WorldWideScience

Sample records for annual radioactive waste

  1. Annual radioactive waste tank inspection program -- 1993

    International Nuclear Information System (INIS)

    Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1993 to evaluate these vessels, and evaluations based on data accrued by inspections made since the tanks were constructed, are the subject of this report. The 1993 inspection program revealed that the condition of the Savannah River Site waste tanks had not changed significantly from that reported in the previous annual report. No new leaksites were observed. No evidence of corrosion or materials degradation was observed in the waste tanks. However, degradation was observed on covers of the concrete encasements for the out-of-service transfer lines to Tanks 1 through 8

  2. ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM - 2011

    Energy Technology Data Exchange (ETDEWEB)

    West, B.; Waltz, R.

    2012-06-21

    Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2011 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2011 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2011-00026, HLW Tank Farm Inspection Plan for 2011, were completed. Ultrasonic measurements (UT) performed in 2011 met the requirements of C-ESR-G-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 25, 26 and 34 and the findings are documented in SRNL-STI-2011-00495, Tank Inspection NDE Results for Fiscal Year 2011, Waste Tanks 25, 26, 34 and 41. A total of 5813 photographs were made and 835 visual and video inspections were performed during 2011. A potential leaksite was discovered at Tank 4 during routine annual inspections performed in 2011. The new crack, which is above the allowable fill level, resulted in no release to the environment or tank annulus. The location of the crack is documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.6.

  3. ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2008

    Energy Technology Data Exchange (ETDEWEB)

    West, B.; Waltz, R.

    2009-06-11

    Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2008 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report.

  4. Annual Radioactive Waste Tank Inspection Program - 1997

    International Nuclear Information System (INIS)

    Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1997 to evaluate these vessels, and evaluations based on data accrued by inspections performed since the tanks were constructed are the subject of this report

  5. ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2009

    Energy Technology Data Exchange (ETDEWEB)

    West, B.; Waltz, R.

    2010-06-21

    Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2009 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2009 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per LWO-LWE-2008-00423, HLW Tank Farm Inspection Plan for 2009, were completed. All Ultrasonic measurements (UT) performed in 2009 met the requirements of C-ESG-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 1, and WSRC-TR-2002-00061, Rev.4. UT inspections were performed on Tank 29 and the findings are documented in SRNL-STI-2009-00559, Tank Inspection NDE Results for Fiscal Year 2009, Waste Tank 29. Post chemical cleaning UT measurements were made in Tank 6 and the results are documented in SRNL-STI-2009-00560, Tank Inspection NDE Results Tank 6, Including Summary of Waste Removal Support Activities in Tanks 5 and 6. A total of 6669 photographs were made and 1276 visual and video inspections were performed during 2009. Twenty-Two new leaksites were identified in 2009. The locations of these leaksites are documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.4. Fifteen leaksites at Tank 5 were documented during tank wall/annulus cleaning activities. Five leaksites at Tank 6 were documented during tank wall/annulus cleaning activities. Two new leaksites were identified at Tank 19 during waste removal activities. Previously documented leaksites were reactivated at Tanks 5 and 12 during waste removal activities. Also, a very small amount of additional leakage from a previously identified leaksite at Tank 14 was observed.

  6. ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2010

    Energy Technology Data Exchange (ETDEWEB)

    West, B.; Waltz, R.

    2011-06-23

    Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2010 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2010 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2009-00138, HLW Tank Farm Inspection Plan for 2010, were completed. Ultrasonic measurements (UT) performed in 2010 met the requirements of C-ESG-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 30, 31 and 32 and the findings are documented in SRNL-STI-2010-00533, Tank Inspection NDE Results for Fiscal Year 2010, Waste Tanks 30, 31 and 32. A total of 5824 photographs were made and 1087 visual and video inspections were performed during 2010. Ten new leaksites at Tank 5 were identified in 2010. The locations of these leaksites are documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.5. Ten leaksites at Tank 5 were documented during tank wall/annulus cleaning activities. None of these new leaksites resulted in a release to the environment. The leaksites were documented during wall cleaning activities and the waste nodules associated with the leaksites were washed away. Previously documented leaksites were reactivated at Tank 12 during waste removal activities.

