programme and a synopsis of progress and results achieved as prepared by the contractor under the responsibility of the project leader. Part A deals with the study of management systems, treatment and characterization of waste, general aspects of the waste disposal and the safety of geological disposal systems. The running activities on construction and operation of underground facilities in candidated geological media for disposal is presented in part B

  1. Defining greater-than-class-C low-level radioactive waste

    International Nuclear Information System (INIS)

    Knecht, M.A.; Oztunali, O.I.

    1986-01-01

    The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) was signed by President Reagan on January 15, 1986. This act requires the federal government to be responsible for the disposal of greater-than-class-C low-level radioactive waste (LLRW) that is generated commercially by state agencies and by federal entities (other than waste generated by atomic weapons research, development, or testing, or by decommissioning of vessels of the nuclear navy). To plan for disposal, the federal government will require estimates of the volume of waste involved and characterization of this waste. A clear definition of greater-than-class-C LLRW is the first step in determining what wastes will be included in the waste to be received by the federal government. This definition will influence major policy decisions to be made for management of such waste. The purpose of this paper is to examine the existing information on greater-than-class-C LLRW in view of the current definition of such waste and potential changes in this definition - for example, an upper limit on the concentrations of radionuclides in LLRW. The paper identifies further information needs to develop a clear definition of such waste for use in federal planning for acceptance of responsibility for disposal of such waste

  2. Radioactive waste management solutions

    International Nuclear Information System (INIS)

    Siemann, Michael

    2015-01-01

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

  3. Technical and socio-political issues in radioactive waste disposal 1986. Vol. 1A

    International Nuclear Information System (INIS)

    Parker, F.L.; Kasperson, R.E.; Andersson, T.L.; Parker, S.A.

    1987-11-01

    Review of radioactive waste management activities and goals in the Federal Republic of Germany, France, Sweden, Switzerland, United Kingdom, USA, European Communities, IAEA, NEA, ICRP and UNSCEAR. (HP)

  4. Disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Blomeke, J.O.

    1979-01-01

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

  5. Radioactive wastes

    International Nuclear Information System (INIS)

    Grass, F.

    1982-01-01

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

  6. Radioactive waste management

    International Nuclear Information System (INIS)

    Balek, V.

    1994-01-01

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

  7. Understanding radioactive waste

    International Nuclear Information System (INIS)

    Murray, R.L.

    1981-12-01

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

  8. Understanding radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Murray, R.L.

    1981-12-01

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

  9. 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.)

  10. Environmental monitoring report for commercial low-level radioactive waste disposal sites (1960's through 1990's)

    International Nuclear Information System (INIS)

    1996-11-01

    During the time period covered in this report (1960's through early 1990's), six commercial low-level radioactive waste (LLRW) disposal facilities have been operated in the US. This report provides environmental monitoring data collected at each site. The report summarizes: (1) each site's general design, (2) each site's inventory, (3) the environmental monitoring program for each site and the data obtained as the program has evolved, and (4) what the program has indicated about releases to off-site areas, if any, including a statement of the actual health and safety significance of any release. A summary with conclusions is provided at the end of each site's chapter. The six commercial LLRW disposal sites discussed are located near: Sheffield, Illinois; Maxey Flats, Kentucky; Beatty, Nevada; West Valley, New York; Barnwell, South Carolina; Richland, Washington

  11. Hydrologic and Meteorological Data for an Unsaturated-Zone Study Area near the Radioactive Waste Management Complex, Idaho National Engineering and Environmental Laboratory, Idaho, 1990-96

    International Nuclear Information System (INIS)

    Perkins, K. S.; Nimmo, J. R.; Pittman, J. R.

    1998-01-01

    Trenches and pits at the Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA) at the Idaho National Engineering and Environmental Laboratory (formerly known as the Idaho National Engineering Laboratory) have been used for burial of radioactive waste since 1952. In 1985, the U.S. Geological Survey (USGS), in cooperation with the U.S. Department of Energy, began a multi-phase study of the geohydrology of the RWMC to provide a basis for estimating the extent of and the potential for migration of radionuclides in the unsaturated zone beneath the waste trenches and pits. This phase of the study provides hydrologic and meteorological data collected at a designated test trench area adjacent to the northern boundary of the RWMC SDA from 1990 through 1996. The test trench area was constructed by the USGS in 1985. Hydrologic data presented in this report were collected during 1990-96 in the USGS test trench area. Soil-moisture content measurement from disturbed and undisturbed soil were collected approximately monthly during 1990-96 from 11 neutron-probe access holes with a neutron moisture gage. In 1994, three additional neutron access holes were completed for monitoring. A meteorological station inside the test trench area provided data for determination of evapotranspiration rates. The soil-moisture and meteorological data are contained in files on 3-1/2 inch diskettes (disks 1 and 2) included with this report. The data are presented in simple American Standard Code for Information Interchange (ASCII) format with tab-delimited fields. The files occupy a total of 1.5 megabytes of disk space

  12. Managing the nation's commercial high-level radioactive waste

    International Nuclear Information System (INIS)

    Cotton, T.

    1985-01-01

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

  13. Mixed Waste Management Facility closure at the Savannah River Site

    International Nuclear Information System (INIS)

    Bittner, M.F.

    1991-08-01

    The Mixed Waste Management Facility of the Savannah River Plant received hazardous and solid low level radioactive wastes from 1972 until 1986. Because this facility did not have a permit to receive hazardous wastes, a Resource Conservation and Recovery Act closure was performed between 1987 and 1990. This closure consisted of dynamic compaction of the waste trenches and placement of a 3-foot clay cap, a 2-foot soil cover, and a vegetative layer. Operations of the waste disposal facility, tests performed to complete the closure design, and the construction of the closure cap are discussed herein

  14. Low-level Radioactive waste Management

    International Nuclear Information System (INIS)

    1991-01-01

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

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

    International Nuclear Information System (INIS)

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

    1977-05-01

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

  16. Radiological effluent and onsite area monitoring report for the Nevada Test Site (January 1986-December 1986)

    International Nuclear Information System (INIS)

    Gonzalez, D.A.

    1987-09-01

    This report documents the environmental surveillance program at the Nevada Test Site as conducted by the Department of Energy (DOE) onsite radiological safety contractor from January 1986 through December 1986. It presents results and evaluations of radioactivity measurements in air and water, and of direct gamma radiation exposure rates. It establishes relevant correlations between the data recorded and DOE concentration guides (CG's). External gamma exposure levels and radioactivity in air and water on the Nevada Test Site were low compared to DOE guidelines. The highest average gross beta concentration in air was 0.005% of the DOE concentration guide (CG). The highest average Pu-239 concentration was 7.7% of the standard. The highest average tritium concentration was 0.39% of the standard. Kr-85 concentrations increased slightly from CY-1985 to CY-1986. Xe-133 remained nondetectable with some exceptions. The highest average gross beta concentration in potable water remained within the applicable standard for drinking water. The highest average Pu-239 concentration from contaminated waters was 0.0005% of the concentration guide. The highest average tritium concentration in noncontaminated water was 6% of the level for drinking water required by the National Interim Primary Drinking Water Regulation. The amounts of tritium-bearing effluent released to contaminated waste ponds was calculated and reported to DOE Headquarters. Gamma radiation measurements were roughly the same in CY-1986 relative to the previous year. All surveillance results from the Radioactive Waste Management Site (RWMS) indicate that no detectable releases of radioactive materials occurred in that network in 1986. 29 refs., 14 figs., 23 tabs

  17. Low-level radioactive-waste compacts. Status report as of July 1982

    International Nuclear Information System (INIS)

    1982-07-01

    The Low-Level Radioactive Waste Policy Act (P.L. 96-573), enacted in December 1980, established as federal policy that states take responsibility for providing disposal capacity for low-level radioactive waste (LLW) generated within their borders, except for defense waste and Federal R and D. At the request of Senator James A. McClure, Chairman of the Senate Committee on Energy and Natural Resources, DOE has documented the progress of states individually and collectively in fulfilling their responsibilities under the Public Law. Regionalization through formation of low-level waste compacts has been the primary vehicle by which many states are assuming this responsibility. To date seven low-level waste compacts have been drafted and six have been enacted by state legislatures or ratified by a governor. As indicated by national progress to date, DOE considers the task of compacting achievable by the January 1, 1986, exclusionary date set in law, although several states and NRC questioned this

  18. Low-level radioactive-waste compacts. Status report as of July 1982

    Energy Technology Data Exchange (ETDEWEB)

    1982-07-01

    The Low-Level Radioactive Waste Policy Act (P.L. 96-573), enacted in December 1980, established as federal policy that states take responsibility for providing disposal capacity for low-level radioactive waste (LLW) generated within their borders, except for defense waste and Federal R and D. At the request of Senator James A. McClure, Chairman of the Senate Committee on Energy and Natural Resources, DOE has documented the progress of states individually and collectively in fulfilling their responsibilities under the Public Law. Regionalization through formation of low-level waste compacts has been the primary vehicle by which many states are assuming this responsibility. To date seven low-level waste compacts have been drafted and six have been enacted by state legislatures or ratified by a governor. As indicated by national progress to date, DOE considers the task of compacting achievable by the January 1, 1986, exclusionary date set in law, although several states and NRC questioned this.

  19. Radioactive waste processing

    International Nuclear Information System (INIS)

    Dejonghe, P.

    1978-01-01

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

  20. 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

  1. Vermont's involvement with the DOE's high-level radioactive waste disposal crystalline repository project. Final technical report, January 1-September 30, 1986

    International Nuclear Information System (INIS)

    1986-09-01

    The US Department of Energy (DOE) is charged with siting a second repository for the disposal of highly radioactive nuclear wastes. Because of this siting process, the DOE has looked to localities in 17 states in the eastern US for possible sites in crystalline rock. During the beginning of the progress report period, crystalline rocks in Vermont were under consideration as sites for further study. Vermont, through the Vermont State Geologist's Office, was closely involved with the DOE program during this period. Our main function has been to review DOE reports; attend DOE workshops and meetings; and inform the Vermont public, with the help of the DOE, about the high-level nuclear waste repository siting process. Nine sites in Vermont were under consideration during the Regional Characterization Phase until January 16, 1986. Because of this fact, there was considerable public interest in this program. Upon release of the Draft Area Recommendation Report, Vermont crystalline rock bodies were dropped from consideration. A site in New Hampshire and two sites in Maine remained on the list. Because of the draft status of the report and the possibility that a site 20 miles from the Vermont border in New Hampshire could remain as a selected site, Vermont has stayed active and interested. Two briefings and hearings were held in the State during the comment period January 16 through April 16, 1986. A thorough review of the Draft Area Recommendation Report was completed using reviewers from our Office, State agencies, outside experts, and citizen groups. With the announcement on May 28, 1986 of the suspension of the second repository siting process in crystalline rocks, our Office has worked toward closing out our active involvement

  2. Office of Civilian Radioactive Waste Management annual report to Congress

    International Nuclear Information System (INIS)

    1990-12-01

    This seventh Annual Report to Congress by the Office of Civilian Radioactive Waste Management (OCRWM) describes activities and expenditures of the Office during fiscal years (FY) 1989 and 1990. In November 1989, OCRWM is responsible for disposing of the Nation's spent nuclear fuel and high-level radioactive waste in a manner that protects the health and safety of the public and the quality of the environment. To direct the implementation of its mission, OCRWM has established the following objectives: (1) Safe and timely disposal: to establish as soon as practicable the ability to dispose of radioactive waste in a geologic repository licensed by the NRC. (2) Timely and adequate waste acceptance: to begin the operation of the waste management system as soon as practicable in order to obtain the system development and operational benefits that have been identified for the MRS facility. (3) Schedule confidence: to establish confidence in the schedule for waste acceptance and disposal such that the management of radioactive waste is not an obstacle to the nuclear energy option. (4) System flexibility: to ensure that the program has the flexibility necessary for adapting to future circumstances while fulfilling established commitments. To achieve these objectives, OCRWM is developing a waste management system consisting of a geologic repository for permanent disposed deep beneath the surface of the earth, a facility for MRS, and a system for transporting the waste

  3. Radioactive wastes of Nuclear Industry

    International Nuclear Information System (INIS)

    1995-01-01

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

  4. Technical and socio-political issues in radioactive waste disposal 1986. Vol. 2

    International Nuclear Information System (INIS)

    Parker, F.L.; Kasperson, R.E.; Andersson, T.L.; Parker, S.A.

    1987-11-01

    Subseabed disposal of high level radioactive waste and spent fuel, in contrast to land based mined geologic repositories, has not yet been judged by any nation or international bodies to be technologically acceptable, but it is presently considered to be the only available alternative to land based geologic disposal. The work under the scientific program for subseabed disposal the most truly international of all the radioactive waste program, was proceeding along a well defined route to proof or rejection of concept. This date will certainly be delayed because of the withdrawal of the USA from the program. The work under the aegis of the NEA will result in a report in 1987 that will be a status report. To date no scientific information has emerged that would negate the advantages of the subseabed disposal method. Validation of some of the models has not been completed. The option, if possible, would be very attractive for many reasons including no easy direct exposure to man, no contamination of potential drinking water supplies, no near neighbors, an international solution rather than a parochial solution, and location in a formation with highly desirable attributes (stability, exchange capacity, etc.) that may not be available in every nation with a nuclear energy program. Even if the scientific feasibility were proven, then there still remain enormous institutional obstacles to be overcome including the determined opposition of many countries on ecological and philosophical grounds, the existence of international treaties that appear to prohibit such disposal and the fact that it is not the first choice for disposal of spent nuclear fuel or high level radioactive waste. (orig./HP)

  5. Radioactive Waste in Perspective

    International Nuclear Information System (INIS)

    2011-01-01

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

  6. Management of radioactive waste

    International Nuclear Information System (INIS)

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

    1998-09-01

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

  7. Aespoe Hard Rock Laboratory. Overview of the investigations 1986-1990

    International Nuclear Information System (INIS)

    Stanfors, R.; Erlstroem, M.; Markstroem, I.

    1991-06-01

    In order to prepare for the siting and licensing of a spent fuel repository SKB has decided to construct a new underground research laboratory. The pre-investigations for the Aespoe Hard Rock Laboratory started in late 1986. This report gives a comprehensive compilation of the different investigations performed during the pre-investigation phase (1986-1990). The information is mainly compiled in CAD-generated maps and illustrations in which the reader can gather information concerning the scope of work as well as references to more detailed reports for further study. (au)

  8. Effectiveness of interim remedial actions at a radioactive waste facility

    International Nuclear Information System (INIS)

    Devgun, J.S.; Beskid, N.J.; Peterson, J.M.; Seay, W.M.; McNamee, E.

    1989-01-01

    Over the past eight years, several interim remedial actions have been taken at the Niagara Falls Storage Site (NFSS), primarily to reduce radon and gamma radiation exposures and to consolidate radioactive waste into a waste containment facility. Interim remedial actions have included capping of vents, sealing of pipes, relocation of the perimeter fence (to limit radon risk), transfer and consolidation of waste, upgrading of storage buildings, construction of a clay cutoff wall (to limit the potential groundwater transport of contaminants), treatment and release of contaminated water, interim use of a synthetic liner, and emplacement of an interim clay cap. An interim waste containment facility was completed in 1986. 6 refs., 3 figs

  9. Immersed radioactive wastes

    International Nuclear Information System (INIS)

    2017-03-01

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

  10. Environmental monitoring report for commercial low-level radioactive waste disposal sites (1960`s through 1990`s)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-11-01

    During the time period covered in this report (1960`s through early 1990`s), six commercial low-level radioactive waste (LLRW) disposal facilities have been operated in the US. This report provides environmental monitoring data collected at each site. The report summarizes: (1) each site`s general design, (2) each site`s inventory, (3) the environmental monitoring program for each site and the data obtained as the program has evolved, and (4) what the program has indicated about releases to off-site areas, if any, including a statement of the actual health and safety significance of any release. A summary with conclusions is provided at the end of each site`s chapter. The six commercial LLRW disposal sites discussed are located near: Sheffield, Illinois; Maxey Flats, Kentucky; Beatty, Nevada; West Valley, New York; Barnwell, South Carolina; Richland, Washington.

  11. 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

  12. Management of Radioactive Wastes

    International Nuclear Information System (INIS)

    Tchokosa, P.

    2010-01-01

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

  13. Radioactive waste management

    International Nuclear Information System (INIS)

    1992-01-01

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

  14. Integrated data base for 1986: spent fuel and radioactive waste inventories, projections, and characteristics. Revision 2

    International Nuclear Information System (INIS)

    1986-09-01

    The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US Department of Energy (DOE) radioactive wastes through December 31, 1985, based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. Current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the expected defense-related and private industrial and institutional activities and the latest DOE/Energy Information Administration (EIA) projections of US commercial nuclear power growth. The materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, remedial action waste, and decommissioning waste. For each category, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or calculated isotopic compositions

  15. Dynamics of radioactive waste generation

    International Nuclear Information System (INIS)

    Dogaru, Daniela; Virtopeanu, Cornelia; Ivan, Alexandrina

    2008-01-01

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

  16. Controlling radioactive waste

    International Nuclear Information System (INIS)

    Wurtinger, W.

    1992-01-01

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

  17. Aspects of radioactive waste management

    International Nuclear Information System (INIS)

    Cutoiu, Dan

    2003-01-01

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

  18. Chernobyl radioactivity in grain produced in Greece in 1986

    International Nuclear Information System (INIS)

    Dominici, G.; Malvicini, A.; Panetsos, F.

    1988-01-01

    The Chernobyl radioactive cloud reached Greece in the first days of May 1986. During this period, the gain was in maximum growth; therefore, in absorbing the radionuclides it has become an excellent indicator of the deposited radioactivity. Measurements carried out in grain samples which were obtained from Greece are reported and some conclusions regarding population doses are presented

  19. Transport of radioactive wastes

    International Nuclear Information System (INIS)

    Stuller, C.

    2003-01-01

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

  20. 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

  1. Expediting the commercial disposal option: Low-level radioactive waste shipments from the Mound Plant

    Energy Technology Data Exchange (ETDEWEB)

    Rice, S.; Rothman, R.

    1995-12-31

    In April, Envirocare of Utah, Inc., successfully commenced operation of its mixed waste treatment operation. A mixed waste which was (a) radioactive, (b) listed as a hazardous waste under the Resource Conservation and Recovery Act (RCRA), and (c) prohibited from land disposal was treated using Envirocare`s full-scale Mixed Waste Treatment Facility. The treatment system involved application of chemical fixation/stabilization technologies to reduce the leachability of the waste to meet applicable concentration-based RCRA treatment standards. In 1988, Envirocare became the first licensed facility for the disposal of naturally occurring radioactive material. In 1990, Envirocare received a RCRA Part B permit for commercial mixed waste storage and disposal. In 1994, Envirocare was awarded a contract for the disposal of DOE mixed wastes. Envirocare`s RCRA Part B permit allows for the receipt, storage, treatment, and disposal of mixed wastes that do not meet the land-disposal treatment standards of 40 CFR (Code of Federal Regulations) 268. Envirocare has successfully received, managed, and disposed of naturally occurring radioactive material, low-activity radioactive waste, and mixed waste from government and private generators.

  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. 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.

  4. Environmental radioactivity measurement. Ispra 1990

    International Nuclear Information System (INIS)

    Dominici, G.; Risposi, L.

    1992-01-01

    In this report there are briefly described the measurements of environmental radioactivity performed during 1990 by the site survey group of the Radioprotection Division at the Joint Research Centre Ispra Establishment. Data are give on the concentrations of Sr-90, Cs-137, HTO and other radionuclides in precipitation, air, waters, herbage, milk and radioactive effluents. The environmental contamination is mainly a consequence of the nuclear accident of Chernobyl

  5. Mortaliteten hos multitraumatiserede trafiktilskadekomne. Deskriptiv undersøgelse 1986-1990

    DEFF Research Database (Denmark)

    Larsen, M S; Jørgensen, H R

    1995-01-01

    In the period 1986-1990, 16,307 patients were injured in road traffic accidents in the city of Odense, Denmark. 251 had multiple injuries according to the definition: AIS > or = 3 in at least two body regions. Overall mortality was 41%, while the mortality in hospital was 20%. 19 patients died...

  6. Radioactive wastes and discharges

    International Nuclear Information System (INIS)

    1993-01-01

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

  7. Records of wells and chemical analyses of water from wells for the period June 13, 1984 to December 4, 1986 at the Maxey Flats Radioactive Waste Disposal Site, Kentucky

    Science.gov (United States)

    Lyverse, M.A.

    1987-01-01

    Lithologic data are presented for 113 wells drilled at the Maxey Flats Radioactive Waste Disposal Site for the period June 13, 1984 to December 4, 1986. Water levels, tritium concentrations, and specific conductance are also presented for wells yielding sufficient water for measuring and sampling. At least one sample was collected from most wells for the determination of gross alpha and beta activity. These activities and the results for gamma emitting radionuclides (Cobalt 60 and Cesium 137) are also presented. (USGS)

  8. Management of radioactive wastes

    International Nuclear Information System (INIS)

    Hendee, W.R.

    1984-01-01

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

  9. Radioactive waste disposal

    International Nuclear Information System (INIS)

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

    1981-01-01

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

  10. Managing commercial high-level radioactive waste: summary

    International Nuclear Information System (INIS)

    1982-04-01

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

  11. Evaluation of low and intermediate level radioactive solidified waste forms and packages

    International Nuclear Information System (INIS)

    1990-10-01

    Evaluation of low and intermediate level radioactive waste forms and packages with respect to compliance with quality and safety requirements for transport, interim storage and disposal has become a very important part of the radioactive waste management strategy in many countries. The evaluation of waste forms and packages provides precise basic data for regulatory bodies to establish safety requirements, and implement quality control and quality assurance procedures for radioactive waste management programmes. The requirements depend very much upon the disposal option selected, treatment technology used, waste form characteristics, package quality and other factors. The regulatory requirements can also influence the methodology of waste form/package evaluation together with selection and analysis of data for quality control and safety assurance. A coordinated research programme started at the end of 1985 and brought together 12 participants from 11 countries. The results of the programme and each particular project were discussed at three Research Coordination Meetings held in Cairo, Egypt, in May, 1986; in Beijing, China, in April, 1998; and at Harwell Laboratory, United Kingdom, in November, 1989. This document summarises the salient features and results achieved during the four year investigation and a recommendation for future work in this area. Refs, figs and tabs

  12. Radioactive wastes and discharges

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

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

  13. Radioactive wastes and discharges

    International Nuclear Information System (INIS)

    2000-01-01

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

  14. Your radioactive garden

    International Nuclear Information System (INIS)

    Marshall, W.G.

    1986-01-01

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

  15. International trends of radioactive waste management

    International Nuclear Information System (INIS)

    Luo Shanggeng

    1989-01-01

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

  16. Radioactive waste management

    International Nuclear Information System (INIS)

    2003-01-01

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

  17. Objectives for radioactive waste packaging

    International Nuclear Information System (INIS)

    Flowers, R.H.

    1982-04-01

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

  18. Radioactive Wastes. Revised.

    Science.gov (United States)

    Fox, Charles H.

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

  19. Radioactive Waste Management Strategy

    International Nuclear Information System (INIS)

    2002-01-01

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

  20. Experimentation of nuclear weapons, releases and storages of radioactive wastes in the Kara sea and in New Zemble

    International Nuclear Information System (INIS)

    Charmasson, S.

    1996-01-01

    132 nuclear weapons were tested from 1955 to 1990 in New Zemble. From 1959 to 1993, low level liquid radioactive wastes, low and medium level solid radioactive wastes, reactor core and fuel of submarine and nuclear propelled ships were released in the Kara and the Barentz seas. For these two seas, a recapitulation of the different radioactive sources and the found level of radioactivity of the marine environment are presented. (A.B.). 22 refs. 4 figs., 6 tabs

  1. Royal Decree-Law 1302/1986 of 28 June 1986 on environmental impact studies

    International Nuclear Information System (INIS)

    1986-01-01

    This Royal Decree-Law (No 1302/1986) of 28th June 1986 was published in the Official Gazette of 30th June 1986. The purpose of this Decree-Law is to provide for assessments of the environmental impact of certain projected installations and activities. The installations and activities requiring environmental impact studies are listed in the Annex to the Decree-Law and include nuclear power plants and other nuclear reactors (excluding those whose thermal power does not exceed 1 kW) as well as installations for the disposal and final storage of radioactive waste (NEA) [fr

  2. 1994 state-by-state assessment of low-level radioactive wastes received at commercial disposal sites

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    Each year the National Low-Level Waste Management Program publishes a state-by-state assessment report. This report provides both national and state-specific disposal data on low-level radioactive waste commercially disposed in the United States. Data in this report are categorized according to disposal site, generator category, waste class, volumes, and radionuclide activity. Included in this report are tables showing the distribution of waste by state for 1994 and a comparison of waste volumes and radioactivity by state for 1990 through 1994; also included is a list of all commercial nuclear power reactors in the United States as of December 31, 1994. This report distinguishes between low-level radioactive waste shipped directly for disposal by generators and waste that was handled by an intermediary, a reporting change introduced in the 1988 state-by-state report.

  3. Technical and socio-political issues in radioactive waste disposal 1986. Vol. 1

    International Nuclear Information System (INIS)

    Parker, F.L.; Kasperson, R.E.; Andersson, T.L.; Parker, S.A.

    1987-11-01

    The purpose of the study was to provide an integrated technical and socio-political analysis of how six countries (Federal Republic of Germany, France, Sweden, Switzerland, United Kingdom and the United States of America) have responded to four key issues in radioactive waste management: a) What constitutes 'safe' or 'absolutely safe' disposal, b) site selection processes, c) timing and type of interim storage. (orig./HP)

  4. Radioactive Waste Management and Environmental Contamination Issues at the Chernobyl Site

    International Nuclear Information System (INIS)

    Napier, Bruce A.; Schmieman, Eric A.; Voitsekhovitch, Oleg V.

    2007-01-01

    The destruction of the Unit 4 reactor at the Chernobyl Nuclear Power Plant resulted in the generation of radioactive contamination and radioactive waste at the site and in the surrounding area (referred to as the Exclusion Zone). In the course of remediation activities, large volumes of radioactive waste were generated and placed in temporary near surface waste-storage and disposal facilities. Trench and landfill type facilities were created from 1986 to 1987 in the Chernobyl Exclusion Zone at distances 0.5 to 15 km from the NPP site. This large number of facilities was established without proper design documentation, engineered barriers, or hydrogeological investigations and they do not meet contemporary waste-safety requirements. Immediately following the accident, a Shelter was constructed over the destroyed reactor; in addition to uncertainties in stability at the time of its construction, structural elements of the Shelter have degraded as a result of corrosion. The main potential hazard of the Shelter is a possible collapse of its top structures and release of radioactive dust into the environment. A New Safe Confinement (NSC) with a 100-years service life is planned to be built as a cover over the existing Shelter as a longer-term solution. The construction of the NSC will enable the dismantlement of the current Shelter, removal of highly radioactive, fuel-containing materials from Unit 4, and eventual decommissioning of the damaged reactor. More radioactive waste will be generated during NSC construction, possible Shelter dismantling, removal of fuel containing materials, and decommissioning of Unit 4. The future development of the Exclusion Zone depends on the future strategy for converting Unit 4 into an ecologically safe system, i.e., the development of the NSC, the dismantlement of the current Shelter, removal of fuel containing material, and eventual decommissioning of the accident site. To date, a broadly accepted strategy for radioactive waste

  5. Radioactive waste management and environmental contamination issues at the Chernobyl site.

    Science.gov (United States)

    Napier, B A; Schmieman, E A; Voitsekovitch, O

    2007-11-01

    The destruction of the Unit 4 reactor at the Chernobyl Nuclear Power Plant resulted in the generation of radioactive contamination and radioactive waste at the site and in the surrounding area (referred to as the Exclusion Zone). In the course of remediation activities, large volumes of radioactive waste were generated and placed in temporary near-surface waste storage and disposal facilities. Trench and landfill type facilities were created from 1986-1987 in the Chernobyl Exclusion Zone at distances 0.5-15 km from the nuclear power plant site. This large number of facilities was established without proper design documentation, engineered barriers, or hydrogeological investigations and they do not meet contemporary waste-safety requirements. Immediately following the accident, a Shelter was constructed over the destroyed reactor; in addition to uncertainties in stability at the time of its construction, structural elements of the Shelter have degraded as a result of corrosion. The main potential hazard of the Shelter is a possible collapse of its top structures and release of radioactive dust into the environment. A New Safe Confinement (NSC) with a 100 y service life is planned to be built as a cover over the existing Shelter as a longer-term solution. The construction of the NSC will enable the dismantlement of the current Shelter, removal of highly radioactive, fuel-containing materials from Unit 4, and eventual decommissioning of the damaged reactor. More radioactive waste will be generated during NSC construction, possible Shelter dismantling, removal of fuel-containing materials, and decommissioning of Unit 4. The future development of the Exclusion Zone depends on the future strategy for converting Unit 4 into an ecologically safe system, i.e., the development of the NSC, the dismantlement of the current Shelter, removal of fuel-containing material, and eventual decommissioning of the accident site. To date, a broadly accepted strategy for radioactive waste

  6. Radioactive liquid waste filtering device

    International Nuclear Information System (INIS)

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

    1988-01-01

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

  7. Radioactive Waste Repositories Administration - SURAO

    International Nuclear Information System (INIS)

    Kucerka, M.

    1998-01-01

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

  8. Radioactive Waste Management in the USSR: A review of unclassified sources, 1963-1990

    International Nuclear Information System (INIS)

    Bradley, D.J.; Schneider, K.J.

    1990-03-01

    The Soviet Union operates a vast and growing radioactive waste management system. Detailed information on this system is rare and a general overall picture only emerges after a review of a great deal of literature. Little is known about Soviet waste management practices related to uranium mining, conversion, and fuel fabrication processes. However, releases of radioactive material to the environment from uranium mining and milling operations are causing public concern. Official Soviet policy calls for a closed fuel cycle, with reprocessing of power reactor fuel that has been cooled for five years. Information on reprocessing in the Soviet Union has been severely limited until 1989, when two reprocessing sites were acknowledge by the Soviets. The Soviets have announced that their high-level waste management plan is to (1) store liquid wastes for 3--5 years; (2) incorporate the waste into glass (at a final glass volume of 100--500 liters/MT of fuel reprocessed); (3) set it aside in air-cooled storage for 30--50 years; and (4) provide for its final disposal in a deep geologic repository. Millions of cures of liquid low- and intermediate-level wastes have been disposed of by well injection where they were supposedly contained by watertight rock strata. Some gaseous wastes were also disposed of by well injection. This practice is not referred to in recent literature and thus may not be widely used today. Deep geologic disposal of vitrified high-level waste has been studied over the last decade in the Soviet Union. Key disposal concepts include mining shafts, deep drill holes, and underground excavations. 209 refs., 4 figs., 7 tabs

  9. Management responsible for the radioactive waste in the University of Costa Rica

    International Nuclear Information System (INIS)

    Mora, P.; Varela, A.

    2003-01-01

    Through the University Plan de Seguridad Radiologica (PSR), established in 1990, radioactive wastes generated by the University of Costa Rica (UCR) personnel are handled. They are properly collected, stroraged and disposed. The waste room is used by the following centers: Laboratorio de Fisica Nuclear Aplicada, Instituto de Investigaciones en Salud, Centro de Biologia Celular y Molecular and Centro de Investigaciones en Contaminacion Ambiental. The PSR has prestorage procedures, internal controls inside the waste room, protocols for storage, withdraw of sources, and discharges to the environment according to national and international legislation. The main radioactive wastes in liquid or solid forms contain p 32 , I 125 , S 35 y C 14 that eventually be disposed as excempted materials. The waste room stores sources with the following radionuclides Cs 137 , U 238 , Th 232 , Sr 90 , Ra 226 , Cd 109 , Cf 252 and Am 241 . It has 96 permanent sources and 52 that will be disposed. The PSR allows the University to have a centralized facility for the safe management of all radioactive waste generated locally. (Author) [es

  10. Perspectives concerning radioactive waste management

    International Nuclear Information System (INIS)

    Noynaert, L.

    2013-01-01

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

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

    International Nuclear Information System (INIS)

    1984-01-01

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

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

    International Nuclear Information System (INIS)

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

    1991-07-01

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

  13. Radioactive mixed waste disposal

    International Nuclear Information System (INIS)

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

    1993-02-01

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

  14. Radioactive waste management

    International Nuclear Information System (INIS)

    1984-07-01

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

  15. Radioactive waste (disposal)

    International Nuclear Information System (INIS)

    Jenkin, P.

    1985-01-01

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

  16. Radioactive wastes

    International Nuclear Information System (INIS)

    Dupuis, M.C.

    2007-01-01

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

  17. What to do with radioactive wastes?

    International Nuclear Information System (INIS)

    2006-01-01

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

  18. The disposal of radioactive waste

    International Nuclear Information System (INIS)

    Ormai, P.

    2006-01-01

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

  19. Radioactive waste processing

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  20. Radioactive Waste Management BasisApril 2006

    Energy Technology Data Exchange (ETDEWEB)

    Perkins, B K

    2011-08-31

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

  1. Radioactive waste management and regulation

    International Nuclear Information System (INIS)

    Willrich, M.

    1976-12-01

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

  2. Radioactive waste management

    International Nuclear Information System (INIS)

    Morley, F.

    1980-01-01

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

  3. Predisposal Radioactive Waste Management

    International Nuclear Information System (INIS)

    2014-01-01

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

  4. Management of radioactive waste: A review

    OpenAIRE

    Luis Paulo Sant'ana; Taynara Cristina Cordeiro

    2016-01-01

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

  5. Method of storing radioactive wastes

    International Nuclear Information System (INIS)

    Adachi, Toshio; Hiratake, Susumu.

    1980-01-01

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

  6. 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

  7. Summary of expenditures of rebates from the low-level radioactive waste surcharge escrow account for calendar year 1988

    International Nuclear Information System (INIS)

    1989-06-01

    This is the third report submitted to Congress under Public Law 99-240, ''The Low-Level Radioactive Waste Policy Amendments Act of 1985'' (the Act). This section of the Act requires the Department of Energy to summarize the annual expenditures made by states and compacts of funds disbursed from the Department's Surcharge Escrow Account, and to assess the compliance of these expenditures with the specified limitations. This report covers expenditures made during calendar year 1988 from funds disbursed to states and compacts following the July 1, 1986, and January 1, 1988, milestones. The next milestone in the Act is January 1, 1990, following which the accumulated surcharge deposits in the Department's Surcharge Escrow Account will again be disbursed. The Act authorizes states with operating low-level radioactive waste disposal sites (sited states) to collect surcharges on disposal of waste from generators located in compact regions currently without disposal sites (non-sited compacts) and in states that do not have sites and that are not members of compacts (nonmember states). The Act requires the sited states to make a monthly deposit to the Department of Energy's Surcharge Escrow Account of 25 percent of the surcharges they collect. Following each milestone date, the Department is required to disburse these funds, with accrued interest, back to those non-sited compacts and nonmember states found in compliance with the milestone requirements for new disposal site development. 4 tabs

  8. The Community's research and development programme on radioactive waste management and storage

    International Nuclear Information System (INIS)

    Orlowski, S.; Gandolfo, J.M.

    1988-01-01

    This is the first annual progress report of the European Community's 1985-89 programme of research on radioactive waste management and disposal, carried out by public organizations and private firms in the Community under cost-sharing contracts with the Commission of the European Communities. The 1985-89 programme is aiming at perfecting and demonstrating a system for managing the radioactive waste produced by the nuclear industry, ensuring at the various stages the best possible protection of man and the environment. This first report describes the work to be carried out under the research contracts already concluded before end of 1986 as well as the initial work performed and the first results obtained. For each contract, paragraph C ''Progress of work and obtained results'' was prepared by the contractor under the responsibility of the project leader

  9. Artificial radioactivity in the environmental samples as IAEA reference materials

    International Nuclear Information System (INIS)

    Salagean, M.; Pantelica, A.

    1998-01-01

    . Uncontaminated by nuclear activities: IAEA-327, Podsolic soil collected in 1990 from the Moscow region and considered uncontaminated by radionuclides of the Chernobyl accident or by other nuclear activities. The results obtained by our laboratory are in good agreement with the certified IAEA data. Generally, the concentration of the artificial radionuclides in the investigated samples is higher than that expected from the influence of global fallout in the intercomparison materials distributed before Chernobyl accident. Concerning the nature of these investigated IAEA reference materials, very high values for the concentration levels of cesium radionuclides especially in IAEA-373 (grass) and IAEA-375 (soil) samples collected in the vicinity of Chernobyl Power Station after the nuclear accident in 1986 were found. High levels of radioactivities for the artificial radionuclides were also determined in the samples collected in the neighbourhood of the nuclear installations, especially in marine sediment (IAEA-135). It is of interest to point out the high concentration of cesium radionuclides in IAEA-300 sediment collected in 1992 in the Baltic Sea in comparison with the IAEA-306 sediment collected also in the Baltic Sea in 1986. It seems to be an increase of the Baltic Sea artificial radioactivity by accumulation in time. Marine sediment constitutes an important component of marine ecosystem since it represents the final sink for any releases of wastes into the sea. These certified radioactive materials are very useful to all laboratories engaged in the radioactive pollution investigations on environmental samples. (authors)

  10. Method for calcining radioactive wastes

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  11. Evolution in radioactive waste countermeasures

    International Nuclear Information System (INIS)

    Moriguchi, Yasutaka

    1984-01-01

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

  12. ORNL radioactive waste operations

    International Nuclear Information System (INIS)

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

    1982-01-01

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

  13. Management of hospital radioactive wastes

    International Nuclear Information System (INIS)

    Mantrana, D.

    1986-01-01

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

  14. Radioactive Waste.

    Science.gov (United States)

    Blaylock, B. G.

    1978-01-01

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

  15. 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

  16. Radioactive Waste Management Fellowship Program: Summary of program activities for calendar year 1986

    International Nuclear Information System (INIS)

    1987-01-01

    This document describes a graduate fellowship program designed to guide future scientists and engineers toward a career in high level radioactive waste management. Oak Ridge Associated Universities administers this program on behalf of 17 participating universities. The report summarizes the background and qualifications of the last year's applicants and awardees and provides examples of the distributed literature describing the program. 8 figs

  17. Handling of radioactive waste

    International Nuclear Information System (INIS)

    Sanhueza Mir, Azucena

    1998-01-01

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

  18. Fusion reactor radioactive waste management

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  19. radioactive waste disposal standards abroad

    International Nuclear Information System (INIS)

    Lu Yan; Xin Pingping; Wu Jian; Zhang Xue

    2012-01-01

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

  20. Disposal facility for radioactive wastes

    International Nuclear Information System (INIS)

    Utsunomiya, Toru.

    1985-01-01

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

  1. Integrated Data Base for 1991: US spent fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    1991-10-01

    The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1990. These data are based on the most reliable information available form government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated generally through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 160 refs., 61 figs., 142 tabs

  2. Radioactive Waste Management BasisSept 2001

    International Nuclear Information System (INIS)

    Goodwin, S.S.

    2011-01-01

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

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

    International Nuclear Information System (INIS)

    Morais, Carlos Antonio de

    1996-01-01

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

  4. Radioactive waste: show time? - 16309

    International Nuclear Information System (INIS)

    Codee, Hans; Verhoef, Ewoud

    2009-01-01

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

  5. Rokkasho low-level radioactive waste disposal in Japan

    International Nuclear Information System (INIS)

    Takahashi, Y.

    1994-01-01

    Japan Nuclear Fuel Limited commenced the operation of the shallow land disposal of low-level radioactive waste from reactor operation, in 1992 at Rokkasho site in Aomori Prefecture. JNFL is private company whose main activities within the responsibility of JNFL are: 1) Disposal of low-level radioactive waste, 2) Uranium enrichment, 3) Reprocessing of spent nuclear fuels, 4) Temporary storage of returned wastes from COGEMA and BNFL by reprocessing contracts, prior to disposal. JNFL selected the site for the disposal of LLW at Rokkasho in Aomori Prefecture, then bought land of 3.4 million m 2 . Among waste spectrum, LLWs from nuclear power plants, from uranium enrichment and from reprocessing are to be managed by JNFL, including dismantling of these facilities, and JNFL has plan to dispose about 600 thousand m 3 of wastes ultimately. On the middle of November 1990 JNFL got the permission of the application for 40 thousand m 3 (equivalent to 200,000 drums each with a 200-liter capacity) of reactor operating wastes which is solidified with cement, bitumen or plastics as a first stage. And after the construction work for about 2 years, the operations started at Dec. 8th, 1992. The Disposal center has already accepted about 24,000 LLW drums as of the end of February, 1994. (author)

  6. HMIP monitoring programme: radioactive substances report for 1990

    International Nuclear Information System (INIS)

    1992-03-01

    Discharges of radioactive wastes to the environment can only be made under authorisation from government bodies. The main potential sources of environmental contamination in England are nuclear sites (power stations, fuel fabrication and reprocessing plants), some industrial premises such as metal smelters, and landfill sites. As well as the environmental monitoring programmes undertaken by the operators of such sites various government bodies also undertake monitoring. In January 1988 Her Majesty's Inspectorate of Pollution (HMIP) initiated a programme to monitor exposure of the public from non-food pathways such as could occur from occupation of beaches, river banks etc. Radiation levels and radiochemical and gamma spectra of samples collected at specified locations near nuclear sites and industrial premises have been monitored every quarter since then. The results for 1990 are presented and discussed. (UK)

  7. Radioactive wastes - inventories and classification

    International Nuclear Information System (INIS)

    Brennecke, P.; Hollmann, A.

    1992-01-01

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

  8. Technological and organizational aspects of radioactive waste management

    International Nuclear Information System (INIS)

    2005-01-01

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

  9. National profile on commercially generated low-level radioactive mixed waste

    Energy Technology Data Exchange (ETDEWEB)

    Klein, J.A.; Mrochek, J.E.; Jolley, R.L.; Osborne-Lee, I.W.; Francis, A.A.; Wright, T. [Oak Ridge National Lab., TN (United States)

    1992-12-01

    This report details the findings and conclusions drawn from a survey undertaken as part of a joint US Nuclear Regulatory Commission and US Environmental Protection Agency-sponsored project entitled ``National Profile on Commercially Generated Low-Level Radioactive Mixed Waste.`` The overall objective of the work was to compile a national profile on the volumes, characteristics, and treatability of commercially generated low-level mixed waste for 1990 by five major facility categories-academic, industrial, medical, and NRC-/Agreement State-licensed goverment facilities and nuclear utilities. Included in this report are descriptions of the methodology used to collect and collate the data, the procedures used to estimate the mixed waste generation rate for commercial facilities in the United States in 1990, and the identification of available treatment technologies to meet applicable EPA treatment standards (40 CFR Part 268) and, if possible, to render the hazardous component of specific mixed waste streams nonhazardous. The report also contains information on existing and potential commercial waste treatment facilities that may provide treatment for specific waste streams identified in the national survey. The report does not include any aspect of the Department of Energy`s (DOES) management of mixed waste and generally does not address wastes from remedial action activities.

  10. National profile on commercially generated low-level radioactive mixed waste

    International Nuclear Information System (INIS)

    Klein, J.A.; Mrochek, J.E.; Jolley, R.L.; Osborne-Lee, I.W.; Francis, A.A.; Wright, T.

    1992-12-01

    This report details the findings and conclusions drawn from a survey undertaken as part of a joint US Nuclear Regulatory Commission and US Environmental Protection Agency-sponsored project entitled ''National Profile on Commercially Generated Low-Level Radioactive Mixed Waste.'' The overall objective of the work was to compile a national profile on the volumes, characteristics, and treatability of commercially generated low-level mixed waste for 1990 by five major facility categories-academic, industrial, medical, and NRC-/Agreement State-licensed goverment facilities and nuclear utilities. Included in this report are descriptions of the methodology used to collect and collate the data, the procedures used to estimate the mixed waste generation rate for commercial facilities in the United States in 1990, and the identification of available treatment technologies to meet applicable EPA treatment standards (40 CFR Part 268) and, if possible, to render the hazardous component of specific mixed waste streams nonhazardous. The report also contains information on existing and potential commercial waste treatment facilities that may provide treatment for specific waste streams identified in the national survey. The report does not include any aspect of the Department of Energy's (DOES) management of mixed waste and generally does not address wastes from remedial action activities

  11. Solid and liquid radioactive wastes

    International Nuclear Information System (INIS)

    Cluchet, J.; Desroches, J.