  7. ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM- 2007

    Energy Technology Data Exchange (ETDEWEB)

    West, B; Ruel Waltz, R

    2008-06-05

    Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. The 2007 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. A very small amount of material had seeped from Tank 12 from a previously identified leaksite. The material observed had dried on the tank wall and did not reach the annulus floor. A total of 5945 photographs were made and 1221 visual and video inspections were performed during 2007. Additionally, ultrasonic testing was performed on four Waste Tanks (15, 36, 37 and 38) in accordance with approved inspection plans that met the requirements of WSRC-TR-2002- 00061, Revision 2 'In-Service Inspection Program for High Level Waste Tanks'. The Ultrasonic Testing (UT) In-Service Inspections (ISI) are documented in a separate report that is prepared by the ISI programmatic Level III UT Analyst. Tanks 15, 36, 37 and 38 are documented in 'Tank Inspection NDE Results for Fiscal Year 2007'; WSRC-TR-2007-00064.

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    This is the second Annual Report on the activities and expenditures of the Office of Civilian Radioactive Waste Management (OCRWM) and covers the fiscal year ending September 30, 1984. Research over the past 30 years has shown that high-level radioactive waste and spent nuclear fuel can be safely disposed of in geologic repositories. This report provides an overview of the OCRWM organization. The specific accomplishments of the Office are presented. The Office's financial statements for fiscal years 1983 and 1984 are included, and a concluding chapter updates the report with a brief summary of key accomplishments since the end of fiscal year 1984. 9 figs., 5 tabs

  10. Nineteenth annual report of the Radioactive Waste Management Advisory Committee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-08-01

    This report includes a review of the RWMAC's work in 1998-1999 and its work programme and further it presents operational and administrative issues; future work programme; the Select Committee enquiry and the development of future policy. The document discusses issues on achieving a consensus and research on long-term management of radioactive waste; radioactive waste management at the UKAEA Dounreay Nuclear Site; radioactive particles at UKAEA Dounreay; radioactive contamination of pigeons from BNFL Sellafield; authorisations for the disposal and discharge of radioactive wastes; implementation of the basic safety standards directive; small users of radioactive materials.

  11. Hanford Site annual dangerous waste report: Volume 2, Generator dangerous waste report, radioactive mixed waste

    International Nuclear Information System (INIS)

    This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, waste number, waste designation, weight, and waste designation

  12. Hanford Site annual dangerous waste report: Volume 4, Waste Management Facility report, Radioactive mixed waste

    International Nuclear Information System (INIS)

    This report contains information on radioactive mixed wastes at the Hanford Site. Information consists of shipment date, physical state, chemical nature, waste description, handling method and containment vessel, waste number, waste designation and amount of waste

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

    International Nuclear Information System (INIS)

    This is the fifth Annual Report to Congress by the Office of Civilian Radioactive Waste Management (OCRWM). The report covers the activities and expenditures of OCRWM during fiscal year 1987, which ended on September 30, 1987. The activities and accomplishments of OCRWM during fiscal year 1987 are discussed in chapters 1 through 9 of this report. The audited financial statements of the Nuclear Waste Fund are provided in chapter 10. Since the close of the fiscal year, a number of significant events have occurred. Foremost among them was the passage of the Nuclear Waste Policy Amendments Act of 1987 (Amendments Act) on December 21, 1987, nearly 3 months after the end of the fiscal year covered by this report. As a result, some of the plans and activities discussed in chapters 1 through 9 are currently undergoing significant change or are being discontinued. Most prominent among the provisions of the Amendments Act is the designation of Yucca Mountain, Nevada, as the only candidate first repository site to be characterized. Therefore, the site characterization plans for Deaf Smith, Texas, and Hanford, Washington, discussed in chapter 3, will not be issued. The refocusing of the waste management program under the Amendments Act is highlighted in the epilogue, chapter 11. 68 refs., 7 figs., 7 tabs