    1977-01-01

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

  12. Overview of commercial low-level radioactive waste disposal in the United States

    International Nuclear Information System (INIS)

    Smith, P.

    1994-01-01

    Disposal of commercial low-level radioactive waste (LLW) is a critical part of the national infrastructure needed to maintain the health of American businesses, universities, and hospitals. Currently only 19 States (located in the Northwest and Southeast) have access to operating disposal facilities; all other States are storing their LLW until they open new disposal facilities on their own or in concert with other States through regional compact agreements. In response to recommendations from the National Governors Association, Congress assigned the burden for LLW disposal to all States, first in 1980 through Public Law 96-573, the open-quotes Low-level Radioactive Waste Policy Actclose quotes, and again in 1986 through Public Law 99-240, the open-quotes Low-Level Radioactive Waste Policy Amendments Act of 1985close quotes. As directed by Congress, the Department of Energy provides technical assistance to States and compact regions with this task. After almost 14 years, nine compact regions have been ratified by Congress; California, Texas, North Carolina, and Nebraska have submitted license applications; California has issued an operating license; and the number of operating disposal facilities has decreased from three to two

  13. Radioactive wastes in Oklo

    International Nuclear Information System (INIS)

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

    2006-01-01

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

  14. Treatment and conditioning of historical radioactive waste

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  15. Radioactivity of people in Finland after the Chernobyl accident in 1986

    International Nuclear Information System (INIS)

    Rahola, T.; Suomela, M.; Illukka, E.; Puhakainen, M.; Pusa, S.

    1987-06-01

    After the reactor accident at Chernobyl on April 26, 1986 radioactive fallout was carried by air currents to most parts of Europe. The radioactive air currents reached Finland on April 27. Immediately after the arrival of such air in Finland, contamination of people by radioactive nuclides began via inhalation of this air. The ingestion route become important later, when radionuclides were transported via different foodchains to man. To determine the level of radionuclides in the body and to estimate the internal radiation doses caused by the Chernobyl accident, whole-body counting measurements were performed. The results of whole-body counting of six different groups of Finnish people measured during 1986 after the accident at Chernobyl are reported. Three were reference groups measured routinely once or twice annually, two groups were comprised of workers at nuclear power stations and one group consisted of 262 persons not belonging to any other group. The total number of whole-body counting measurements of persons in these groups in 1986 from the end of April to the end of December was 624. In April and May small amounts of 131 I were detected in the thyroid. In June the first signs of 134 Cs in the body were noticed. At the end of 1986 the mean 134 Cs body burden for women and men in the Helsinki reference group was 730 Bq. The mean 137 Cs body burden in women and men increased from 150 Bq in June to 1500 Bq in December. The differences in the deposition levels in the five fallout regions into which Finland was divided were reflected in the activity levels of the measured people. The weighted annual mean body burden for people in Finland at the end of 1986 was 370 Bq 134 Cs and 820 Bq 137 Cs. The maximum body burdens of 134 Cs and 137 Cs found in Finns in 1986 were 6300 Bq and 13000 Bq, respectively. The mean internal committed effective dose equivalent 0.06 mSv from 134 Cs and 137 Cs in the body of Finnish people in 1986 was calculated using the whole

  16. Thermal treatment of organic radioactive waste

    International Nuclear Information System (INIS)

    Chrubasik, A.; Stich, W.

    1993-01-01

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

  17. Management situation and prospect of radioactive waste

    International Nuclear Information System (INIS)

    Han, Pil Jun

    1985-04-01

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

  18. Measurements of radioactive and xenobiotic substances in the biological environment in the Netherlands 1986

    International Nuclear Information System (INIS)

    1988-01-01

    A brief survey of the results of detailed radioactivity measurements performed in the Netherlands during the period immediately after the Chernobylsk accident, and the risk analyses made on the basis of these results, are presented. The increase of the airborne radioactivity and the activity concentrations in surface water during the first week of May 1986 is demonstrated graphically. The radiation dose in 1986 due to artificial radioactivity has been calculated to be about 60 μSv for adults, 70 μSv for ten-year-old children and 110 μSv for one-year-old children. 54 figs.; 32 tabs

  19. Radioactive waste management policy

    International Nuclear Information System (INIS)

    Morrison, R.W.

    1983-06-01

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

  20. Central interstate low-level radioactive waste compact region site exclusionary screening study. Phase I. Final report

    International Nuclear Information System (INIS)

    1985-06-01

    The Low-Level Radioactive Waste Policy Act of 1980 assigns to the states the responsibility for disposal of the low-level radioactive waste generated within their boundaries. It also provides for regional compacts among states to address their needs on a broader basis and permits restriction of the use of regional disposal facilities after January 1, 1986, to generators of low-level waste within the region. Each state, either individually or as a member of a compact, must therefore consider the establishment of a low-level radioactive waste disposal facility within its borders. The states of Arkansas, Kansas, Louisiana, Nebraska, and Oklahoma adopted the Central Interstate Low-Level Waste Compact (CILLWC) and legislation was submitted to Congress for consent in June of 1983 legislation is being reintroduced in the 99th Congress. In August of 1984, the CILLWC selected and contracted Dames and Moore to conduct a Phase I-Site Suitability Screening Study for a low-level radioactive waste disposal facility in the five-state region. This report presents the results of the Phase I Screening Study. Dames and Moore reported to the Technical Advisory Committee (TAC) of the CILLWC which provided guidance and comment on work progress and direction

  1. 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

  2. Disposal of radioactive wastes. Chapter 11

    International Nuclear Information System (INIS)

    Skitt, J.

    1979-01-01

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

  3. Handbook of high-level radioactive waste transportation

    International Nuclear Information System (INIS)

    Sattler, L.R.

    1992-10-01

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

  4. Implications of recent ICRP recommendations for risk assessments for radioactive waste disposal and cleanup

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1992-01-01

    The International Commission on Radiological Protection (ICRP) adopted a new set of recommendations in November 1990 which were issued at ICRP Publication No. 60 in March 1991. These recommendations incorporate new radiobiological information and outline a comprehensive system of radiological protection. This paper evaluates the implications of these new recommendations vis a vis risk assessments for radioactive waste disposal and remediation of radioactively contaminated sites

  5. Radioactive waste management in Mexico

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  6. Radioactive waste problems in Russia

    International Nuclear Information System (INIS)

    Bridges, O.; Bridges, J.W.

    1995-01-01

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

  7. Radioactive waste management from nuclear facilities

    International Nuclear Information System (INIS)

    2005-06-01

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

  8. Classification of radioactive waste

    International Nuclear Information System (INIS)

    1994-01-01

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

  9. Radioactive waste management in Korea

    International Nuclear Information System (INIS)

    Lee, Ik Hwan

    1997-01-01

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

  10. Treatment of radioactive waste in the Federal Republic of Germany

    Energy Technology Data Exchange (ETDEWEB)

    Krause, H [Kernforschungszentrum Karlsruhe (F.R. Germany). Abt. Behandlung Radioaktiver Abfaelle

    1976-07-01

    In the Federal Republic of Germany a nuclear generating capacity of approximately 65 GWe is anticipated by 1990 which, together with the fuel cycle industry and a reprocessing plant, will produce approximately 18,000 m/sup 3/ of preconcentrated liquids and 16,000 m/sup 3/ of solid waste with a total activity of some 3 x 10/sup 7/ Ci. The contribution to the total amount and activity of waste made by the individual types of waste in various nuclear installations differs widely. Waste from reprocessing plants contains some 99.9% of the radionuclides contained in liquid waste and 86% of those contained in solid waste. Waste from the rest of the fuel cycle, the nuclear power stations and the large research centers together contains only some 0.01% of the total activity of the solid waste. In terms of volume, most of the radioactive waste is low level waste.

  11. 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)

  12. Nuclear and radiological safety. 1986-1998. International Atomic Energy Agency publications

    International Nuclear Information System (INIS)

    1999-04-01

    This catalogue lists all sales publications of the IAEA dealing with nuclear and radiological safety issued from 1986 to 1998. Publications are sorted according to the following subjects: Uranium mining and milling; Fuel fabrication and storage; Nuclear power plants; Research reactors; Radiation sources and accelerators; Transport of radioactive material; Waste repositories; Radiation protection; Accident response; Radioactive waste management; Safety analysis; Quality management; Legal and governmental aspects

  13. Radioactive waste management - the Indian scenario

    International Nuclear Information System (INIS)

    Raj, Kanwar

    2008-01-01

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

  14. Solidification method of radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

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

    1992-07-24

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

  15. Operational experience acquired in radioactive waste compaction

    International Nuclear Information System (INIS)

    Bauer, S.; Mohr, P.; Hempelmann, W.

    1993-01-01

    The low-level radioactive waste scrapping facility in the KfK decontamination division was commissioned in 1983. Non-combustible residues and removed system components of low activity, but which are to be handled and disposed of as radioactive waste are in drums, casks or containers delivered to the facility. The waste usually undergoes pretreatment in a crusher, with the volume being definitively reduced at a pressure of 690 bar in the high-pressure compactor. In 1990, the overhead-crane was refurbished for remote control handling in the scrapping caisson. The parts to undergo scrapping are unpacked in the material lock, and then go into the scrapping caisson. It is possible to use here various mechanical and thermal methods to dismantle the respective parts. But most of the parts to undergo scrapping are such as that it is possible to directly pretreat them in the crusher. The obtained scrap is loaded into 180-liter drums. Most of the machinery in the caisson is manually operated. The operating crew enters the caisson in fully ventilated protective overalls. The drums filled with the scrap then go to the high-pressure compactor in the caisson. The compacts are temporarily stored, until recalled depending on their height and filled into drums such as that optimal drum filling is guaranteed

  16. Regulation on radioactive waste management

    International Nuclear Information System (INIS)

    1999-01-01

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

  17. Method and techniques of radioactive waste treatment

    International Nuclear Information System (INIS)

    Ghafar, M.; Aasi, N.

    2002-04-01

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

  18. Radioactive wastes management development in Chile

    International Nuclear Information System (INIS)

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

    1994-01-01

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

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

    International Nuclear Information System (INIS)

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

    2016-01-01

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

  20. 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

  1. Radioactive waste management in Tanzania

    International Nuclear Information System (INIS)

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

    2002-01-01

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

  2. Radioactivity curves plotted for various foodstuffs after 1986

    International Nuclear Information System (INIS)

    Diehl, J.F.

    1989-01-01

    Investigations were carried out into the daily food rations of adults. They were based on data obtained within the system for the surveillance of environmental radioactivity in the Federal Republic of Germany. It was found that the monthly averages determined after Chernobyl for Cs-134 and Cs-137 reached a maximum in the March of 1987, to decline continuously after that point of time. Vegetable, meat and fish largely reflect this general development, even though game continues to be an exception to the rule. The additional radioactivity from the period between 1986 and 1989 was calculated to account for a dose of approx. 80 μSv in 50 years. (DG) [de

  3. Security of Radioactive Waste

    International Nuclear Information System (INIS)

    Goldammer, W.

    2003-01-01

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

  4. Treatment of Radioactive Gaseous Waste

    International Nuclear Information System (INIS)

    2014-07-01

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

  5. 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)

  6. Development of the safety assessment technology for the radioactive waste disposal

    International Nuclear Information System (INIS)

    Kim, Chang Lak; Choi, Kwang Sub; Cho, Chan Hee; Lee, Myung Chan; Kim, Jhin Wung

    1992-03-01

    The major goal of this project is to develop a source-term model for the safety assessment of a low- and intermediate-level radioactive waste repository as follows: 1) estimation of the arising of low- and intermediate-level radioactive wastes, 2) development of inventory data base, 3) development of a source-term code for shallow-land disposal, and 4) improvement of the REPS source-term code for rock cavern type disposal developed already in 1990 and conservative safety assessment for an imaginary repository. In addition, the source of C-14 in the inventory is assessed by two methods: decontamination factor and scaling factor. The source-term code for shallow-land disposal include the following submodels: surface water penetration into the repository, concrete degradation, corrosion of container drums, leaching of radionuclides from waste forms, and migration of radionuclides from engineered disposal facility is estimated by this code. (Author)

  7. Radioactive waste disposal

    International Nuclear Information System (INIS)

    Petit, J.C.

    1998-04-01

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

  8. Final disposal of radioactive waste

    Directory of Open Access Journals (Sweden)

    Freiesleben H.

    2013-06-01

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

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

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  10. Radioactivity and nuclear waste

    International Nuclear Information System (INIS)

    Saas, A.

    1996-01-01

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

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

    International Nuclear Information System (INIS)

    1984-07-01

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

  12. Disposal method of radioactive wastes

    International Nuclear Information System (INIS)

    Uetake, Naoto; Fukazawa, Tetsuo.

    1986-01-01

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

  13. 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.

  14. 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

  15. Handling and disposing of radioactive waste

    International Nuclear Information System (INIS)

    Trauger, D.B.

    1983-01-01

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

  16. Specified radioactive waste final disposal act

    International Nuclear Information System (INIS)

    Yasui, Masaya

    2001-01-01

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

  17. Centralized interim storage facility for radioactive wastes at Wuerenlingen (ZWILAG)

    International Nuclear Information System (INIS)

    Lutz, H.R.; Schnetzler, U.

    1994-01-01

    Radioactive waste management in Switzerland is the responsibility of the waste producers; in this respect, the law requires permanent, safe management of the wastes by means of final disposal. Nagra is responsible for the research and development work associated with final disposal. Processing of the wastes into a form suitable for disposal, as well as interim storage, remain the responsibility of the waste producers. In order to supplement the existing conditioning and storage facilities at the nuclear power plants and to replace the outdated waste treatment plant at the Paul Scherrer Institute (PSI) at Wuerenlingen, the operators of the Swiss nuclear power plants are planning a joint treatment and storage facility at the PSI-East site. The organisation ''Zwischenlager Wuerenlingen AG'', which was set up at the beginning of 1990, has been entrusted with this task. (author) 4 figs

  18. Management of Radioactive Wastes in Developing Countries

    International Nuclear Information System (INIS)

    Abdel Ghani, A.H.

    1999-01-01

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

  19. Monitoring of radioactive wastes

    International Nuclear Information System (INIS)

    Houriet, J.Ph.

    1982-08-01

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

  20. Geological Disposal of Radioactive Waste

    International Nuclear Information System (INIS)

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

    2014-01-01

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

  1. 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)

  2. The Radioactive Waste Management Advisory Committee's advice to ministers on the problems of 'small users' of radioactive materials

    International Nuclear Information System (INIS)

    2000-09-01

    The Radioactive Waste Management Advisory Committee (RWMAC) is the independent body that advises the UK Government, including the devolved administrations for Scotland and Wales, on issues relating to the management of civil radioactive waste. Radioactive wastes are produced by the civil nuclear industry, by the Ministry of Defence, and by a varied group of organisations known as 'Small Users'. Small Users include hospitals, universities and some non-nuclear industries, which use radioactive materials and, in turn, produce radioactive waste. In 1991, and again in 1996, RWMAC provided the Government with advice on the problems encountered by Small Users. These difficulties were associated both with specific aspects of the radioactive waste management required and with the controls exercised by the regulators. As part of its work programme for 1999-2000, Ministers asked the Committee to return to these issues. In volume, Small User radioactive wastes make up only a small part of the total UK inventory. However, like those produced by the nuclear and defence sectors, it is vital that they are managed properly, as some carry the potential for considerable harm. Equally, it is important that the financial costs imposed on Small Users as a result of regulation are commensurate with the actual health risk involved. Otherwise, for example, the benefits accruing from use of radioactive materials in medicine might be prejudiced. We have tried to strike an appropriate balance in arriving at the views set out in our report. The report draws attention to a number of areas that Government could usefully consider in respect of Small User waste management, possibly as part of its forthcoming radioactive waste management policy review. A key issue is the need to get to grips with the problem of historic redundant radioactive sources held under registration by Small Users. Many such sources are in the public sector and, under current funding arrangements, Small Users encounter

  3. Environmental aspects of commercial radioactive waste management

    International Nuclear Information System (INIS)

    1979-05-01

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

  4. National inventory of radioactive wastes

    International Nuclear Information System (INIS)

    1997-01-01

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

  5. Radioactive wastes

    International Nuclear Information System (INIS)

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

    1994-01-01

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

  6. 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

  7. Supercompaction of radioactive waste at NPP Krsko

    International Nuclear Information System (INIS)

    Fink, K.; Sirola, P.

    1996-01-01

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

  8. Mixed radioactive and chemotoxic wastes (RMW)

    International Nuclear Information System (INIS)

    Dejonghe, I.P.

    1991-01-01

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

  9. Understanding radioactive waste

    International Nuclear Information System (INIS)

    Murray, R.L.

    1989-01-01

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

  10. Radioactive waste material melter apparatus

    Science.gov (United States)

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

    1990-04-24

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

  11. Radioactive waste material melter apparatus

    International Nuclear Information System (INIS)

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

    1990-01-01

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

  12. The transport of radioactive waste

    International Nuclear Information System (INIS)

    Appleton, P.R.; Poulter, D.R.

    1989-01-01

    Regulations have been developed to ensure the safe transport of all radioactive materials by all modes (road, rail, sea and air). There are no features of radioactive waste which set it aside from other radioactive materials for transport, and the same regulations control all radioactive material transport. These regulations and their underlying basis are described in this paper, and their application to waste transport is outlined. (author)

  13. Low-level radioactive biomedical wastes

    International Nuclear Information System (INIS)

    Casarett, G.W.

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

  14. Krsko NPP radioactive waste characteristics

    International Nuclear Information System (INIS)

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

    2007-01-01

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

  15. Radioactive waste management - with evidence

    International Nuclear Information System (INIS)

    1988-01-01

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

  16. Disposal of Radioactive Waste

    International Nuclear Information System (INIS)

    2011-01-01

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

  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. 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)

  19. Management on radioactive wastes

    International Nuclear Information System (INIS)

    Balu, K.; Bhatia, S.C.

    1979-01-01

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

  20. [Microbiological Aspects of Radioactive Waste Storage].

    Science.gov (United States)

    Safonov, A V; Gorbunova, O A; German, K E; Zakharova, E V; Tregubova, V E; Ershov, B G; Nazina, T N

    2015-01-01

    The article gives information about the microorganisms inhabiting in surface storages of solid radioactive waste and deep disposal sites of liquid radioactive waste. It was shown that intensification of microbial processes can lead to significant changes in the chemical composition and physical state of the radioactive waste. It was concluded that the biogeochemical processes can have both a positive effect on the safety of radioactive waste storages (immobilization of RW macrocomponents, a decreased migration ability of radionuclides) and a negative one (biogenic gas production in subterranean formations and destruction of cement matrix).

  1. Management of radioactive wastes in China

    International Nuclear Information System (INIS)

    Pan Ziqiang

    1994-01-01

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

  2. Sponsored research on radioactive waste management

    International Nuclear Information System (INIS)

    1983-01-01

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

  3. Radioactive waste management

    International Nuclear Information System (INIS)

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

    1975-08-01

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

  4. Responsible handling of the radioactive waste at the Universidad de Costa Rica

    International Nuclear Information System (INIS)

    Mora Rodriguez, Patricia; Varela, Alfonso

    2006-01-01

    The Radiation Safety Program (RSP) of the Universidad de Costa Rica established in 1990, handles the radioactive waste generated at the University. A centralized storage waste room is used by the Centro de Investigacion en Ciencias Atomicas, Nucleares y Moleculares, Instituto de Investigacion en Salud, Centro de Investigacion en Biologia Celular y Molecular, and the Centro de Investigacion en Contaminacion Ambiental. The RSP has pre-storage procedures, internal controls, protocols for storage, withdrawal of sources and discharges to the environment, according to national and international legislation. The main radionuclides in liquid and solid wastes are P32, I125, S35 y C14; which after a storage period will be disposed of as exempted materials. The waste room also permanently stores sources with the following radionuclides Cs137, U238, Th232, Sr90, Ra226, Cd109, Cf252 and Am241. It has 96 permanent sources and 52 that will be disposed of. The RSP allows the University to have a centralized facility for the safe management of all radioactive waste generated locally. (Author)

  5. Method of disposing radioactive wastes

    International Nuclear Information System (INIS)

    Isozaki, Kei.

    1983-01-01

    Purpose : To enable safety ocean disposal of radioactive wastes by decreasing the leaching rate of radioactive nucleides, improving the quick-curing nature and increasing the durability. Method : A mixture comprising 2 - 20 parts by weight of alkali metal hydroxide and 100 parts by weight of finely powdered aqueous slags from a blast furnace is added to radioactive wastes to solidify them. In the case of medium or low level radioactive wastes, the solidification agent is added by 200 parts by weight to 100 parts by weight of the wastes and, in the case of high level wastes, the solidification agent is added in such an amount that the wastes occupy about 20% by weight in the total of the wastes and the solidification agent. Sodium hydroxide used as the alkali metal hydroxide is partially replaced with sodium carbonate, a water-reducing agent such as lignin sulfonate is added to improve the fluidity and suppress the leaching rate and the wastes are solidified in a drum can. In this way, corrosions of the vessel can be suppressed by the alkaline nature and the compression strength, heat stability and the like of the product also become excellent. (Sekiya, K.)

  6. 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)

  7. Radioactive waste interim storage in Germany

    International Nuclear Information System (INIS)

    2015-12-01

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

  8. Communication from the Radioactive Waste Service

    CERN Multimedia

    2011-01-01

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

  9. Radioactive wastes and their disposal

    International Nuclear Information System (INIS)

    Neumann, L.

    1984-01-01

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

  10. Method of processing radioactive solid wastes

    International Nuclear Information System (INIS)

    Ootaka, Hisashi; Aizu, Tadashi.

    1980-01-01

    Purpose: To improve the volume-reducing effect for the radioactive solids wastes by freezing and then pulverizing them. Method: Miscellaneous radioactive solid wastes produced from a nuclear power plant and packed in vinyl resin bags are filled in a drum can and nitrogen gas at low temperature (lower than 0 0 C) from a cylinder previously prepared by filling liquid nitrogen (at 15kg/cm 2 , -196 0 C) to freeze the radioactive solid wastes. Thereafter, a hydraulic press is inserted into the drum can to compress and pulverize the thus freezed miscellaneous radioactive solid wastes into powder. The powder thus formed does not expand even after removing the hydraulic press from the drum can, whereby the volume reduction of the radioactive solid wastes can be carried out effectively. (Horiuchi, T.)

  11. Gaseous radioactive waste processing system

    International Nuclear Information System (INIS)

    Onizawa, Hideo.

    1976-01-01

    Object: To prevent explosion of hydrogen gas within gaseous radioactive waste by removing the hydrogen gas by means of a hydrogen absorber. Structure: A coolant extracted from a reactor cooling system is sprayed by nozzle into a gaseous phase (hydrogen) portion within a tank, thus causing slipping of radioactive rare gas. The gaseous radioactive waste rich in hydrogen, which is purged in the tank, is forced by a waste gas compressor into a hydrogen occlusion device. The hydrogen occlusion device is filled with hydrogen occluding agents such as Mg, Mg-Ni alloy, V-Nb alloy, La-Ni alloy and so forth, and hydrogen in the waste gas is removed through reaction to produce hydrogen metal. The gaseous radioactive waste, which is deprived of hydrogen and reduced in volume, is stored in an attenuation tank. The hydrogen stored in the hydrogen absorber is released and used again as purge gas. (Horiuchi, T.)

  12. Management of small quantities of radioactive waste

    International Nuclear Information System (INIS)

    1998-09-01

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

  13. 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.

  14. Radioactive waste management

    International Nuclear Information System (INIS)

    Pahissa Campa, Jaime; Pahissa, Marta H. de

    2000-01-01

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

  15. Extended storage of low-level radioactive waste: potential problem areas

    International Nuclear Information System (INIS)

    Siskind, B.; Dougherty, D.R.; MacKenzie, D.R.

    1985-12-01

    If a state or state compact does not have adequate disposal capacity for low-level radioactive waste (LLRW) by 1986 as required by the Low-Level Waste Policy Act, then extended storage of certain LLRW may be necessary. In this report, extended storage of LLRW is considered in order to determine for the Nuclear Regulatory Commission areas of concern and actions recommended to resolve these concerns. The focus is on the properties and performance of the waste form and waste container. Storage alternatives are considered in order to characterize the likely storage environments for these wastes. The areas of concern about extended storage of LLRW are grouped into two categories: (1) Performance of the waste form and/or container during storage, e.g., radiolytic gas generation, radiation-enhanced degradation of polymeric materials, and corrosion. (2) Effects of extended storage on the properties of the waste form and/or container that are important after storage (e.g., radiation-induced embrittlement of high-density polyethylene and the weakening of steel containers resulting from corrosion). A discussion is given of additional information and actions required to address these concerns

  16. 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)

  17. Radioactive waste management in West Germany

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-01-01

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

  18. Twelfth annual US DOE low-level waste management conference

    International Nuclear Information System (INIS)

    1990-01-01

    The papers in this document comprise the proceedings of the Department of Energy's Twelfth Annual Low-Level Radioactive Waste Management Conference, which was held in Chicago, Illinois, on August 28 and 29, 1990. General subjects addressed during the conference included: mixed waste, low-level radioactive waste tracking and transportation, public involvement, performance assessment, waste stabilization, financial assurance, waste minimization, licensing and environmental documentation, below-regulatory-concern waste, low-level radioactive waste temporary storage, current challenges, and challenges beyond 1990

  19. Chemical decontamination method for radioactive metal waste

    International Nuclear Information System (INIS)

    Onuma, Tsutomu; Akimoto, Hidetoshi

    1991-01-01

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

  20. Radioactive waste management - an educational challenge

    International Nuclear Information System (INIS)

    Tulenko, J.S.

    1991-01-01

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

  1. Nuclear fuel cycle waste recycling technology deverlopment - Radioactive metal waste recycling technology development

    International Nuclear Information System (INIS)

    Oh, Won Zin; Moon, Jei Kwon; Jung, Chong Hun; Park, Sang Yoon

    1998-08-01

    With relation to recycling of the radioactive metal wastes which are generated during operation and decommissioning of nuclear facilities, the following were described in this report. 1. Analysis of the state of the art on the radioactive metal waste recycling technologies. 2. Economical assessment on the radioactive metal waste recycling. 3. Process development for radioactive metal waste recycling, A. Decontamination technologies for radioactive metal waste recycling. B. Decontamination waste treatment technologies, C. Residual radioactivity evaluation technologies. (author). 238 refs., 60 tabs., 79 figs

  2. MANAGEMENT OF RADIOACTIVE WASTES IN CHINA

    Institute of Scientific and Technical Information of China (English)

    潘自强

    1994-01-01

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

  3. Radioactive Waste and Clean-up: Introduction

    International Nuclear Information System (INIS)

    Collard, G.

    2007-01-01

    The primary mission of the Radioactive Waste and Clean-up division is to propose, to develop and to evaluate solutions for a safe, acceptable and sustainable management of radioactive waste. The Radioactive Waste and Clean-up division programme consists in research, studies, development and demonstration aiming to realise the objective of Agenda 21 on sustainable development in the field of radioactive waste and rehabilitation on radioactively contaminated sites. Indeed, it participates in the realisation of an objective which is to ensure that radioactive wastes are safely managed, transported, stored and disposed of, with a view to protecting human health and the environment, within a wider framework of an interactive and integrated approach to radioactive waste management and safety. We believe that nuclear energy will be necessary for the sustainable development of mankind in the 21st century, but we well understand that it would not be maintained if it is not proven that within benefits of nuclear energy a better protection of the environment is included. Although the current waste management practices are both technically and from the environmental point of view adequate, efforts in relation of future power production and waste management technologies should be put on waste minimisation. Therefore, the new and innovative reactors, fuel cycle and waste management processes and installations should be designed so that the waste generation can be kept in minimum. In addition to the design, the installations should be operated so as to create less waste; consideration should be given e.g. to keeping water chemistry clean and other quality factors. SCK-CEN in general and the Radioactive Waste and Clean-up division in particular are present in international groups preparing the development of innovative nuclear reactors, as Generation 4 and INPRO. Because performance assessments are often black boxes for the public, demonstration is needed for the acceptation of

  4. Underground storage of radioactive wastes

    International Nuclear Information System (INIS)

    Dietz, D.N.

    1977-01-01

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

  5. The Radioactive Waste Management at Studsvik

    Energy Technology Data Exchange (ETDEWEB)

    Hedlund, R; Lindskog, A

    1966-04-15

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

  6. The Radioactive Waste Management at Studsvik

    International Nuclear Information System (INIS)

    Hedlund, R.; Lindskog, A.

    1966-04-01

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

  7. The Radioactive Waste Management Advisory Committee's report on radioactive waste management practices in Switzerland

    International Nuclear Information System (INIS)

    1998-01-01

    Radioactive Waste Management Advisory Committee (RWMAC) is the independent body that advises the Secretary of State for the Environment, Transport and the Regions and the Secretaries of State for Scotland and for Wales on issues relating to radioactive waste management. The terms of reference of the RWMAC, and a list of its Members, are given in Annex 1 to this Report. A group of 16 RWMAC Members examined the management of radioactive waste in Switzerland during a study visit to that country made between 8 and 12 October 1996. The aim of the visit was to acquire first hand knowledge of a set of practices adopted outside the United Kingdom by visiting radioactive waste management facilities and holding discussions with those involved, whether as operators, regulators or advisors to Government. This Report describes what the group saw, records the information collected, and sets out its findings. Switzerland's political system, with the emphasis placed on referenda, encourages popular participation in the democratic process. This may appear to have slowed down the provision of management facilities for radioactive wastes. From a longer term perspective, however, it is clear that such facilities may only really be viable in locations where there is sufficient local support. The quality of the arguments, from both supporters and opponents of nuclear power, is clear evidence of the importance which needs to be attached to the views of those affected. In order to build on what has already been achieved, notably in storage and research, those concerned with radioactive waste management in Switzerland continue to recognise this underlying principle

  8. 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.)

  9. Method of solidifying radioactive waste

    International Nuclear Information System (INIS)

    Hasegawa, Akira; Mihara, Shigeru; Yamashita, Koji; Sauda, Kenzo.

    1988-01-01

    Purpose: To obtain satisfactory plastic solidification products rapidly and more conveniently from radioactive wastes. Method: liquid wastes contain, in addition to sodium sulfate as the main ingredient, nitrates hindering the polymerizing curing reactions and various other unknown ingredients, while spent resins contain residual cationic exchange groups hindering the polymerizing reaction. Generally, as the acid value of unsaturated liquid polyester resins is lower, the number of terminal alkyd resins is small, formation of nitrates is reduced and the polymerizing curing reaction is taken place more smoothly. In view of the above, radioactive wastes obtained by dry powderization or dehydration of radioactive liquid wastes or spent resins are polymerized with unsaturated liquid polyester resins with the acid value of less than 13 to obtain plastic solidification. Thus, if the radioactive wastes contain a great amount of polymerization hindering material such as NaNO 2 , they can be solidified rapidly and conveniently with no requirement for pre-treatment. (Kamimura, Y.)

  10. 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.

  11. Method of solidifying radioactive solid wastes

    International Nuclear Information System (INIS)

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

    1984-01-01

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

  12. 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

  13. Developing radioactive waste management policy

    International Nuclear Information System (INIS)

    Gichana, Z.

    2012-04-01

    A policy for radioactive waste management with defined goals and requirements is needed as a basis for the preparation of legislation, review or revision of related legislation and to define roles and responsibilities for ensuring the safe management of radioactive waste. A well defined policy and associated strategies are useful in promoting consistency of emphasis and direction within all of the sectors involved in radioactive waste management. The absence of policy and strategy can lead to confusion or lack of coordination and direction. A policy and/or strategy may sometimes be needed to prevent inaction on a particular waste management issue or to resolve an impasse. (author)

  14. Overview of radioactive waste management

    International Nuclear Information System (INIS)

    Ritter, G.L.

    1980-01-01

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

  15. The incineration of radioactive waste

    International Nuclear Information System (INIS)

    Thegerstroem, C.

    1980-03-01

    In this study, made on contract for the Swedish Nuclear Power Inspectorate, different methods for incineration of radioactive wastes are reviewed. Operation experiences and methods under development are also discussed. The aim of incineration of radioactive wastes is to reduce the volume and weight of the wastes. Waste categories most commonly treated by incineration are burnable solid low level wastes like trash wastes consisting of plastic, paper, protective clothing, isolating material etc. Primarily, techniques for the incineration of this type of waste are described but incineration of other types of low level wastes like oil or solvents and medium level wastes like ion-exchange resins is also briefly discussed. The report contains tables with condensed data on incineration plants in different countries. Problems encountered, experiences and new developments are reviewed. The most important problems in incineration of radioactive wastes have been plugging and corrosion of offgas systems, due to incomplete combustion of combustion of materials like rubber and PVC giving rise to corrosive gases, combined with inadequate materials of construction in heat-exchangers, channels and filter housings. (author)

  16. Radioactive waste management at AECL

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  17. Session 1984-85. Radioactive waste. Minutes of evidence, Monday 17 June 1985. Nuclear Industry Radioactive Waste Executive

    International Nuclear Information System (INIS)

    1985-01-01

    The Environment Select Committee of the House of Commons received a memorandum from the Nuclear Industry Radioactive Waste Executive, on the management and disposal of radioactive waste arising in the UK, under the headings: introduction; the structure of NIREX; the nature of radioactive waste; plans for the disposal of low and intermediate level wastes. Representatives of NIREX were examined on the subject of the memorandum and the minutes of evidence are recorded. (U.K.)

  18. Coal combustion ashes: A radioactive Waste?

    International Nuclear Information System (INIS)

    Michetti, F.P.; Tocci, M.

    1992-01-01

    The radioactive substances naturally hold in fossil fuels, such as Uranium and Thorium, after the combustion, are subjected to an increase of concentration in the residual combustion products as flying ashes or as firebox ashes. A significant percentage of the waste should be classified as radioactive waste, while the political strategies seems to be setted to declassify it as non-radioactive waste. (Author)

  19. Argentina's radioactive waste disposal policy

    International Nuclear Information System (INIS)

    Palacios, E.

    1986-01-01

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

  20. Management of radioactive waste from nuclear applications

    International Nuclear Information System (INIS)

    1997-01-01

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

  1. Radioactive liquid waste processing system

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  2. Nuclear Waste Treatment Program: Annual report for FY 1986

    International Nuclear Information System (INIS)

    Burkholder, H.C.; Brouns, R.A.; Powell, J.A.

    1987-09-01

    To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs

  3. Nuclear Waste Treatment Program: Annual report for FY 1986

    Energy Technology Data Exchange (ETDEWEB)

    Burkholder, H.C.; Brouns, R.A. (comps.); Powell, J.A. (ed.)

    1987-09-01

    To support DOE's attainment of its goals, Nuclear Waste Treatment Program (NWTP) is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting. This annual report describes progress during FY 1986 toward meeting these two objectives. 29 refs., 59 figs., 25 tabs.

  4. Twelfth annual US DOE low-level waste management conference

    Energy Technology Data Exchange (ETDEWEB)

    1990-01-01

    The papers in this document comprise the proceedings of the Department of Energy's Twelfth Annual Low-Level Radioactive Waste Management Conference, which was held in Chicago, Illinois, on August 28 and 29, 1990. General subjects addressed during the conference included: mixed waste, low-level radioactive waste tracking and transportation, public involvement, performance assessment, waste stabilization, financial assurance, waste minimization, licensing and environmental documentation, below-regulatory-concern waste, low-level radioactive waste temporary storage, current challenges, and challenges beyond 1990.

  5. Radioactive waste programme in Latvia

    International Nuclear Information System (INIS)

    Salmins, A.

    2000-01-01

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

  6. Collecting and identifying the radioactive waste

    International Nuclear Information System (INIS)

    Dogaru, C. GH.

    2001-01-01

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

  7. Radioactivity in foodstuffs 1990

    International Nuclear Information System (INIS)

    1991-01-01

    The average per capita radiation dose received by the Norwegian population due to intake of foodstuffs in 1990 was between 0.03 and 0.06 mSv. This was about the same level as in previous years since the Chernobyl accident. Certain individuals with special dietary habits (consumption of large amounts of freshwater fish and reindeer), and who live in heavily contaminated areas, received higher doses (appr. 1 mSv). In 1990 dietary advice was maintained with regard to people consuming large amounts of reindeer meat and/or game and freshwater fish. The aim is still that no person shall be exposed to an annual dose of more than 1 mSv through food. The present report reviews the data concerning radioactivity levels in dairy products, meat and fish for 1990. Levels were similar to those recorded in the previous year, but considerably lower than those in 1988. The report also presents some data from a 5-year radio-ecological research programme carried out by the Norwegian Institute of Nature Research (NINA). In general, levels in wild fish and game were below the intervention limit of 6000 Bq/kg, apart from a few reindeer herds and fish from a few localities. 8 figs. 6 tabs

  8. Radioactive waste storage facility and underground disposal method for radioactive wastes using the facility

    International Nuclear Information System (INIS)

    Endo, Yoshihiro.

    1997-01-01

    A sealed container storage chamber is formed in underground rocks. A container storage pool is formed on the inner bottom of the sealed vessel storage chamber. A heat exchanger for cooling water and a recycling pump are disposed on an operation floor of the sealed vessel storage chamber. Radioactive wastes sealed vessels in which radioactive wastes are sealed are transferred from the ground to the sealed vessel storage chamber through a sealed vessel transferring shaft, and immersed in cooling water stored in the vessel storage pool. When after heat of the radioactive wastes is removed by the cooling water, the cooling water in the vessel storage pool is sucked up to the ground surface. After dismantling equipments, bentonite-type fillers are filled in the inside of the sealed vessel storage chamber, sealed vessel transferring shaft, air supplying shaft and air exhaustion shaft, and the radioactive waste-sealed vessels can be subjected stably to into underground disposal. (I.N.)

  9. Geological aspects of radioactive waste disposal

    International Nuclear Information System (INIS)

    Kobera, P.

    1985-01-01

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

  10. Radioactive waste disposal package

    Science.gov (United States)

    Lampe, Robert F.

    1986-11-04

    A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

  11. Shifting paradigms in managing radioactive waste

    International Nuclear Information System (INIS)

    Le Bars, Y.; Pescatore, C.

    2004-01-01

    The Stakeholder involvement in policy making of radioactive waste management, has received considerable attention within the OECD. The Nea forum on Stakeholder confidence (FSC) was set up in 2000. A Nea recent publication entitled ''Learning and adapting to societal requirements for radioactive waste management'' brings together the key FSC findings and experience covering four years of work. Six main areas are targeted in this publication and are briefly described in this document: favourable candidates for issuing radioactive waste management policy, the design of the decision-making process, the social and ethical dimension, trust in the actors, Stakeholder involvement and the local dimension of radioactive waste management. (A.L.B.)

  12. Radioactive waste disposal implications of extending Part IIA of the Environmental Protection Act to cover radioactively contaminated land.

    Science.gov (United States)

    Nancarrow, D J; White, M M

    2004-03-01

    A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA of the Environmental Protection Act 1990 to include radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of the radioactive wastes arising from remediation. This is expected to be principally wastes of high volume and low activity (categorised as low level waste (LLW) and very low level waste (VLLW)). The availability problem results from a lack of applications by landfill operators for authorisation to accept LLW wastes for disposal. This is apparently due to perceived adverse publicity associated with the consultation process for authorisation coupled with uncertainty over future liabilities. Disposal of waste as VLLW is limited both by questions over volumes that may be acceptable and, more fundamentally, by the likely alpha activity of wastes (originating from radium and thorium operations). Authorised on-site disposal has had little attention in policy and guidance in recent years, but may have a part to play, especially if considered commercially attractive. Disposal at BNFL's near surface disposal facility for LLW at Drigg is limited to wastes for which there are no practical alternative disposal options (and preference has been given to operational type wastes). Therefore, wastes from the radioactively contaminated land (RCL) regime are not obviously attractive for disposal to Drigg. Illustrative calculations have been performed based on possible volumes and activities of RCL arisings (and assuming Drigg's future volumetric disposal capacity is 950,000 m3). These suggest that wastes arising from implementing the RCL regime, if all disposed to Drigg, would not represent a significant fraction of the volumetric capacity of Drigg, but could have a significant impact on the radiological

  13. Radioactive waste disposal implications of extending Part IIA of the Environmental Protection Act to cover radioactively contaminated land

    International Nuclear Information System (INIS)

    Nancarrow, D J; White, M M

    2004-01-01

    A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA of the Environmental Protection Act 1990 to include radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of the radioactive wastes arising from remediation. This is expected to be principally wastes of high volume and low activity (categorised as low level waste (LLW) and very low level waste (VLLW)). The availability problem results from a lack of applications by landfill operators for authorisation to accept LLW wastes for disposal. This is apparently due to perceived adverse publicity associated with the consultation process for authorisation coupled with uncertainty over future liabilities. Disposal of waste as VLLW is limited both by questions over volumes that may be acceptable and, more fundamentally, by the likely alpha activity of wastes (originating from radium and thorium operations). Authorised on-site disposal has had little attention in policy and guidance in recent years, but may have a part to play, especially if considered commercially attractive. Disposal at BNFL's near surface disposal facility for LLW at Drigg is limited to wastes for which there are no practical alternative disposal options (and preference has been given to operational type wastes). Therefore, wastes from the radioactively contaminated land (RCL) regime are not obviously attractive for disposal to Drigg. Illustrative calculations have been performed based on possible volumes and activities of RCL arisings (and assuming Drigg's future volumetric disposal capacity is 950 000 m 3 ). These suggest that wastes arising from implementing the RCL regime, if all disposed to Drigg, would not represent a significant fraction of the volumetric capacity of Drigg, but could have a significant impact on the radiological

  14. Low-level radioactive waste management. Background paper

    International Nuclear Information System (INIS)

    Fawcett, R.

    1993-11-01

    The management of radioactive waste is one of the most serious environmental problems facing Canadians. From the early industrial uses of radioactive material in the 1930s to the development of nuclear power reactors and the medical and experimental use of radioisotopes today, there has been a steady accumulation of waste products. Although the difficulties involved in radioactive waste management are considerable, responsible solutions are possible. This paper will discuss low-level radioactive waste, including its production, the amounts in storage, the rate of waste accumulation and possible strategies for its management. (author). 2 figs

  15. Radioactive waste treatment and handling in France

    International Nuclear Information System (INIS)

    Sivintsev, Yu.V.

    1984-01-01

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

  16. Radioactive wastes management

    International Nuclear Information System (INIS)

    Albert, Ph.

    1999-01-01

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

  17. Radioactive waste management

    International Nuclear Information System (INIS)

    Kizawa, Hideo

    1982-01-01

    A system of combining a calciner for concentrated radioactive liquid waste and an incinerator for miscellaneous radioactive solid waste is being developed. Both the calciner and the incinerator are operated by fluidized bed method. The system features the following points: (1) Inflammable miscellaneous solids and concentrated liquid can be treated in combination to reduce the volume. (2) Used ion-exchange resin can be incinerated. (3) The system is applicable even if any final waste disposal method is adopted; calcinated and incinerated solids obtained as intermediate products are easy to handle and store. (4) The system is readily compatible with other waste treatment systems to form optimal total system. The following matters are described: the principle of fluidized-bed furnaces, the objects of treatment, system constitution, the features of the calciner and incinerator, and the current status of development. (J.P.N.)

  18. 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

  19. Underground radioactive waste disposal concept

    International Nuclear Information System (INIS)

    Frgic, L.; Tor, K.; Hudec, M.

    2002-01-01

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

  20. Radioactive waste management regulatory framework in Mexico

    International Nuclear Information System (INIS)

    Barcenas, M.; Mejia, M.