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

    International Nuclear Information System (INIS)

    This is the third annual report on the activities and expenditures of the Office of Civilian Radioactive Waste Management (OCRWM) and covers the period from October 1, 1984 through September 30, 1985. The following were among the most significant accomplishments during FY 1985: publication of the mission plan; creation of a systems integration capability; publication of draft environmental assessments; development of a program management system and implementation of a comprehensive approach of ''managing for quality'' in all program activities; and development of new initiatives and more consistent interactions in the area of institutional relationships. The Office's financial statements for fiscal years 1984 and 1985 are included, and a concluding chapter updates the report with a brief summary of highlights of accomplishments following the end of fiscal year 1985. 96 refs., 10 figs., 5 tabs

  15. Annual Report of Radioactive Waste Facilities Operation in 2013

    Institute of Scientific and Technical Information of China (English)

    DU; Hong-ming; GAO; Zhi-gang; LIU; Fu-guo

    2013-01-01

    301,a section of Department of Radiochemistry,which manages 15 facilities and undertakes the administrative tasks of radioactive waste,is the important guarantee of scientific research production and safety in CIAE.1 The safe operation of the radioactive waste management facilities In 2013,in order to ensure the operation safety,we formulated the inspection regulations,which included regular operation inspection,week safety inspection from the leaders of the section and

  16. Thirteenth annual U.S. DOE low-level radioactive waste management conference: Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-12-31

    The 40 papers in this document comprise the proceedings of the Department of Energy`s Thirteenth Annual Low-Level Radioactive Waste Management Conference that was held in Atlanta, Georgia, on November 19--21, 1991. General subjects addressed during the conference included: disposal facility design; greater-than-class C low-level waste; public acceptance considerations; waste certification; site characterization; performance assessment; licensing and documentation; emerging low-level waste technologies; waste minimization; mixed waste; tracking and transportation; storage; and regulatory changes. Papers have been processed separately for inclusion on the data base.

  17. Radioactive Wastes.

    Science.gov (United States)

    Choudri, B S; Baawain, Mahad

    2016-10-01

    Papers reviewed herein present a general overview of radioactive waste activities around the world in 2015. These include safety assessments, decommission and decontamination of nuclear facilities, fusion facilities, transportation and management solutions for the final disposal of low and high level radioactive wastes (LLW and HLW), interim storage and final disposal options for spent fuel (SF), and tritiated wastes, with a focus on environmental impacts due to the mobility of radionuclides in water, soil and ecosystem alongwith other progress made in the management of radioactive wastes. PMID:27620100

  18. Radioactive Wastes.

    Science.gov (United States)

    Choudri, B S; Baawain, Mahad

    2015-10-01

    Papers reviewed herein present a general overview of radioactive waste activities around the world in 2014. These include safety assessments, decommission and decontamination of nuclear facilities, fusion facilities, transportation and management solutions for the final disposal of low and high level radioactive wastes (LLW and HLW), interim storage and final disposal options for spent fuel (SF), and tritiated wastes, with a focus on environmental impacts due to the mobility of radionuclides in water, soil and ecosystem alongwith other progress made in the management of radioactive wastes. PMID:26420096

  19. Radioactive Wastes.

    Science.gov (United States)

    Choudri, B S; Baawain, Mahad

    2016-10-01

    Papers reviewed herein present a general overview of radioactive waste activities around the world in 2015. These include safety assessments, decommission and decontamination of nuclear facilities, fusion facilities, transportation and management solutions for the final disposal of low and high level radioactive wastes (LLW and HLW), interim storage and final disposal options for spent fuel (SF), and tritiated wastes, with a focus on environmental impacts due to the mobility of radionuclides in water, soil and ecosystem alongwith other progress made in the management of radioactive wastes.

  20. OCRWM annual report to Congress FY 1999 [USDOE Office of Civilian Radioactive Waste Management

    Energy Technology Data Exchange (ETDEWEB)

    None

    2000-05-01

    During Fiscal Year 1999, the Office of Civilian Radioactive Waste Management (OCRWM) continued to make significant progress in its characterization of the Yucca Mountain, Nevada, candidate geologic repository site. Although OCRWM's appropriation for Fiscal Year 1999 was lower than requested, the Program accomplished all three success measures in the Secretary's Fiscal Year 1999 Performance Agreement with the President and completed important work in many other areas. This Annual Report reviews this work and looks toward future activities.

  1. OCRWM annual report to Congress FY 1999 [USDOE Office of Civilian Radioactive Waste Management

    International Nuclear Information System (INIS)

    During Fiscal Year 1999, the Office of Civilian Radioactive Waste Management (OCRWM) continued to make significant progress in its characterization of the Yucca Mountain, Nevada, candidate geologic repository site. Although OCRWM's appropriation for Fiscal Year 1999 was lower than requested, the Program accomplished all three success measures in the Secretary's Fiscal Year 1999 Performance Agreement with the President and completed important work in many other areas. This Annual Report reviews this work and looks toward future activities

  2. 1992 annual report on low-level radioactive waste management progress

    International Nuclear Information System (INIS)

    This report summarizes the progress States and compact regions made during 1992 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 1992 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

  3. Radioactive wastes

    International Nuclear Information System (INIS)

    Here are gathered 1)the decrees (99-686 and 99-687) of the 3 rd of August 1999 relative to the researches on radioactive waste management. A local committee of information and follow-up has to be established on the site of each underground facility. The composition of this committee is determined here (99-686). 3 people will from now on be jointly ordered by the Minister of Economy, Finance and Industry and by the Secretary of State of Industry to conduct a preliminary dialogue for the choice of one or several sites on which previous works should be made before the construction of an underground facility (99-687). They take the opinion of the people's representatives, the associations and the concerned population and inform the Ministers of Environment, Energy and Research of the collected information. 2)the decree of the 3 rd of August 1999 authorizing the 'Agence nationale pour la gestion des dechets radioactifs' (ANDRA) to install and exploit an underground facility located in Bure (Meuse) and intended to study the deep geological deposits where could be stored radioactive wastes. (O.M.)

  4. 1996 annual report on low-level radioactive waste management progress. Report to Congress

    International Nuclear Information System (INIS)

    This report is prepared in response to the Low-Level Radioactive Waste Policy Act (the Act), Public Law 96-573, 1980, as amended by the Low-Level Radioactive Waste Policy Amendments Act of 1985, Public Law 99-240. The report summarizes the activities during calendar year 1996 related to the establishment of new disposal facilities for commercially-generated low-level radioactive waste. The report emphasizes significant issues and events that have affected progress in developing new disposal facilities, and also includes an introduction that provides background information and perspective on US policy for low-level radioactive waste disposal

  5. 1989 Annual report on low-level radioactive waste management progress

    International Nuclear Information System (INIS)

    This report summarizes the progress during 1989 of states and compacts in establishing new low-level radioactive waste disposal facilities. It also provides summary information on the volume of low-level waste received for disposal in 1989 by commercially operated low-level waste disposal facilities. This report is in response to Section 7(b) of Title I of Public Law 99--240, the Low-Level Radioactive Waste Policy Amendments Act of 1985. 2 figs., 5 tabs

  6. Annual Report - FY 2001, Radioactive Waste Shipments To and From the Nevada Test Site, February 2002; TOPICAL

    International Nuclear Information System (INIS)