    2001-01-01

    The purpose of this paper is to present an overview of the current regulatory framework concerning the radioactive waste management in Mexico. It is intended to show regulatory historical antecedents, the legal responsibilities assigned to institutions involved in the radioactive waste management, the sources of radioactive waste, and the development and preparation of national standards for fulfilling the legal framework for low level radioactive waste. It is at present the most important matter to be resolved. (author)

  1. Radioactive wastes handling facility

    International Nuclear Information System (INIS)

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

    1997-01-01

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

  2. Method of processing radioactive liquid waste

    International Nuclear Information System (INIS)

    Motojima, Kenji; Kawamura, Fumio.

    1981-01-01

    Purpose: To increase the efficiency of removing radioactive cesium from radioactive liquid waste by employing zeolite affixed to metallic compound ferrocyanide as an adsorbent. Method: Regenerated liquid waste of a reactor condensation desalting unit, floor drain and so forth are collected through respective supply tubes to a liquid waste tank, and the liquid waste is fed by a pump to a column filled with zeolite containing a metallic compound ferrocyanide, such as with copper, zinc, manganese, iron, cobalt, nickel or the like. The liquid waste from which radioactive cesium is removed is dried and pelletized by volume reducing and solidifying means. (Yoshino, Y.)

  3. The management of radioactive waste in laboratories

    International Nuclear Information System (INIS)

    McLintock, I.S.

    1996-01-01

    Many laboratories in universities, colleges, research institutions and hospitals produce radioactive wastes. The recently-coined term for them is small users of radioactive materials, to distinguish them from concerns such as the nuclear industry. Until recently the accepted official view was that small users had few problems in disposing of their radioactive wastes. This misconception was dispelled in 1991 by the 12th Annual Report of the Radioactive Waste Management Advisory Committee. This book includes a description of the principles of the management and disposal of radioactive wastes from these laboratories. Its main intention, however, is to provide practical information and data for laboratory workers as well as for those responsible for management and ultimate disposal of radioactive wastes. I hope that it succeeds in this intention. (UK)

  4. Low-level radioactive wastes

    International Nuclear Information System (INIS)

    Garbay, H.; Chapuis, A.M.

    1988-01-01

    During dismantling operations of nuclear facilities radioctive and non radioactive wastes are produced. The distinction between both kinds of wastes is not easy. In each dismantling operation special care and rules are defined for the separation of wastes. Each case must be separately studied. The volume and the surface activites are analyzed. Part of the wastes had been disposed in a public environment. The regulations, the international recommendations, thetheoretical and experimental investigations in this field are presented. A regulation principle and examples of radioactivity limits, on the basis of international recommendations, are provided. Those limits are calculated from individual radiation dose that may reach human beings [fr

  5. Method of transporting radioactive slurry-like wastes

    Energy Technology Data Exchange (ETDEWEB)

    Kamiya, K; Yusa, H; Sugimoto, Y

    1975-06-30

    The object is to prevent blockage of a transporting tube to positively and effectively transport radioactive slurry wastes. A method of transporting radioactive slurry-like wastes produced in an atomic power plant, wherein liquid wastes produced in the power plant are diluted to form into a driving liquid, by which said radioactive slurry-like wastes are transported within the pipe, and said driving liquid is recovered as the liquid waste.

  6. National Inventory of Radioactive Wastes, Edition 1998

    International Nuclear Information System (INIS)

    Pallard, Bernard; Vervialle, Jean Pierre; Voizard, Patrice

    1998-01-01

    The National Radioactive Waste Inventory is an annual report of French National Agency for Radioactive Waste Management (ANDRA). The issue on 1998 has the following content: 1. General presentation; 2. Location of radioactive wastes in France; 3. Regional file catalogue; 4. Address directory; 5. Annexes. The inventory establishes the producer and owner categories, the French overseas waste sources, location of pollutant sides, spread wastes (hospitals, universities and industrial sector), railways terminals

  7. 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.

  8. Disposal of radioactive wastes from Czechoslovak nuclear power plants

    International Nuclear Information System (INIS)

    Neumann, L.

    In gaseous radioactive waste disposal, aerosol particles are filtered and gaseous wastes are discharged in the environment. The filters and filter materials used are stored on solid radioactive waste storage sites in the individual power plants. Liquid radioactive wastes are concentrated and the concentrates are stored. Distillates and low-level radioactive waste water are discharged into the hydrosphere. Solid radioactive wastes are stored without treatment in power plant bunkers. Bituminization and cementation of liquid radioactive wastes are discussed. (H.S.)

  9. World ocean and radioactive wastes

    International Nuclear Information System (INIS)

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

    2000-01-01

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

  10. Radioactive waste management in Belgium

    International Nuclear Information System (INIS)

    Detilleux, E.

    1984-01-01

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

  11. Method of solidifying radioactive wastes

    International Nuclear Information System (INIS)

    Fukazawa, Tetsuo; Ootsuka, Masaharu; Uetake, Naoto; Ozawa, Yoshihiro.

    1984-01-01

    Purpose: To prepare radioactive solidified wastes excellent in strength, heat resistance, weather-proof, water resistance, dampproof and low-leaching property. Method: A hardening material reactive with alkali silicates to form less soluble salts is used as a hardener for alkali silicates which are solidification filler for the radioactive wastes, and mixed with cement as a water absorbent and water to solidify the radioactive wastes. The hardening agent includes, for example, CaCO 3 , Ca(ClO 4 ) 2 , CaSiF 6 and CaSiO 3 . Further, in order to reduce the water content in the wastes and reduce the gap ratio in the solidification products, the hardener adding rate, cement adding rate and water content are selected adequately. As the result, solidification products can be prepared with no deposition of easily soluble salts to the surface thereof, with extremely low leaching of radioactive nucleides. (Kamimura, M.)

  12. Vitrification of hazardous and radioactive wastes

    International Nuclear Information System (INIS)

    Bickford, D.F.; Schumacher, R.

    1995-01-01

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

  13. National Syrian Program for Radioactive Waste Management

    International Nuclear Information System (INIS)

    Othman, I.; Takriti, S.

    2009-06-01

    A national plan for radioactive waste management has been presented. It includes identifying, transport, recording, classifying, processing and disposal. It is an important reference for radioactive waste management for those dealing with radioactive waste, and presents a complete protection to environemnt and people. (author)

  14. A method for conditioning radioactive-wastes

    International Nuclear Information System (INIS)

    Cuaz, Daniel; Thiery, Daniel.

    1974-01-01

    Description is given of a method for conditioning radioactive-wastes, according to the main patent. This method is characterized in that the radioactive wastes are constituted by radio-elements incorporated with filtration and/or floculation promoters. This can be applied to radioactive effluent processing [fr

  15. Cosmic disposal of radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

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

    1975-03-01

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

  16. Radioactive waste storage issues

    International Nuclear Information System (INIS)

    Kunz, D.E.

    1994-01-01

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

  17. Method of processing radioactive wastes

    International Nuclear Information System (INIS)

    Takahashi, Toshihiko; Maruko, Morihisa; Takamura, Yoshiyuki.

    1981-01-01

    Purpose: To effectively separate radioactive claddings from the slurry of wasted ion exchange resins containing radioactive claddings. Method: Wasted ion exchange resins having radioactive claddings (fine particles of iron oxides or hydroxide adhered with radioactive cobalt) are introduced into a clad separation tank. Sulfuric acid or sodium hydroxide is introduced to the separation tank to adjust the pH value to 3 - 6. Then, sodium lauryl sulfate is added for capturing claddings and airs are blown from an air supply nozzle to generate air bubbles. The claddings are detached from the ion exchange resins and adhered to the air bubbles. The air bubbles adhered with the claddings float up to the surface of the liquid wastes and then forced out of the separation tank. (Ikeda, J.)

  18. Method of processing radioactive wastes

    International Nuclear Information System (INIS)

    Katada, Katsuo.

    1986-01-01

    Purpose: To improve the management for radioactive wastes containers thereby decrease the amount of stored matters by arranging the radioactive wastes containers in the order of their radioactivity levels. Method: The radiation doses of radioactive wastes containers arranged in the storing area before volume-reducing treatment are previously measured by a dosemeter. Then, a classifying machine is actuated to hoist the containers in the order to their radiation levels and the containers are sent out passing through conveyor, surface contamination gage, weight measuring device and switcher to a volume-reducing processing machine. The volume-reduced products are packed each by several units to the storing containers. Thus, the storing containers after stored for a certain period of time can be transferred in an assembled state. (Kawakami, Y.)

  19. Radioactive waste disposal. Facts, problems and responsible action

    International Nuclear Information System (INIS)

    Finckh, E.; Seitz, M.

    1994-01-01

    In a first part, natural science and technology aspects of waste management are outlined: basic concepts of radioactivity; properties, detection and primary effects of radioactive radiation; biological effect of radioactivity and radiation; general geological bases; composition of spent fuel elements; interim storage and transport; reprocessing of spent fuels; classification and treatment of radioactive wastes; emplacement possibilities for radioactive wastes; possible ways of radionuclides from the repository back into the biosphere; comparative consideration of the risks involved in nuclear waste management. The second part of the paper deals with ethical and theological aspects of radioactive waste management. (orig./HP) [de

  20. 40 CFR 227.30 - High-level radioactive waste.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false High-level radioactive waste. 227.30...-level radioactive waste. High-level radioactive waste means the aqueous waste resulting from the operation of the first cycle solvent extraction system, or equivalent, and the concentrated waste from...

  1. Elements of a radioactive waste management course

    International Nuclear Information System (INIS)

    Fentiman, A.W.

    1994-01-01

    The demand for scientists, engineers, and technicians with expertise in radioactive waste management is growing rapidly. Many universities, government agencies, and private contractors are developing courses in radioactive waste management. Two such courses have been developed at The Ohio State University. In support of that course development, two surveys were conducted. One survey went to all nuclear engineering programs in the US to determine what radioactive waste management courses are currently being taught. The other went to 600 waste management professionals, asking them to list the topics they think should be included in a radioactive waste management course. Four key elements of a course in radioactive waste management were identified. They are (a) technical information, (b) legal and regulatory framework, (c) communicating with the public, and (d) sources of information on waste management. Contents of each of the four elements are discussed, and results of the surveys are presented

  2. Requirements for a radioactive waste data base

    International Nuclear Information System (INIS)

    Sato, Y.; Kobayashi, I.; Kikuchi, M.

    1990-01-01

    With the progress of nuclear fuel cycle in Japan, various types of radioactive waste will generate at each nuclear facility in the cycle. Therefor generated volume and stored quantity of waste will be supposed to increase. From the viewpoints of safety and public acceptance, by using mainframe computer it is necessary that the treatment of historical waste data, the estimation of generated waste volume and stored quantity and the investigation of research and development status of waste processing and disposal are carried out. This paper proposes design and development of the radioactive waste data base which is able to properly and correctly manage and grasp numerical and/or documentary information for generated radioactive waste. So the data base will be expected to use for planning the future management of radioactive waste. (author)

  3. 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

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

    International Nuclear Information System (INIS)

    Yamamoto, Masayuki; Hashimoto, Naro

    2002-02-01

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

  5. The management of high-level radioactive wastes

    International Nuclear Information System (INIS)

    Lennemann, Wm.L.

    1979-01-01

    The definition of high-level radioactive wastes is given. The following aspects of high-level radioactive wastes' management are discussed: fuel reprocessing and high-level waste; storage of high-level liquid waste; solidification of high-level waste; interim storage of solidified high-level waste; disposal of high-level waste; disposal of irradiated fuel elements as a waste

  6. 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

  7. Lessons to be learned from radioactive waste disposal practices for non-radioactive hazardous waste management

    International Nuclear Information System (INIS)

    Merz, E.R.

    1991-01-01

    The criteria to be set up for any kind of hazardous waste disposal must always be put in perspective: 1. what are the waste characteristics? 2. what time period for safe isolation is of interest? 3. which geological disposal alternatives exist? Different approaches may be used in the short- and long-term perspective. In either case, a general procedure is recommended which involves concentrating, containing and isolating the source of toxicity, both radioactive and chemotoxic substances, as far as practicable. Waste characterization of either chemotoxic or radioactive wastes should be performed applying comparable scientifically based principles. The important question which arises is whether their hazard potential can be quantified on the basis of dose comparison regarding the morbidity effects of radiation and of chemical pollutants. Good control over the consequences of hazardous waste disposal requires threat detailed criteria for tolerable contamination of radioactive as well as chemical pollutants should be established, and that compliance with these criteria can be demonstrated. As yet, there are no well developed principles for assessing the detriment from most types of genotoxic waste other than radioactive material. The time horizon discussed for both categories of waste for their proof of safe isolation differs by a factor of about one hundred. (au)

  8. 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

  9. Radioactive waste management for a radiologically contaminated hospitalized patient

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  10. Method of processing radioactive liquid wastes

    Energy Technology Data Exchange (ETDEWEB)

    Sugimoto, Y; Kikuchi, M; Funabashi, K; Yusa, H; Horiuchi, S

    1978-12-21

    Purpose: To decrease the volume of radioactive liquid wastes essentially consisting of sodium hydroxide and boric acid. Method: The concentration ratio of sodium hydroxide to boric acid by weight in radioactive liquid wastes essentially consisting of sodium hydroxide and boric acid is adjusted in the range of 0.28 - 0.4 by means of a pH detector and a sodium concentration detector. Thereafter, the radioactive liquid wastes are dried into powder and then discharged.

  11. Ruthenium separation device from radioactive waste

    International Nuclear Information System (INIS)

    Ayabe, Osao.

    1988-01-01

    Purpose: To efficiently oxidize ruthenium in radioactive wastes and evaporize ruthenium tetraoxide after oxidization thereof, thereby improve the separation and recovery rate. Constitution: The device comprises an oxidization vessel for supplying an oxidizing agent into radioactive wastes to oxidize ruthenium in the wastes into ruthenium tetraoxide, and a distillation vessel for introducing radioactive wastes after oxidization, distillating under heating ruthenium tetraoxide leached into the wastes and evaporizing ruthenium tetraoxide. By dividing the device into the oxidizing vessel and the distillation vessel, the oxidizing treatment and the distilling treatment can individually be operated optimally to improve the separation and recovery rate of ruthenium. (Takahashi, M.)

  12. Nuclear power and radioactive waste

    International Nuclear Information System (INIS)

    Grimston, M.

    1991-03-01

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

  13. 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

  14. 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

  15. Research requirements for a unified approach to modelling chemical effects associated with radioactive waste disposal

    International Nuclear Information System (INIS)

    Krol, A.A.; Read, D.

    1986-09-01

    This report contains the results of a review of the current modelling, laboratory experiments and field experiments being conducted in the United Kingdom to aid understanding and improve prediction of the effects of chemistry on the disposal of radioactive wastes. The aim has been to summarise present work and derive a structure for future research effort that would support the use of probabilistic risk assessment (pra) methods for the disposal of radioactive wastes. The review was conducted by a combination of letter and personal visits, and preliminary results were reported to a plenary meeting of participants held in April, 1986. Following this meeting, copies of the report were circulated to participants at draft stage, so that the finalised report should be taken to provide as far as possible a consensus of opinion of research requirements. (author)

  16. Method for processing powdery radioactive wastes

    International Nuclear Information System (INIS)

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

    1978-01-01

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

  17. Radioactive waste treatment

    International Nuclear Information System (INIS)

    Alter, U.

    1988-01-01

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

  18. Liquid Radioactive Wastes Treatment: A Review

    Directory of Open Access Journals (Sweden)

    Yung-Tse Hung

    2011-05-01

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

  19. Radioactive Waste and Clean-up Division

    International Nuclear Information System (INIS)

    Collard, G.

    2001-01-01

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

  20. Characterization of the solid radioactive waste from Cernavoda NPP

    International Nuclear Information System (INIS)

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

    2005-01-01

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

  1. 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)

  2. FFTF radioactive solid waste handling and transport

    International Nuclear Information System (INIS)

    Thomson, J.D.

    1982-01-01

    The equipment necessary for the disposal of radioactive solid waste from the Fast Flux Test Facility (FFTF) is scheduled to be available for operation in late 1982. The plan for disposal of radioactive waste from FFTF will utilize special waste containers, a reusable Solid Waste Cask (SWC) and a Disposable Solid Waste Cask (DSWC). The SWC will be used to transport the waste from the Reactor Containment Building to a concrete and steel DSWC. The DSWC will then be transported to a burial site on the Hanford Reservation near Richland, Washington. Radioactive solid waste generated during the operation of the FFTF consists of activated test assembly hardware, reflectors, in-core shim assemblies and control rods. This radioactive waste must be cleaned (sodium removed) prior to disposal. This paper provides a description of the solid waste disposal process, and the casks and equipment used for handling and transport

  3. Waterproofing improvement of radioactive waste asphalt solid

    International Nuclear Information System (INIS)

    Adachi, Katsuhiko; Yamaguchi, Takashi; Ikeoka, Akira.

    1981-01-01

    Purpose: To improve the waterproofing of asphalt solid by adding an alkaline earth metal salt and, further, paraffin, into radioactive liquid waste when processing asphalt solidification of the radioactive liquid waste. Method: Before processing molten asphalt solidification of radioactive liquid waste, soluble salts of alkaline earth metal such as calcium chloride, magnesium chloride, or the like is added to the radioactive liquid waste. Paraffin having a melting point of higher than 60 0 C, for example, is added to the asphalt, and waterproofing can be remarkably improved. The waste asphalt solid thus fabricated can prevent the swelling thereof, and can improve its waterproofing. (Yoshihara, H.)

  4. Identification and characterization of radioactive wastes

    International Nuclear Information System (INIS)

    RANDRIAMORA, T.H.

    2007-01-01

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

  5. Radioactive waste management perspectives in Malaysian Nuclear Agency

    International Nuclear Information System (INIS)

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

    2009-01-01

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

  6. Institutional arrangements for radioactive waste management

    International Nuclear Information System (INIS)

    Willrich, M.

    1976-01-01

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

  7. Spanish program on disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Lopez Perez, B.; Ramos Salvador, L.; Martines Martinez, A.

    1977-01-01

    The Spanish Energetic Program assumes an installed nuclear electrical power of 23.000 MWe by the year 1985. Therefore, Spain is making an effort in the managment of radioactive wastes, that can be synthesized in the following points: 1.- Make-up and review of the regulation on the management of radioactive wastes. 2.- Development of the processes and equipment for the treatment of solid, liquid and gaseous wastes from the CNEN ''Juan Vigon'', as well as those from the Nuclear Center of Soria. Solidification studies of RAA wastes arisen from the reprocessing. 3.- Evaluation of radioactive waste treatment systems of the new installed nuclear power plants. Assistance to the nuclear and radioactive facilities operators. 4.- Increase the storage capacity of the pilot repository for solid radioactive wastes of categories 1 and 2 IAEA, located in Sierra Albarrana. Studies of adequate geological formation for storage of solid wastes of IAEA categories 3 and 4. 5.- Studies about long term surface storage systems for solidified RAA wastes arisen from the reprocessing [es

  8. Optimization of the radioactive waste storage

    International Nuclear Information System (INIS)

    Dellamano, Jose Claudio

    2005-01-01

    Radioactive waste storage is the practice adopted in countries where the production of small quantities of radioactive waste does not justify the immediate investment in the construction of a repository. Accordingly, at IPEN, treated radioactive wastes, mainly solid compacted, have been stored for more than 20 years, in 200 dm 3 drums. The storage facility is almost complete and must be extended. Taking into account that a fraction of these wastes has decayed to a very low level due to the short half - life of some radionuclides and considering that 'retrieval for disposal as very low level radioactive waste' is one of the actions suggested to radioactive waste managers, the Laboratory of Waste Management of IPEN started a project to apply the concepts of clearance levels and exemption limits to optimize the radioactive waste storage capacity . This study has been carried out by determining the doses and costs related to two main options: either to maintain the present situation or to open the packages and segregate the wastes that may be subject to clearance, using the national, two international clearance levels and the annual public limit. Doses and costs were evaluated as well as the collective dose and the detriment cost. The analytical solution among the evaluated options was determined by using the technique to aid decision making known as cost-benefit analysis. At last, it was carried out the sensitivity analysis considering all criteria and parameters in order to assess the robustness of the analytical solution. This study can be used as base to other institutions or other countries with similar nuclear programs. (author)

  9. Method and device of decontaminating radioactive solid wastes

    International Nuclear Information System (INIS)

    Hasegawa, Hiroshi; Tamada, Masami.

    1983-01-01

    Purpose: To surely enable grinding for the inner surface of hollow radioactive solid wastes such as pipeways or valves, as well as enable to decontaminate these solid wastes to such a level as being capable of processing in the same manner for the ordinary wastes. Method: A grinding piece abutting resiliently against the inner surface of a hollow radioactive solid wastes to be contaminated is attached at the top end of a flexible shaft, and the inner surface of the radioactive solid wastes is ground while rotating and slightly reciprocating, as well as axially moving the flexible shaft. Consequently, since the grinding piece is always abutted against the inner surface of the radioactive solid wastes just following after the profile of the inner surface, and the flexible shaft is resiliently flexed corresponding to the profile of the inner surface of the radioactive solid wastes, even an inner surface of radioactive solid wastes with a complicated configuration can surely be ground entirely. This surely enables to remove radioactive claddings and contaminated layers deposited on the surface. (Yoshihara, H.)

  10. Method of decomposing radioactive organic solvent wastes

    International Nuclear Information System (INIS)

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

    1986-01-01

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

  11. Radioactive wastes. Their industrial management

    International Nuclear Information System (INIS)

    Lavie, J.M.

    1982-01-01

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

  12. Optimization of Concrete Composition in Radioactive Waste Management

    International Nuclear Information System (INIS)

    IIija, P.

    1999-01-01

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

  13. Instructive for radioactive solid waste management

    International Nuclear Information System (INIS)

    Mora Rodriguez, Patricia

    2014-01-01

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

  14. 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)

  15. Proposed goals for radioactive waste management

    International Nuclear Information System (INIS)

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

    1977-04-01

    Goals are proposed for the national radioactive waste management program to establish a policy basis for the guidance and coordination of the activities of government, business, and academic organizations whose responsibility it will be to manage radioactive wastes. The report is based on findings, interpretations, and analyses of selected primary literature and interviews of personnel concerned with waste management. Public concerns are identified, their relevance assessed, and a conceptual framework is developed that facilitates understanding of the dimensions and demands of the radioactive waste management problem. The nature and scope of the study are described along with the approach used to arrive at a set of goals appropriately focused on waste management

  16. Radioactive waste disposal

    International Nuclear Information System (INIS)

    Cluchet, J.; Roger, B.

    1975-10-01

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

  17. Interim storage of radioactive waste packages

    International Nuclear Information System (INIS)

    1998-01-01

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

  18. Radioactive waste management at WWER type reactors

    International Nuclear Information System (INIS)

    1993-05-01

    This report was prepared within the framework of the Technical Assistance Regional Project on Advice on Waste Management at WWER Type Reactors, which was initiated by the IAEA in 1991. The Regional Project is an integral part of the IAEA's activities directed towards improvement of the safety and reliability of nuclear power plants with WWER type reactors (Soviet designed PWRs). Forty-five WWER type units are currently in operation and twenty-five are under construction in Bulgaria, Czechoslovakia, Finland, Hungary and the former USSR. The idea of regional collaboration between eastern European countries under the auspices of the IAEA was discussed for the first time during the last meeting of the Council for Mutual Economic Assistance (CMEA) on spent fuel and radioactive waste management, held in Rez, Czechoslovakia, in October 1990. Since then, the CMEA and some of its former Member States have ceased to exist. However, there are many reasons for eastern European countries to continue their regional collaboration at a higher level. The USSR, the designer and supplier of WWER type reactors in eastern European countries, participated in the first phase of the project. The majority of WWER type reactors are situated in States of the former USSR (Russia and Ukraine). The main results of the first phase of the Regional Project are: (i) Re-establishment of communication channels among eastern European countries operating WWER type reactors by incorporating the IAEA's technical assistance; (ii) Identification of common waste management problems (administrative and technical) requiring resolution; (iii) Familiarization with radioactive waste management systems at nuclear power plants with WWER type reactors - Paks (Hungary), Loviisa (Finland), Jaslovske Bohunice (Czechoslovakia) and Novovoronezh (Russian Federation). Tabs

  19. Characterization of the solid radioactive waste From Cernavoda NPP

    International Nuclear Information System (INIS)

    Iordache, M.; Laotaru, V.

    2005-01-01

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

  20. Radioactive fallout in air and rain: results to the end of 1990

    International Nuclear Information System (INIS)

    Playford, K.; Lewis, G.N.J.; Carpenter, R.C.

    1992-01-01

    Samples of atmospheric particulate and rainwater have been collected from the United Kingdom and elsewhere. Results are presented of analyses of these samples for various fission products and certain other radionuclides. Average concentrations of Cs-137 in air in the United Kingdom in 1990 were 1% of those in 1986. They were attributable mainly to the resuspension of deposited activity resulting from the Chernobyl accident of April 1986. Plutonium concentrations in air and rainwater were a very small fraction of the National Radiological Protection Board's Generalised Derived Limit for members of the public. Estimates are given of the worldwide deposit of Cs-137 and Sr-90 to the end of 1990. The gamma and beta-ray dose rates from fallout at Chilton are estimated from the observed deposition. (author)

  1. Radioactive waste management

    International Nuclear Information System (INIS)

    1982-07-01

    In response to the Sixth Report of the Royal Commission on Environmental Pollution, a White Paper was published in 1977, announcing a number of steps to deal with the problems presented by wastes from the nuclear industry and setting out the position of the then government. The present White paper is in four sections. i. A brief description of the nature of radioactive wastes, and the general objectives of waste management. ii. What has been achieved, the role of the Radioactive Waste Management Advisory Committee, the expansion of research, and the conclusions from the review of existing controls. iii. The present position for each major category of waste, including relevant current action and research, transport and decommissioning. iv. The next steps. Research and development must continue; shallow land burial and the carefully controlled disposal of certain wastes to the sea will continue to play a role; and, for some wastes, new disposal facilities are needed at an early date. For others, the appropriate course of action at the moment is properly controlled storage. New developments are also required in organisation. Throughout, the public must be kept fully informed about what is being done, and there must be proper scope for public discussion. (U.K.)

  2. Classification and disposal of radioactive wastes

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1990-01-01

    This paper reviews the historical development in the U.S. of definitions and requirements for permanent disposal of different classes of radioactive waste. We first consider the descriptions of different waste classes that were developed prior to definitions in laws and regulations. These descriptions usually were not based on requirements for permanent disposal but, rather, on the source of the waste and requirements for safe handling and storage. We then discuss existing laws and regulations for disposal of different waste classes. Current definitions of waste classes are largely qualitative, and thus somewhat ambiguous, and are based primarily on the source of the waste rather than the properties of its radioactive constituents. Furthermore, even though permanent disposal is clearly recognized as the ultimate goal of radioactive water management, current laws and regulations do not associated the definitions of different waste classes with requirement for particular disposal systems. Thus, requirements for waste disposal essentially are unaffected by ambiguities in the present waste classification system

  3. Management of radioactive waste in FR Yugoslavia

    International Nuclear Information System (INIS)

    Plecas, I.

    1998-01-01

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

  4. Radioactive waste management: International peer reviews

    International Nuclear Information System (INIS)

    Warnecke, E.; Bonne, A.

    1995-01-01

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

  5. Progress on Radioactive Waste Treatment Facilities Construction

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

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

  6. Low-Activity Radioactive Wastes

    Science.gov (United States)

    In 2003 EPA published an Advance Notice of Proposed Rulemaking (ANPR) to collect public comment on alternatives for disposal of waste containing low concentrations of radioactive material ('low-activity' waste).

  7. Management of very low-level radioactive waste

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  8. Radioactive wastes: sources, treatment, and disposal

    International Nuclear Information System (INIS)

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

    1975-01-01

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

  9. Radioactive waste processing device

    International Nuclear Information System (INIS)

    Seki, Shuji.

    1992-01-01

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

  10. Radioactive waste management

    International Nuclear Information System (INIS)

    Tang, Y.S.; Saling, J.H.

    1990-01-01

    The purposes of the book are: To create a general awareness of technologies and programs of radioactive waste management. To summarize the current status of such technologies, and to prepare practicing scientists, engineers, administrative personnel, and students for the future demand for a working team in such waste management

  11. Radioactive waste management: An international perspective

    International Nuclear Information System (INIS)

    Chan, C.Y.

    1992-01-01

    Scientists, governments, and the general public have devoted considerable attention to the subject of radioactive waste over the past 35 years. The subject has gained even more attention of late, owing to heightened awareness of environmental protection. Potential transboundary effects have further added to this interest, which today extends beyond local domains to regional and global levels. Almost all of the IAEA's Member States generate some radioactive wastes. The type of waste they produce varies, however, as do the quantities, which range from a few grams to several hundred tonnes of wastes per year. This article will summarize the status of waste management and disposal activities in IAEA Member States as well as providing a brief background on what radioactive waste is, where it comes from, and how it is managed

  12. Quantitative analysis of the radioactive wastes to be generated in the Brazilian nuclear power plants

    International Nuclear Information System (INIS)

    Santos, Jose Mauro Esteves dos

    1979-01-01

    In the nuclear fuel cycle radioactive waste requiring special treatment (processing, transportation and disposal) is produced. For the implementation of a waste management program, parameters such as volume, specific activity, thermal power, gamma power, (alpha,η) and spontaneous fission neutron production rates are required. In this work, we have calculated: a) The specific activity, thermal power, gamma power and neutron production rate for the irradiated fuel of Angra II; b) The volumes of radioactive waste that will be produced in the nuclear fuel cycle in Brazil; c) The specific activity, thermal power, gamma power and neutron production rate for the high-level waste that will be produced during fuel reprocessing. In the short-term it is concluded that the major problems that will require solution will be the disposal of the low-level waste (volume V L ) and the interim storage of the irradiated fuel elements (volume V F ) generated in the nuclear power plants. For the years 1990 and 2010 these volumes are: (1990) V L = 16149 m 3 ; V F = 1287 m 3 and (2010) V L = 690506 m 3 , V F = 55051 m 3 . In the medium-term the problem of the interim storage of the high-level waste (volume V H ) must be solved. The volumes of this waste we have calculated for the years 2000 and 2010 are: (2000) V H = 50 m 3 and (2010) V H = 1265 m 3 . Long term evaluation of high-level waste disposal must be analysed to aid in initial studies of this problem. Several parameters of this waste have been calculated as a function of time after reprocessing. (author)

  13. The issue resolution process in the Civilian Radioactive Waste Transportation Program

    International Nuclear Information System (INIS)

    Holm, J.A.; Denny, S.

    1987-01-01

    The Civilian Radioactive Waste Management (OCRWM) Program consists of various technical and institutional program activities which engender concern from the general public and from policymakers at federal, state, and local levels. Most familiar are the concerns centered around selection of a site for a repository; however, the transportation portion of the OCRWM program also engenders similar concerns for safety, efficiency and effectiveness. The major Transportation institutional issues were detailed in the Institutional Plan, issued in 1986, and include topics such as liability, defense waste, routing, emergency response, risk identification and mitigation, cash integrity, inspection and enforcement of high-level waste shipments and use of overweight trucks as part of the modal mix. This paper will define the process being used to identify and resolve institutional issues, show how the technical and institutional issues interface and are addressed, and briefly describe four specific activities which illustrate the process of resolving institutional issues in the Transportation program

  14. The management of radioactive wastes in Canada

    International Nuclear Information System (INIS)

    1979-01-01

    Ten papers are presented, dealing with the management and environmental impact of radioactive wastes, environmental considerations related to uranium mining and milling, the management of uranium refining wastes, reactor waste management, proposals for the disposal of low- and intermediate-level wastes, disposal of nuclear fuel wastes, federal government policy on radioactive waste management, licensing requirements, environmental assessment, and internatioal cooperation in wast management. (LL)

  15. Radioactive waste management and disposal in Australia

    International Nuclear Information System (INIS)

    Harries, J.R.

    1997-01-01

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

  16. 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)

  17. Radioactivity of surface water and freshwater fish in Finland in 1988-1990

    International Nuclear Information System (INIS)

    Saxen, R.; Koskelainen, U.

    1992-02-01

    Changes over time in the activity concentrations of radionuclides in surface water and in the five largest rivers and some smaller rivers discharging into the Baltic Sea were monitored in 1988-1990. The dominant gamma-emitting radionuclides were 137 Cs and 134 Cs. The effect of the uneven distribution of Chernobyl deposition is still seen in the results. The activity concentrations of 137 Cs in surface water have decreased significantly: In the drainage area where the activity concentrations were highest after the Chernobyl accident, the concentrations in October 1990 were only about 1-4% of the maximum values in May 1986. The decrease in the activity concentrations of 90 Sr was much slighter. The study of areal and temporal changes in the activity concentrations of 137 Cs in fish, started in 1986, continued in 1988-1990. In all, about 2400 fish samples from southern and middle Finland (excluding Lappland) were analyzed gammaspectrometrially during these three years. Seventeen different fish species were included in the study. (20 refs., 14 figs., 30 tabs.)

  18. Predisposal of Radioactive Waste from NPP 1000 MWe

    International Nuclear Information System (INIS)

    Suryantoro

    2007-01-01

    Predisposal of radioactive waste from NPP 1000 MW which was planned to be operated in 2016 has been conducted. In this study NPP applying PWR type was assumed. This assessment comprises all aspects of radioactive waste coming from NPP. One through cycle was chosen consequently no reprocessing step will be conducted. The assessment shows that technologically all radioactive waste treatment process rising from NPP operation has similarities to the existing radioactive waste process conducted by RWI which has lower scale of waste amount. (author)

  19. The solidification of radioactive waste

    International Nuclear Information System (INIS)

    Nagaya, Kiichi; Fujimoto, Yoshio; Hashimoto, Yasuo; Nomura, Ichiro

    1985-01-01

    A previous paper covered the decomposition and vitrification of Na 2 SO 4 (the primary component of the liquid waste from BWR) with silica. Now, in order to establish an integrated treatment system for the radioactive waste from BWR, this paper examines the effects of combining incinerator ash and other incinerator wastes with radioactive waste on the durability of the final vitrified products. A bench scale test plat consisting of a waiped file evaporator/dryer, a Joule-heated glass melter and SO 2 absorber was therefore put into operation and run safety for a period of 3000 hours. The combination of the radioactive waste with incinerator ash and the secondary waste of the incinerator was found to make no difference on the durability of the final vitrified products effecting no increase or decrease. Durability similar to that displayed in the beaker tests was proven, with the final vitrified products exhibiting a leaching rate less than 3 x 10 -4 g/cm 2 /day at 95 deg C. (author)

  20. Low-Level Radioactive Waste temporary storage issues

    International Nuclear Information System (INIS)

    1992-04-01

    The Low-Level Radioactive Waste Policy Act of 1980 gave responsibility for the disposal of commercially generated low-level radioactive waste to the States. The Low-Level Radioactive Waste Policy Amendments Act of 1985 attached additional requirements for specific State milestones. Compact regions were formed and host States selected to establish disposal facilities for the waste generated within their borders. As a result of the Low-Level Radioactive Waste Policy Amendments Act of 1985, the existing low-level radioactive waste disposal sites will close at the end of 1992; the only exception is the Richland, Washington, site, which will remain open to the Northwest Compact region only. All host States are required to provide for disposal of low-level radioactive waste by January 1, 1996. States also have the option of taking title to the waste after January 1, 1993, or taking title by default on January 1, 1996. Low-level radioactive waste disposal will not be available to most States on January 1, 1993. The most viable option between that date and the time disposal is available is storage. Several options for storage can be considered. In some cases, a finite storage time will be permitted by the Nuclear Regulatory Commission at the generator site, not to exceed five years. If disposal is not available within that time frame, other options must be considered. There are several options that include some form of extension for storage at the generator site, moving the waste to an existing storage site, or establishing a new storage facility. Each of these options will include differing issues specific to the type of storage sought

  1. The trends of radioactive waste disposal

    International Nuclear Information System (INIS)

    Nomi, Mitsuhiko

    1977-01-01

    The disposal of radioactive wastes instead of their treatment has come to be important problem. The future development of nuclear fuel can not be expected unless the final disposal of nuclear fuel cycle is determined. Research and development have been made on the basis of the development project on the treatment of radioactive wastes published by Japan Atomic Energy Commission in 1976. The high level wastes produced by the reprocessing installations for used nuclear fuel are accompanied by strong radioactivity and heat generation. The most promising method for their disposal is to keep them in holes dug at the sea bottom after they are solidified. Middle or low level wastes are divided into two groups; one contains transuranium elements and the other does not. These wastes are preserved on the ground or in shallow strata, while the safe abandonment into the ground or the sea has been discussed about the latter. The co-operations among nations are necessary not only for peaceful utilization of atomic energy but also for radioactive waste disposal. (Kobatake, H.)

  2. Membrane Treatment of Liquid Salt Bearing Radioactive Wastes

    International Nuclear Information System (INIS)

    Dmitriev, S. A.; Adamovich, D. V.; Demkin, V. I.; Timofeev, E. M.

    2003-01-01

    The main fields of introduction and application of membrane methods for preliminary treatment and processing salt liquid radioactive waste (SLRW) can be nuclear power stations (NPP) and enterprises on atomic submarines (AS) utilization. Unlike the earlier developed technology for the liquid salt bearing radioactive waste decontamination and concentrating this report presents the new enhanced membrane technology for the liquid salt bearing radioactive waste processing based on the state-of-the-art membrane unit design, namely, the filtering units equipped with the metal-ceramic membranes of ''TruMem'' brand, as well as the electrodialysis and electroosmosis concentrators. Application of the above mentioned units in conjunction with the pulse pole changer will allow the marked increase of the radioactive waste concentrating factor and the significant reduction of the waste volume intended for conversion into monolith and disposal. Besides, the application of the electrodialysis units loaded with an ion exchange material at the end polishing stage of the radioactive waste decontamination process will allow the reagent-free radioactive waste treatment that meets the standards set for the release of the decontaminated liquid radioactive waste effluents into the natural reservoirs of fish-farming value

  3. Method of processing radioactive wastes

    International Nuclear Information System (INIS)

    Funabashi, Kiyomi; Sugimoto, Yoshikazu; Kikuchi, Makoto; Yusa, Hideo.

    1979-01-01

    Purpose: To obtain solidified radioactive wastes at high packing density by packing radioactive waste pellets in a container and then packing and curing a thermosetting resin therein. Method: Radioactive liquid wastes are dried into power and subjected to compression molding. The pellets thus obtained are supplied in a predetermined amount from the hopper to the inside of a drum can. Then, thermosetting plastic and a curing agent are filled in the drum can. Gas between the pellets is completely expelled by the intrusion of the thermosetting resin and the curing agent among the pellets. Thereafter, the drum can is heated by a heater and curing is effected. After the curing, the drum can is sealed. (Kawakami, Y.)

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

    International Nuclear Information System (INIS)

    Dziewinska, K.M.

    1998-01-01

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

  5. Collective dose estimates by the marine food pathway from liquid radioactive wastes dumped in the Sea of Japan

    International Nuclear Information System (INIS)

    Togawa, O.; Povinec, P.P.; Pettersson, H.B.L.

    1999-01-01

    IAEA-MEL has been engaged in an assessment programme related to radioactive waste dumping by the former USSR and other countries in the western North Pacific Ocean and its marginal seas. This paper focuses on the Sea of Japan and on estimation of collective doses from liquid radioactive wastes. The results from the Japanese-Korean-Russian joint expeditions are summarized, and collective doses for the Japanese population by the marine food pathway are estimated from liquid radioactive wastes dumped in the Sea of Japan and compared with those from global fallout and natural radionuclides. The collective effective dose equivalents by the annual intake of marine products caught in each year show a maximum a few years after the disposals. The total dose from all radionuclides reaches a maximum of 0.8 man Sv in 1990. Approximately 90% of the dose derives from 137Cs, most of which is due to consumption of fish. The total dose from liquid radioactive wastes is approximately 5% of that from global fallout, the contribution of which is below 0.1% of that of natural 210Po

  6. High-Level Radioactive Waste.

    Science.gov (United States)

    Hayden, Howard C.

    1995-01-01

    Presents a method to calculate the amount of high-level radioactive waste by taking into consideration the following factors: the fission process that yields the waste, identification of the waste, the energy required to run a 1-GWe plant for one year, and the uranium mass required to produce that energy. Briefly discusses waste disposal and…

  7. Management of radioactive wastes of iodine therapy

    International Nuclear Information System (INIS)

    Silva, Andre R.M.; Santos, Helena C.

    2015-01-01

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

  8. Plastic solidification of radioactive wastes

    International Nuclear Information System (INIS)

    Moriyama, Noboru

    1981-01-01

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

  9. Method of solidifying radioactive wastes

    International Nuclear Information System (INIS)

    Maeda, Masahiko; Kira, Satoshi; Watanabe, Naotoshi; Nagaoka, Takeshi; Akane, Junta.

    1982-01-01

    Purpose: To obtain solidification products of radioactive wastes having sufficient monoaxial compression strength and excellent in water durability upon ocean disposal of the wastes. Method: Solidification products having sufficient strength and filled with a great amount of radioactive wastes are obtained by filling and solidifying 100 parts by weight of chlorinated polyethylene resin and 100 - 500 parts by weight of particular or powderous spent ion exchange resin as radioactive wastes. The chlorinated polyethylene resin preferably used herein is prepared by chlorinating powderous or particulate polyethylene resin in an aqueous suspending medium or by chlorinating polyethylene resin dissolved in an organic solvent capable of dissolving the polyethylene resin, and it is crystalline or non-crystalline chlorinated polyethylene resin comprising 20 - 50% by weight of chlorine, non-crystalline resin with 25 - 40% by weight of chlorine being particularly preferred. (Horiuchi, T.)

  10. Radioactive waste management; the realities as against the myths

    International Nuclear Information System (INIS)

    Williams, I.

    1980-01-01

    Nuclear power generation is now an essential requirement for the mankind in the current energy difficulties. The problem of radioactive waste management is arousing the opposition, but it must not inhibit the utilization of nuclear energy. Radioactive waste management concerns the whole course from its occurrence to its final disposal. The purpose of the management is then to protect absolutely the human beings of present and future generations from the danger of radioactivity. Radioactive wastes are varied much in their kinds and natures. While the management technology is nearly all established, the amounts of wastes are increasing. The following matters are described. Definition of radioactive waste management, fundamental strategies of the management, kinds of radioactive wastes, the present situation of radioactive waste management, and problems in the management. (J.P.N.)

  11. CEA and its radioactive wastes

    International Nuclear Information System (INIS)

    Marano, S.

    1999-01-01

    CEA annually produces about 3500 tons of radioactive wastes in its 43 basic nuclear installations. CEA ranks third behind EDF and Cogema. Low-level wastes (A wastes) are sent to ANDRA (national agency for the management of nuclear wastes)whereas medium-level wastes (B wastes) are stored by CEA itself. CEA has checked off its storing places and has set up an installation Cedra to process and store ancient and new nuclear wastes. 3 other installations are planned to operate within 6 years: Agate (Cadarache) will treat liquid effluents, Stella (Saclay) will process liquid wastes that are beta or gamma emitters, and Atena (Marcoule) will treat and store radioactive sodium coming from Phenix reactor and IPSN laboratories. The use of plasma torch for vitrifying wastes is detailed, the management of all the nuclear wastes produced by CEA laboratories and installations is presented. (A.C.)

  12. International energy: Research organizations, 1986--1990

    Energy Technology Data Exchange (ETDEWEB)

    Hendricks, P.; Jordan, S. (eds.) (USDOE Office of Scientific and Technical Information, Oak Ridge, TN (USA))

    1991-03-01

    The International Energy: Research Organizations publication contains the standardized names of energy research organizations used in energy information databases. Involved in this cooperative task are (1) the technical staff of the USDOE Office of Scientific and Technical Information (OSTI) in cooperation with the member countries of the Energy Technology Data Exchange (ETDE) and (2) the International Nuclear Information System (INIS). This publication identifies current organizations doing research in all energy fields, standardizes the format for recording these organization names in bibliographic citations, assigns a numeric code to facilitate data entry, and identifies report number prefixes assigned by these organizations. These research organization names may be used in searching the databases Energy Science Technology'' on DIALOG and Energy'' on STN International. These organization names are also used in USDOE databases on the Integrated Technical Information System. Research organizations active in the past five years, as indicated by database records, were identified to form this publication. This directory includes approximately 34,000 organizations that reported energy-related literature from 1986 to 1990 and updates the DOE Energy Data Base: Corporate Author Entries.

  13. Note from the Radioactive Waste Section

    CERN Multimedia

    TS Department

    2008-01-01

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

  14. Technology applications for radioactive waste minimization

    International Nuclear Information System (INIS)

    Devgun, J.S.

    1994-01-01

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

  15. Electrochemistry and Radioactive Wastes: A Scientific Overview

    Directory of Open Access Journals (Sweden)

    Maher Abed Elaziz

    2015-12-01

    Full Text Available Radioactive wastes are arising from nuclear applications such as nuclear medicine and nuclear power plants. Radioactive wastes should be managed in a safe manner to protect human beings and the environment now and in the future. The management strategy depends on collection, segregation, treatment, immobilization, and disposal. The treatment process is a very important step in which the hazardous materials were converted to a more concentrated, less volume and less movable materials. Electrochemistry is the branch of chemistry in which the passage of electric current was producing a chemical change. Electrochemical treatment of radioactive wastes is widely used all over the world. It has a number of advantages and hence benefits. Electrochemistry can lead to remote, automatic control and increasing safety. The present work is focusing on the role of electrochemistry in the treatment of radioactive wastes worldwide. It contains the fundamentals of electrochemistry, the brief story of radioactive wastes, and the modern trends in the electrochemical treatment of radioactive wastes. An overview of electrochemical decomposition of organic wastes, electrochemical reduction of nitrates, electro- precipitation, electro- ion exchange, and electrochemical remediation of soil are outlined. The main operating factors, the mechanism of decontamination, energy consumption and examples of field trials are considered.

  16. The radiation protection and the radioactive wastes management

    International Nuclear Information System (INIS)

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

    2003-01-01

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

  17. Transport of radioactive waste in Germany - a survey

    International Nuclear Information System (INIS)

    Alter, U.

    1995-01-01

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

  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. Method for solidifying powdery radioactive wastes

    International Nuclear Information System (INIS)

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

    1978-01-01

    Purpose: To solidify powdery radioactive wastes through polymerization in a vessel at a high impregnation speed with no cloggings in pipes. Method: A drum can is lined with an inner liner layer of a predetermined thickness made of inflammable material such as glass fiber. A plurality of pipes for supplying liquid plastic monomer are provided in adjacent to the upper end face of the inflammable material or inserted between the vessel and the inflammable material. Then powdery radioactive wastes are filled in the vessel and the liquid plastic monomer dissolving therein a polymerization initiator is supplied through the pipes. The liquid plastic monomer impregnates through the inflammable material layer into the radioactive wastes and the plastic monomer is polymerized by the aid of the polymerization initiator after a predetermined of time to produce solidified plastic products of radioactive wastes. (Seki, T.)

  20. Issues on safe radioactive waste management at ChNPP site in International Shelter Implementation Plan

    International Nuclear Information System (INIS)

    Bykov, V.; Kilochytska, T.; Gromyko, S.; Kadkin, Y.; Kondratiev, S.; Pavlenko, A.; Bogorinski, P.

    2003-01-01

    The International Shelter Implementation Plan (SIP) [1], is aimed to convert the ChNPP unit 4, destroyed by a beyond-design accident in 1986, into an environmentally safe facility by means of large-scale projects such as stabilization of the existing Sarcophagus (Shelter), construction of a New Safe Confinement (NSC), and installation of engineering and monitoring systems. This report presents some important safety issues concerning radioactive waste (RAW) management at the Shelter. One of the main problems of RAW management is to dispose of large volumes of RAW generated during ground preparation work. It is necessary that RAW be sorted carefully to separate low-active radioactive waste (LLW), which will be the majority, from high-level waste. Considering the fact that the Shelter is in the exclusion zone, the interim storage of LLW in this zone is possible, but a set of safety measures is required, e.g. prevention of dust generation or spreading of radioactivity with water. Another problem is high level RAW management. Highly radioactive fragments of the core, including fuel were ejected during the accident and are now buried under the man-made layer around the Shelter. Unanticipated disclosure of such fragments may happen during any ground preparation work as well as during clearing of premises inside the damaged buildings. Therefore, permanent radiation monitoring is required to prevent any intolerable exposure of workers. Unanticipated disclosure of high-active radioactive waste (HLW) could lead to considerable delay of any work. Since it is particularly difficult to remove HLW from those locations, which can not be easily accessed with removal equipment, such waste needs to be confined and properly shielded at in situ. Due to absence of a permanent HLW storage, an interim storage needs to be provided for in the territory of the Sarcophagus. (author)

  1. ANSTO's radioactive waste management policy. Preliminary environmental review

    International Nuclear Information System (INIS)

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

    1996-05-01

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

  2. Defense radioactive waste management

    International Nuclear Information System (INIS)

    Hindman, T.B. Jr.

    1988-01-01

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

  3. Regulatory body contribution to the development of an integrated radioactive waste management system in the Slovak Republic

    International Nuclear Information System (INIS)

    Konecny, L.; Burclova, J.

    2002-01-01

    The nuclear energy is a very important part of electricity production in the Slovak Republic. Slovakia currently operates 6 nuclear units in two sites and their share on total power production is about 55%. Original soviet design of NPPs operated in Slovakia was based on storage strategy of non-treated solid waste and evaporated liquid waste until decommissioning of the plant. A new approach to the waste management at the end of the 1980s resulted in a strategy to install technologies able to transform in principle all radioactive waste into a form suitable for disposal. The technological part of radioactive waste management was supported in the late 1990s by respective legislation namely by a new act on peaceful use of nuclear energy and by regulation on radioactive waste and spent fuel management. Thus the basis for an integrated radioactive waste management system was created and technical short and long term solutions for the management of all kinds of radioactive waste were prepared. A comprehensive combination of individual components such as legal framework, regulation, overall organization, technology etc. in a single functional system is required for an effective and safe waste management system. Although the waste management system in the Slovak Republic is influenced by historical, socio-political, economic and other factors, a strong regulatory body is one of the key elements of an integrated approach to a generic national system for management of all types of wastes. UJD SR which was appointed as the central state authority for nuclear safety supervision took great effort in its legislative, licensing, assessment and inspection activities with the aim to support this integrated approach. (author)

  4. Method of processing radioactive liquid waste

    International Nuclear Information System (INIS)

    Hasegawa, Akira; Kuribayashi, Hiroshi; Soda, Kenzo; Mihara, Shigeru.

    1988-01-01

    Purpose: To obtain satisfactory plastic solidification products rapidly and smoothly by adding oxidizers to radioactive liquid wastes. Method: Sulfuric acid, etc. are added to radioactive liquid wastes to adjust the pH value of the liquid wastes to less than 3.0. Then, ferrous sulfates are added such that the iron concentration in the liquid wastes is 100 mg/l. Then, after adjusting pH suitably to the drying powderization by adding alkali such as hydroxide, the liquid wastes are dried and powderized. The resultant powder is subjected to plastic solidification by using polymerizable liquid unsaturated polyester resins as the solidifying agent. The thus obtained solidification products are stable in view of the physical property such as strength or water proofness, as well as stable operation is possible even for those radioactive liquid wastes in which the content ingredients are unknown. (Takahashi, M.)

  5. Radioactive waste shredding: Preliminary evaluation

    International Nuclear Information System (INIS)

    Soelberg, N.R.; Reimann, G.A.

    1994-07-01

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

  6. Classification of radioactive wastes produced by the nuclear industry

    International Nuclear Information System (INIS)

    2013-01-01

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

  7. Current status of radioactive waste management in Japan

    International Nuclear Information System (INIS)

    Amanuma, Tsuyoshi

    1985-01-01

    In Japan the nuclear power generation capacity now exceeds the level of 20,000 MW, 24.3 % of the total power generation. It constitutes the major position of energy source, a substitute for a petroleum. In the nuclear power, chemical engineering contributes significantly to treatment and disposal of the radioactive wastes. In the interim report by an ad hoc committee in the Atomic Energy Commission, for the future, rational grouping of the wastes and the direction of land disposal are stated. Contents are the following: basic ideas for the radioactive wastes, radioactive wastes countermeasures in Japan (wastes classification, low and high level and transuranic wastes), radioactive wastes in the nuclear fuel cycle (reactor and fuel reprocessing and reactor dismantling wastes). (Mori, K.)

  8. Offgas treatment for radioactive waste incinerators

    International Nuclear Information System (INIS)

    Stretz, L.A.; Koenig, R.A.

    1980-01-01

    Incineration of radioactive materials for resource recovery or waste volume reduction is recognized as an effective waste treatment method that will increase in usage and importance throughout the nuclear industry. The offgas cleanup subsystem of an incineration process is essential to ensure radionuclide containment and protection of the environment. Several incineration processes and associated offgas cleanup systems are discussed along with potential application of commercial pollution control components to radioactive service. Problems common to radioactive waste incinerator offgas service are identified and areas of needed research and development effort are noted

  9. Disposal of radioactive waste in Romania. Present and future strategy

    International Nuclear Information System (INIS)

    Rodna, A.; Garlea, C.

    2002-01-01

    The paper begins with the presentation of the actual situation of radioactive waste management in Romania. The organizations responsible for radioactive waste management and their capabilities are described, including radioactive waste disposal. The main provisions of the 'Draft law regarding the management of nuclear spent fuel and radioactive waste, in view of their final disposal' are also presented, with accent on the responsibilities of the National Radioactive Waste Agency (ANDRAD) and on the fund for radioactive waste and spent fuel management and for decommissioning. The paper ends with the presentation of the future radioactive waste and spent fuel management strategy. (author)

  10. Disposal of liquid radioactive waste - discharge of radioactive waste waters from hospitals

    International Nuclear Information System (INIS)

    Ludwieg, F.

    1976-01-01

    A survey is given about legal prescriptions in the FRG concerning composition and amount of the liquid waste substances and waste water disposal by emitting into the sewerage, waste water decay systems and collecting and storage of patients excretions. The radiation exposure of the population due to drainage of radioactive waste water from hospitals lower by more than two orders than the mean exposure due to nuclear-medical use. (HP) [de

  11. Technology, socio-political acceptance, and the low-level radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Andrews, L.J.; Domenech, J.S.

    1986-01-01

    The technology which is required to develop and operate low-level radioactive waste disposal sites in the 1990's is available today. The push for best available technology is a response to the political difficulties in securing public acceptance of the site selection process. Advances in waste management technologies include development of High Integrity Containers (HIC), solidification media, liquid volume reduction techniques using GEODE/sub sm/ and DeVoe-Holbein technology of selective removal of target radioisotopes, and CASTOR V storage casks. Advances in technology alone, however, do not make the site selection process easier and without socio-political acceptance there may be no process at all. Chem-Nuclear has been successful in achieving community acceptance at the Barnwell facility and elsewhere. For example, last June in Fall River County, South Dakota, citizens voted almost 2:1 to support the development of a low-level radioactive waste disposal facility. In Edgemont, the city nearest the proposed site, 85% of the voters were in favor of the proposed facility

  12. Indian programme on radioactive waste management

    International Nuclear Information System (INIS)

    Wattal, P.K.

    2013-01-01

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

  13. 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

  14. Ocean disposal of radioactive waste: Status report

    International Nuclear Information System (INIS)

    Calmet, D.P.

    1989-01-01

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

  15. Acceptance criteria for disposal of radioactive waste in Romania

    International Nuclear Information System (INIS)

    Dogaru, D.

    2001-01-01

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

  16. Mechanisms and interaction phenomena influencing releases in a low- and medium-level waste disposal system

    International Nuclear Information System (INIS)

    Brodersen, K.; Nilsson, K.

    1991-01-01

    The report covers work done 1986-1990 at Riso National Laboratory as part of the third EC Research Programme on Radioactive Waste Management. The report is divided into three parts: 1) Waste product characterization: - leaching and volume stability of cemented ion-exchange resins. - Hydroscopic properties of cemented and bituminized radioactive waste. - Water uptake and swelling of bituminized waste, water migration in bitumen membranes and measurements of swelling pressures. - Ageing of bituminized products. 2) Barrier material properties: - The influence of the pore structure in concrete on the hydraulic transport of water and ions through concrete barriers was investigated - Healing of cracks in concrete barriers by precipitation of calcium carbonate was demonstrated experimentally - Transport of components between two thin plates of cement paste with different composition stored together in water - The structure of degraded cement paste was studied using SANS (small angle neutron scattering). 3) Interaction phenomena: - Integral experiments with migration of radioisotopes from cemented waste through barriers made from kaolin, chalk or concrete were made under different external conditions. 51 figs., 15 tabs., 25 refs

  17. Method for processing radioactive wastes containing sodium

    International Nuclear Information System (INIS)

    Kubota, Takeshi.

    1975-01-01

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

  18. BN-350 decommissioning problems of radioactive waste management

    International Nuclear Information System (INIS)

    Galkin, A.; Tkachenko, V.

    2002-01-01

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

  19. Encapsulation of radioactive waste

    International Nuclear Information System (INIS)

    Pordes, O.; Plows, J.P.

    1980-01-01

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

  20. 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

  1. Regulation on radioactive waste management, Governmental Agreement No. 559-98

    International Nuclear Information System (INIS)

    1998-01-01

    This regulation defines the responsibilities on the radioactive waste management in Guatemala including the requirements of users, handling of radioactive wastes, authorization of radioactive waste disposal, transport of radioactive wastes and penalties

  2. Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility

    International Nuclear Information System (INIS)

    Albert, R.

    1992-01-01

    The purpose of this plan is to describe the organization and methodology for the certification of radioactive mixed waste (RMW) handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). RMW is low-level radioactive waste (LLW) or transuranic (TRU) waste that is co-contaminated with dangerous waste as defined in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and the Washington State Dangerous Waste Regulations, 173-303-040 (18). This waste is to be transferred to the Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington. This plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF (Section 4); and a list of the current and planned implementing procedures used in waste certification

  3. Standardization of radioactive waste categories

    International Nuclear Information System (INIS)

    1970-01-01

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

  4. Research programme on radioactive wastes

    International Nuclear Information System (INIS)

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

    2009-11-01

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

  5. Public debate - radioactive wastes management

    International Nuclear Information System (INIS)

    2005-01-01

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

  6. Investigation on design of repository for radioactive waste

    International Nuclear Information System (INIS)

    Zhang Boming; Zhang Ruixue; Wang Fengying

    2010-01-01

    The scheme design of the repository for radioactive waste is introduced according to the traits of radioactive waste in Jiangsu province, such as the style of the repository, lifting facilities, the step for preventing or controlling flood, the aseismatic measure, the pollution prevention and so on. This ensured the radioactive waste and the waste radioactive sources to be stored in security, the area environment not to be polluted. It can improve the use of nuclear technology in Jiangsu province. (authors)

  7. Radioactive waste management

    International Nuclear Information System (INIS)

    Slansky, C.M.

    1975-01-01

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

  8. Waste characterization for radioactive liquid waste evaporators at Argonne National Laboratory - West

    International Nuclear Information System (INIS)

    Christensen, B. D.

    1999-01-01

    Several facilities at Argonne National Laboratory - West (ANL-W) generate many thousand gallons of radioactive liquid waste per year. These waste streams are sent to the AFL-W Radioactive Liquid Waste Treatment Facility (RLWTF) where they are processed through hot air evaporators. These evaporators remove the liquid portion of the waste and leave a relatively small volume of solids in a shielded container. The ANL-W sampling, characterization and tracking programs ensure that these solids ultimately meet the disposal requirements of a low-level radioactive waste landfill. One set of evaporators will process an average 25,000 gallons of radioactive liquid waste, provide shielding, and reduce it to a volume of six cubic meters (container volume) for disposal. Waste characterization of the shielded evaporators poses some challenges. The process of evaporating the liquid and reducing the volume of waste increases the concentrations of RCIU regulated metals and radionuclides in the final waste form. Also, once the liquid waste has been processed through the evaporators it is not possible to obtain sample material for characterization. The process for tracking and assessing the final radioactive waste concentrations is described in this paper, The structural components of the evaporator are an approved and integral part of the final waste stream and they are included in the final waste characterization

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

    International Nuclear Information System (INIS)

    Bujoreanu, C.

    2004-01-01

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

  10. Industrial radioactive wastes: what are we talking about?

    International Nuclear Information System (INIS)

    Le Bars, Y.

    2001-01-01

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

  11. Chemical decontamination method for radioactive metal waste

    International Nuclear Information System (INIS)

    Tanaka, Akio; Onuma, Tsutomu; Yamazaki, Sei; Miura, Haruki.

    1993-01-01

    The present invention provides a chemical decontamination method for radioactive metal wastes, which are generated from radioactive material handling facilities and the surfaces of which are contaminated by radioactive materials. That is, it has a feature of applying acid dissolution simultaneously with mechanical grinding. The radioactive metal wastes are contained in a vessel such as a barrel together with abrasives in a sulfuric acid solution and rotated at several tens rotation per minute. By such procedures for the radioactive metal wastes, (1) cruds and passive membranes are mechanically removed, (2) exposed mother metal materials are uniformly brought into contact with sulfuric acid and further (3) the mother metal materials dissolve the cruds and the passive membranes also chemically by a reducing dissolution (so-called local cell effect). According to the method of the present invention, stainless steel metal wastes having cruds and passive membranes can rapidly and efficiently be decontaminated to a radiation level equal with that of ordinary wastes. (I.S.)

  12. Proceedings of the Korean Radioactive Waste Society Spring 2010

    International Nuclear Information System (INIS)

    2010-01-01

    This proceedings contains articles of the Korean Radioactive Waste Society Spring 2010. It was held on May 13-14, 2010 in Yesan, Korea. The main topics are as follows: Radioactive wastes policy and decontamination and decommissioning, Radioactive waste treatment, Radioactive waste disposal and site selection, Spent fuel and fuel cycle and Radiation safety and environment. (Yi, J. H.)

  13. Step-By-Step: Life Cycle Radioactive Waste Management

    International Nuclear Information System (INIS)

    2014-01-01

    Radioactive waste is an unavoidable by-product when nuclear technologies are used for electricity production and for beneficial practices in medicine, agriculture, research and industry. When the radioactivity of the waste is above a certain threshold, the waste requires special disposal methods. Through extensive research, standards and approaches have been developed for safely and securely preparing for and managing radioactive waste disposal. In the course of its journey from the point of generation to disposal, radioactive waste undergoes a number of predisposal management treatment steps to transform it into a safe, stable and manageable form suitable for transport, storage and disposal

  14. ECOLOGICAL AND TECHNICAL REQUIREMENTS OF RADIOACTIVE WASTE UTILISATION

    Directory of Open Access Journals (Sweden)

    Gabriel Borowski

    2013-01-01

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

  15. Radioactive wastes management: what is the situation?

    International Nuclear Information System (INIS)

    2002-01-01

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

  16. Who regulates the disposal of low-level radioactive waste under the Low-Level Radioactive Waste Policy Act

    International Nuclear Information System (INIS)

    Mostaghel, D.M.

    1988-01-01

    The present existence of immense quantities of low-level nuclear waste, a federal law providing for state or regional control of such waste disposal, and a number of state disposal laws challenged on a variety of constitutional grounds underscore what currently may be the most serious problem in nuclear waste disposal: who is to regulate the disposal of low-level nuclear wastes. This problem's origin may be traced to crucial omissions in the Atomic Energy Act of 1946 and its 1954 amendments (AEA) that concern radioactive waste disposal. Although the AEA states that nuclear materials and facilities are affected with the public interest and should be regulated to provide for the public health and safety, the statute fails to prescribe specific guidelines for any nuclear waste disposal. The Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA) grants states some control over radioactive waste disposal, an area from which they were previously excluded by the doctrine of federal preemption. This Comment discusses the question of who regulates low-level radioactive waste disposal facilities by examining the following: the constitutional doctrines safeguarding federal government authority; area of state authority; grants of specific authority delegations under the LLRWPA and its amendment; and finally, potential problems that may arise depending on whether ultimate regulatory authority is deemed to rest with single states, regional compacts, or the federal government

  17. Managing radioactive waste issues and misunderstandings (radiation realities, energy comparison, waste strategies)

    International Nuclear Information System (INIS)

    Rosen, M.

    2001-01-01

    The technical specialist is confident that radioactive waste can be safely managed, but many in the public remain totally unconvinced. There are issues and deep-seated misunderstandings that drive public doubts. Currently, a growing concern with pollution from other industrial waste is enabling radioactive waste issues to be debated in a wider context that allows comparisons with other potentially hazardous waste, particularly from energy generation sources. Health effects and time period issues are not unique to radioactive waste. This paper concentrates on 3 topics. The first concerns radiation health effects where the real realities of radiation are covered. The large misunderstandings that exist about radiation and its health effects have led to an almost zero health impact regulatory policy. A policy which must be more fully understood and dealt with. The second topic deals with a few revealing comparisons about the various energy generation systems. Nuclear power's 10 thousand fold lower fuel requirements, compared with a comparable fossil fuelled plant, is a dominating factor decisively minimising environmental impacts. The third topic examines waste disposal strategies. Extraordinarily small radioactive waste quantities permit a confinement strategy for disposal as opposed to the more common dispersion strategy for most toxic waste. The small quantities coupled with radioactive decay, contrary to the public perception, make any potential hazard from both low and high level radioactive waste exceedingly small. (author)

  18. Juridical and institutional aspects of radioactive wastes

    International Nuclear Information System (INIS)

    Faria, N.M. de.

    1988-07-01

    The author proposes a discussion of a new branch of the public law - the nuclear law. The main subject is the radioactive waste. Its production is a decisive problem in the utilization of nuclear energy being one of the discussed questions from the technical, economical, political, social and juridical points of view. Countries have been striving to establish their own policies related to radioactive wastes having always in mind the man and the environmental protection. In this scenario the author developed the investigations trying to discuss juridical and institutional aspects of radioactive wastes on the international level as well as in different countries with the aim to establish the juridical basis of a radioactive wastes policy in Brazil [pt

  19. Geological storage of radioactive waste

    International Nuclear Information System (INIS)

    Barthoux, A.

    1983-01-01

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

  20. Must we be afraid by the radioactive waste?

    International Nuclear Information System (INIS)

    2002-01-01

    In the framework of the information on radioactive waste, scientists and politicians give information on the radioactive waste management in France, the researches in the framework of the law of the 30 december 1991, the national agency for the radioactive waste (ANDRA) and its sites. (A.L.B.)

  1. Method for burning radioactive wastes

    International Nuclear Information System (INIS)

    Hattori, Akinori; Tejima, Takaya.

    1987-01-01

    Purpose: To completely process less combustible radioactive wastes with no excess loads on discharge gas processing systems and without causing corrosions to furnace walls. Method: Among combustible radioactive wastes, chlorine-containing less combustible wastes such as chlorine-containing rubbers and vinyl chlorides, and highly heat generating wastes not containing chloride such as polyethylene are selectively packed into packages. While on the other hand, packages of less combustible wastes are charged into a water-cooled jacket type incinerator intermittently while controlling the amount and the interval of charging so that the temperature in the furnace will be kept to lower than 850 deg C for burning treatment. Directly after the completion of the burning, the packed highly heat calorie producing wastes are charged and subjected to combustion treatment. (Yoshihara, H.)

  2. Report on radioactive waste disposal

    International Nuclear Information System (INIS)

    1993-01-01

    The safe management of radioactive wastes constitutes an essential part of the IAEA programme. A large number of reports and conference proceedings covering various aspects of the subject have been issued. The Technical Review Committee on Underground Disposal (February 1988) recommended that the Secretariat issue a report on the state of the art of underground disposal of radioactive wastes. The Committee recommended the need for a report that provided an overview of the present knowledge in the field. This report covers the basic principles associated with the state of the art of near surface and deep geological radioactive waste disposal, including examples of prudent practice, and basic information on performance assessment methods. It does not include a comprehensive description of the waste management programmes in different countries nor provide a textbook on waste disposal. Such books are available elsewhere. Reviewing all the concepts and practices of safe radioactive waste disposal in a document of reasonable size is not possible; therefore, the scope of this report has been limited to cover essential parts of the subject. Exotic disposal techniques and techniques for disposing of uranium mill tailings are not covered, and only brief coverage is provided for disposal at sea and in the sea-bed. The present report provides a list of references to more specialized reports on disposal published by the IAEA as well as by other bodies, which may be consulted if additional information is sought. 108 refs, 22 figs, 2 tabs

  3. Radioactive waste management centers: an approach

    International Nuclear Information System (INIS)

    Lotts, A.L.

    1980-01-01

    Radioactive waste management centers would satisfy the need for a cost-effective, sound management system for nuclear wastes by the industry and would provide a well integrated solution which could be understood by the public. The future demands for nuclear waste processing and disposal by industry and institutions outside the United States Government are such that a number of such facilities are required between now and the year 2000. Waste management centers can be organized around two general needs in the commercial sector: (1) the need for management of low-level waste generated by nuclear power plants, the once-through nuclear fuel cycle production facilities, from hospitals, and other institutions; and (2) more comprehensive centers handling all categories of nuclear wastes that would be generated by a nuclear fuel recycle industry. The basic technology for radioactive waste management will be available by the time such facilities can be deployed. This paper discusses the technical, economic, and social aspects of organizing radioactive waste managment centers and presents a strategy for stimulating their development

  4. Shallow land disposal of radioactive waste

    International Nuclear Information System (INIS)

    1987-01-01

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

  5. High-level radioactive waste disposal problem in Russia

    International Nuclear Information System (INIS)

    Velichkin, Vasily I.

    1999-01-01

    This presentation on radioactive waste management in Russia discusses criteria for the selection of disposal sites, how the various types of waste should be contained and stored, and gives a list showing the liable owner, type, volume, activity and storage place of the present amount of radioactive waste. The bulk of this waste, in volume and radioactivity, is at the enterprises of Minatom of the Russian Federation

  6. 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

  7. Final disposal of radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

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

    1978-08-01

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

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

    International Nuclear Information System (INIS)

    1985-01-01

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

  9. System for disposing of radioactive waste

    International Nuclear Information System (INIS)

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

    1979-01-01

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

  10. System for disposing of radioactive waste

    International Nuclear Information System (INIS)

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

    1977-01-01

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

  11. Hazardous chemical and radioactive wastes at Hanford

    International Nuclear Information System (INIS)

    Keller, J.F.; Stewart, T.L.

    1991-07-01

    The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities have been built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Area to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic (TRU) and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemical as well as radioactive constituents. This paper will focus on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location

  12. Hazardous chemical and radioactive wastes at Hanford

    International Nuclear Information System (INIS)

    Keller, J.F.; Stewart, T.L.

    1993-01-01

    The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities were built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Areas to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemicals as well as radioactive constituents. This paper focuses on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location

  13. Radioactive waste and transport. Chapter 6

    International Nuclear Information System (INIS)

    1978-01-01

    A brief definition of the nature of radioactive waste is followed by a more detailed discussion of high level waste, its composition the amounts involved, storage in liquid and in solid form and the storage of non-reprocessed spent fuel. The final disposal of high level waste in deep geological structures is then described, based on the Swedish KBS study. The effectiveness of the artificial and natural barriers in preventing the radioactive substances from reaching the biosphere is discussed. American and Swedish risk analyses are briefly discussed, and practical experience presented. Low and medium level wastes are thereafter treated in a similar, though briefer manner. Transport of radioactive materials, fresh fuel, spent fuel and waste is then dealt with. Regulations for the containers and their tests are briefly presented and the risk of accidents, theft and sabotage during transport are discussed. (JIW)

  14. Radioactive waste containment

    International Nuclear Information System (INIS)

    Beranger, J.-C.

    1978-01-01

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

  15. Andra. Everything on the management of radioactive wastes

    International Nuclear Information System (INIS)

    2014-08-01

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

  16. Project on effects of gas in underground storage facilities for radioactive waste (Pegasus project)

    International Nuclear Information System (INIS)

    Haijtink, B.; McMenamin, T.

    1993-01-01

    Whereas the subject of gas generation and gas release from radioactive waste repositories has gained in interest on the international scene, the Commission of the European Communities has increased its research efforts on this issue. In particular, in the fourth five-year R and D programme on management and storage of radioactive waste (1990-94), a framework has been set up in which research efforts on the subject of gas generation and migration, supported by the CEC, are brought together and coordinated. In this project, called Pegasus, about 20 organizations and research institutes are involved. The project covers theoretical and experimental studies of the processes of gas formation and possible gas release from the different waste types, LLW, ILW and HLW, under typical repository conditions in suitable geological formations such as clay, salt and granite. In this report the present status of the various research activities are described and 13 papers have been selected

  17. Geotechnical support and topical studies for nuclear waste geologic repositories: Annual report, Fiscal Year 1986

    International Nuclear Information System (INIS)

    1986-11-01

    The multidisciplinary project was initiated in fiscal year 1986. It comprises two major interrelated parts: (1) Technical Assistance. This part of the project includes: (a) review of the progress of major projects in the DOE Office of Civilian Radioactive Waste Management Program and advise the Engineering and Geotechnology Division on significant technical issues facing each project; (b) analyze geotechnical data, reports, tests, surveys and plans for the different projects; (c) review and comment on major technical reports and other program documents such as site characterization plans and area characterization plans and (d) provide scientific and technical input at technical meetings. (2) Topical Studies. This activity comprises studies on scientific and technical topics, and issues of significance to in-situ testing, test analysis methods, and performance assessment of nuclear waste geologic repositories. The subjects of study were selected based on discussions with DOE staff. For fiscal year 1986, one minor and one major area of investigation were undertaken. The minor topic is a preliminary consideration and planning exercise for post-closure monitoring studies. The major topic, with subtasks involving various geoscience disciplines, is on the mechanical, hydraulic, geophysical and geochemical properties of fractures in geologic rock masses. The present report lists the technical reviews and comments made during the fiscal year and summarizes the technical progress of the topical studies

  18. Radioactive waste processing method

    International Nuclear Information System (INIS)

    Sakuramoto, Naohiko.

    1992-01-01

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

  19. 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

  20. 40 CFR 147.3005 - Radioactive waste injection wells.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 22 2010-07-01 2010-07-01 false Radioactive waste injection wells. 147... the Navajo, Ute Mountain Ute, and All Other New Mexico Tribes § 147.3005 Radioactive waste injection... dispose of radioactive waste (as defined in 10 CFR part 20, appendix B, table II, but not including high...

  1. Ocean abandonment of radioactive waste. 2

    International Nuclear Information System (INIS)

    Kouyama, Hiroaki

    1994-01-01

    Now, the nuclear powered submarines armed with ballistic missiles have become the main strength of navy. In Russia, eight nuclear powered icebreakers are operated. Mainly PWRs are used for these nuclear ships. The fuel exchange for nuclear powered submarines is carried out after the use for nearly ten years, therefore, the degree of enrichment of U-235 in fuel seems considerably high. So far, the sinking accidents of five nuclear powered submarines were reported. Former USSR began the ocean abandonment of radioactive waste in 1959, and continued it up to recent date. The northern sea area where the abandonment was carried out and the abandoned amount of radioactivity are shown. Also those in Far East sea area are shown. The management system for radioactive waste in Russia, the course after the abandonment of liquid waste in Japan Sea by Russian navy, the response of Japan regarding the ocean abandonment of radioactive waste and so on are described. (K.I.)

  2. Processing method for radioactive liquid waste

    International Nuclear Information System (INIS)

    Yasumura, Keijiro

    1991-01-01

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

  3. Application of two-barrier model of radioactive agent transport in sea water for analyzing artificial radionuclide release from containers with radioactive waste dumped in Kara Sea

    Energy Technology Data Exchange (ETDEWEB)

    Grishin, Denis S.; Laykin, Andrey I.; Kuchin, Nickolay L.; Platovskikh, Yuri A. [Krylov State Research Center, Saint Petersburg, 44 Moskovskoe shosse, 196158 (Russian Federation)

    2014-07-01

    Modeling of artificial radionuclide transport in sea water is crucial for prognosis of radioecological situation in regions where dumping of radioactive waste had been made and/or accidents with nuclear submarines had taken place. Distribution of artificial radionuclides in bottom sediments can be a detector of radionuclide release from dumped or sunk objects to marine environment. Proper model can determine the dependence between radionuclide distribution in sediments and radionuclide release. Following report describes two-barrier model of radioactive agent transport in sea water. It was tested on data from 1994 - 2013 expeditions to Novaya Zemlya bays, where regular dumping of solid radioactive waste was practiced by the former USSR from the early 1960's until 1990. Two-barrier model agrees with experimental data and allows more accurate determination of time and intensity of artificial radionuclide release from dumped containers. (authors)

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

    International Nuclear Information System (INIS)

    2001-06-01

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

  5. Radioactive waste management for reactors

    International Nuclear Information System (INIS)

    Rodger, W.A.

    1974-01-01

    Radioactive waste management practices at nuclear power plants are summarized. The types of waste produced and methods for treating various types of wastes are described. The waste management systems, including simplified flow diagrams, for typical boiling water reactors and pressurized water reactors are discussed. (U.S.)

  6. Safety disposal studies of radioactive and hazardous wastes using cement

    International Nuclear Information System (INIS)

    Aly, M.M.E.

    2000-01-01

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

  7. Mental Models of Radioactivity and Attitudes towards Radioactive Waste

    International Nuclear Information System (INIS)

    Zeleznik, N.

    2010-01-01

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

  8. Purification of radioactive waste oil by a supercritical fluid

    International Nuclear Information System (INIS)

    Yoo, Jaeryong; Sung, Jinhyun; Park, Kwangheon; Kim, Hongdoo; Kim, Hakwon; Lim, Taeyoon; Yim, Sanghak; Yoon, Weonseob

    2006-01-01

    The radioactive waste oil from the nuclear industry is potentially hazardous due to its possibility to contaminate soil and underwater. Pollutants in waste oil are generally radioactive heavy metals or organo-metals. Radioactive waste oils are highly viscous fluids that are similar to used-motor oils. Several processes have been developed to regenerated used motor oil, such as acid clay treatment, chemical addition, vacuum distillation, thermal cracking and hydrofinishing. However, these technologies are difficult to apply to separating radioactive nuclides from radioactive waste oils. In recent years, our laboratory developed a membrane method for the regeneration of used motor oils. We applied supercritical Co2 (scCO2) as a viscosity reducing additive to waste oils at a lower process temperature in order to improve membrane permeability and thus the energy saving. However, the membrane cannot filter the contaminants in radioactive waste oil that are not particles, such as radioactive ions in impurity water in the oil. In this paper, we suggest a method extracting clean oil from the radioactive waste oil rather than filtering by a supercritical fluid. We selected R22, a refrigerant, as a solvent for extraction. R22 has a mild critical point - 96.1 .deg. and 49.9bar. Regeneration of waste oils by extracting clean oil using a supercritical fluid such as R22 is easy to handle and reduce secondary wastes. In this paper, we examine the feasibility of R22 in extracting clean oil from radioactive waste oils

  9. Transportation of radioactive wastes from nuclear fuel cycles

    International Nuclear Information System (INIS)

    1979-09-01

    This paper discusses current and foreseen radioactive waste transportation systems as they apply to the INFCE Working Group 7 study. The types of wastes considered include spent fuel, which is treated as a waste in once-through fuel cycles; high-, medium-, and low-level waste; and gaseous waste. Regulatory classification of waste quantities and containers applicable to these classifications are discussed. Radioactive wastes are presently being transported in a safe and satisfactory manner. None of the INFCE candidate fuel cycles pose any extraordinary problems to future radioactive waste transportation and such transportation will not constitute a decisive factor in the choice of a preferred fuel cycle

  10. Low-level radioactive waste processing at nuclear power plants

    International Nuclear Information System (INIS)

    1992-12-01

    The Solid Radwaste Processing Source Book is presented as a supplement to the Liquid Radwaste Source Book released in 1990 and updated in 1991. The publication is the result of an industry-wide survey, and is intended as a resource for technical and managerial decisions involving of the processing of solid radioactive waste including ''wet'' and ''dry'' active waste as found at both Pressurized and Boiling Water Reactor sites. In addition to information on processes, vendors, volumes, and in-plant management activities, technology under consideration for future use and computer applications are listed. Together with key personnel and contact information contained in the Liquid Source Books, the collected data will be of great use when seeking specific, unbiased experience on which to base decisions related to so processing, disposal policy, or potential economic and regulatory impact

  11. Operation of low-level radioactive waste incinerator

    International Nuclear Information System (INIS)

    Choi, E.C.; Drolet, T.S.; Stewart, W.B.; Campbell, A.V.

    1979-01-01

    Ontaro Hydro's radioactive waste incinerator designed to reduce the volume of low-level combustible wastes from nuclear generating station's was declared in-service in September 1977. Hiterto about 1500 m 3 of combustible waste have been processed in over 90 separate batches. The process has resulted in 40:1 reduction in the volume and 12.5:1 reduction in the weight of the Type 1 wastes. The ultimate volume reduction factor after storage is 23:1. Airborne emissions has been maintained at the order of 10 -3 to 10 -5 % of the Derived Emission Limits. Incineration of radioactive combustible wastes has been proven feasible, and will remain as one of the most important processes in Ontario Hydro's Radioactive Waste Management Program

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-10-15

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

  13. 2009 National inventory of radioactive material and wastes. In short

    International Nuclear Information System (INIS)

    2009-01-01

    This booklet gives a summary of the national inventory report on radioactive wastes that are present on the French territory (as recorded until december, 2007). Intended for public information, the booklet explains the basics of radioactive materials and wastes and waste management, and gives some data on present and future waste volumes, information about radioactive waste classification, the geographical distribution of waste sites in France, etc. The various types of radioactive wastes are described (classified by their lifetime and activity level) as well as historical storage sites, polluted areas where wastes are stored, radioactive objects, etc. and their respective management approaches are presented

  14. ''New ' technology of solidification of liquid radioactive waste'

    International Nuclear Information System (INIS)

    Sytyl, V.A.; Svistova, L.M.; Spiridonova, V.P.

    1998-01-01

    It is generally accepted that the best method of processing of radioactive waste is its solidification and then storage. At present time, three methods of solidification of radioactive waste are widely used in the world: cementation, bituminous grouting and vitrification. But they do not solve the problem of ecologically processing of waste because of different disadvantages. General disadvantages are: low state of filling, difficulties in solidification of the crystalline hydrated forms of radioactive waste; particular sphere of application and economical difficulties while processing the great volume of waste. In connection with it the urgent necessity is emerging: to develop less expensive and ecologically more reliable technology of solidification of radioactive waste. A new method of solidification is presented with its technical schema. (N.C.)

  15. Management of radioactive wastes with negligible heat generation

    International Nuclear Information System (INIS)

    Alter, U.

    1990-01-01

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

  16. Radioactive waste from non-power applications in Sweden

    International Nuclear Information System (INIS)

    Haegg, Ann-Christin; Lindbom, Gunilla; Persson, Monica

    2001-01-01

    Full text: The system for handling of radioactive waste from the Nuclear Fuel Cycle in Sweden is well established and has been in use for many years. Radioactive waste from other sources is not always handled as rigorously. The Swedish Radiation Protection Institute, SSI has identified the issue and therefore initiated a study with the aim to achieve a sufficient system for handling and disposal of radioactive waste from all sources of radioactive waste. In this paper we discuss some of the sources of radioactive waste and the specific problems they represent. We give a brief description on how they are regulated and handled today and identify some interesting issues. Conventional industry, hospitals, research and education: In the conventional industry the use of different types of radioactive sources is common. The size and type of radioactive source depends on the application (from some megaBq up to thousands of terraBq). The radioactive waste from hospitals, research institutions and pharmaceutical or bio-technical industries consists mainly of very short-lived radionuclides. Also most sealed sources used in the medical field contains short-lived radionuclides. According to the Swedish Radiation Protection Act a licence is needed for the use of sealed sources exceeding 50 kiloBq. For hospitals and research institutes the SSI issues one license covering all radioactive sources below 500 megaBq up to a summary limit depending on the application. All sources with activity exceeding 500 megaBq require a separate license. SSI has issued about 2500 licences. For each licence an annual fee is paid to the SSI. When the radioactive source has fulfilled its purpose the licensee is obliged to inform the SSI that the source is no longer in use and show a certificate from the recognised waste facility. Not until this has been done the licensee is released from its responsibilities. SSI has issued regulations on Radioactive Waste Not Associated with Nuclear Energy. These

  17. Treatment and disposal of radioactive wastes and countermeasures

    International Nuclear Information System (INIS)

    Nomura, Kiyoshi

    1990-01-01

    The treatment and disposal of radioactive wastes are one of important subjects, together with the development of dismantling techniques accompanying the decommissioning measures for nuclear power plants and the development of reprocessing techniques for nuclear fuel cycle. About 25 years have elapsed since the beginning of commercial nuclear power generation in 1966, and the time that the solution of the problems of waste treatment and disposal must be tackled on full scale has come. The features and the amount of generation of radioactive wastes, the way of thinking on the treatment and disposal, and the present status of the treatment and disposal are outlined. For securing the stable supply of energy and solving the environmental problem of the earth such as acid rain and warming, nuclear power generation accomplishes important roles. The objective of waste treatment is based on the way of thinking of 'as low as reasonably achievable (ALARA)'. The radioactive wastes are classified into alpha waste and beta-gamma waste. The present status of RI wastes, the techniques of treating radioactive wastes, the nuclide separation, extinction treatment and the disposal in strata of high level radioactive wastes and the disposal of low level wastes are reported. (K.I.)

  18. Radioactive waste treatment technology at Czech nuclear power plants

    International Nuclear Information System (INIS)

    Kulovany, J.

    2001-01-01

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

  19. Hanford's Radioactive Mixed Waste Disposal Facility

    International Nuclear Information System (INIS)

    McKenney, D.E.

    1995-01-01

    The Radioactive Mixed Waste Disposal Facility, is located in the Hanford Site Low-Level Burial Grounds and is designated as Trench 31 in the 218-W-5 Burial Ground. Trench 31 is a Resource Conservation and Recovery Act compliant landfill and will receive wastes generated from both remediation and waste management activities. On December 30, 1994, Westinghouse Hanford Company declared readiness to operate Trench 31, which is the Hanford Site's (and the Department of Energy complex's) first facility for disposal of low-level radioactive mixed wastes

  20. Extended storage of low-level radioactive waste: potential problem areas

    International Nuclear Information System (INIS)

    Siskind, B.; Dougherty, D.R.; MacKenzie, D.R.

    1985-01-01

    If a state or state compact does not have adequate disposal capacity for low-level radioactive waste (LLRW) by 1986 as required by the Low-Level Waste Policy Act, then extended storage of certain LLRW may be necessary. The issue of extended storage of LLRW is addressed in order to determine for the Nuclear Regulatory Commission the areas of concern and the actions recommended to resolve these concerns. The focus is on the properties and behavior of the waste form and waste container. Storage alternatives are considered in order to characterize the likely storage environments for these wastes. The areas of concern about extended storage of LLRW are grouped into two categories: 1. Behavior of the waste form and/or container during storage, e.g., radiolytic gas generation, radiation-enhanced degradation of polymeric materials, and corrosion. 2. Effects of extended storage on the properties of the waste form and/or container that are important after storage (e.g., radiation-induced oxidative embrittlement of high-density polyethylene and the weakening of steel containers resulting from corrosion by the waste). The additional information and actions required to address these concerns are discussed and, in particular, it is concluded that further information is needed on the rates of corrosion of container material by Class A wastes and on the apparent dose-rate dependence of radiolytic processes in Class B and C waste packages. Modifications to the guidance for solidified wastes and high-integrity containers in NRC's Technical Position on Waste Form are recommended. 27 references