    In February 1997, the U.S. Department of Energy, National Nuclear Security Administration Nevada Operations Office (NNSA/NV) issued the Mitigation Action Plan which addressed potential impacts described in the ''Final Environmental Impact Statement for the Nevada Test Site and Off-Site Locations in the State of Nevada'' (DOE/EIS 0243). NNSA/NV committed to several actions, including the preparation of an annual report, which summarizes waste shipments to and from the Nevada Test Site (NTS) Radioactive Waste Management Sites (RWMSs) at Area 3 and Area 5. This document satisfies requirements with regard to low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) transported to or from the NTS during fiscal year (FY 2001)

  7. Annual Treatment Operation Report of Radioactive Liquid Waste in Temporary Storage

    Institute of Scientific and Technical Information of China (English)

    DU; Hong-ming; LIU; Fu-guo; WANG; Jian-xin; DU; Guang-fei; LI; Wei

    2013-01-01

    This project got the official reply formally in 2011.2013 was the second running year that to treat the radioactive liquid waste in the temporary storage.The main task was cement solidification and evaporation treatment of the radioactive wastewater.The task of each running node had completed

  8. Radioactive waste management

    International Nuclear Information System (INIS)

    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

  9. Radioactive waste management

    International Nuclear Information System (INIS)

    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.)

  10. Toxic Substances Control Act (TSCA) Polychlorinated Biphenyl (PCB)/Radioactive Waste Annual Inventory for Calendar Year 2014

    Energy Technology Data Exchange (ETDEWEB)

    Layton, Deborah L. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-06-01

    The Toxic Substances Control Act, 40 CFR 761.65(a)(1) provides an exemption from the one year storage time limit for PCB/radioactive waste. PCB/radioactive waste may exceed the one year time limit provided that the provisions at 40 CFR 761.65(a)(2)(ii) and 40 CFR 761.65(a)(2)(iii) are followed. These two subsections require, (ii) "A written record documenting all continuing attempts to secure disposal is maintained until the waste is disposed of" and (iii) "The written record required by subsection (ii) of this section is available for inspection or submission if requested by EPA." EPA Region 10 has requested the Department of Energy (DOE) to submit an inventory of radioactive-contaminated PCB waste in storage at the Idaho National Laboratory (INL) for the previous calendar year. The annual inventory is separated into two parts, INL without Advanced Mixed Waste Treatment Project (AMWTP) (this includes Battelle Energy Alliance, LLC, CH2M-WG Idaho, LLC, and the Naval Reactors Facility), and AMWTP.

  11. Toxic Substances Control Act (TSCA) Polychlorinated Biphenyl (PCB)/Radioactive Waste Annual Inventory for Calendar Year 2013

    Energy Technology Data Exchange (ETDEWEB)

    no author on report

    2014-06-01

    The Toxic Substances Control Act, 40 CFR 761.65(a)(1) provides an exemption from the one year storage time limit for PCB/radioactive waste. PCB/radioactive waste may exceed the one year time limit provided that the provisions at 40 CFR 761.65(a)(2)(ii) and 40 CFR 761.65(a)(2)(iii) are followed. These two subsections require, (ii) "A written record documenting all continuing attempts to secure disposal is maintained until the waste is disposed of" and (iii) "The written record required by subsection (ii) of this section is available for inspection or submission if requested by EPA." EPA Region 10 has requested the Department of Energy (DOE) to submit an inventory of radioactive-contaminated PCB waste in storage at the Idaho National Laboratory (INL) for the previous calendar year. The annual inventory is separated into two parts, INL without Advanced Mixed Waste Treatment Project (AMWTP) (this includes Battelle Energy Alliance, LLC, CH2M-WG Idaho, LLC, and the Naval Reactors Facility), and AMWTP.

  12. Office of Civilian Radioactive Waste Management fiscal year 1996 annual report to Congress

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    In Fiscal Year 1996 a revised program strategy was developed that reflects Administration policy and responds to sharply reduced funding and congressional guidance while maintaining progress toward long-term objectives. The program is on track, working toward an early, comprehensive assessment of the viability of the Yucca Mountain site; more closely determining what will be required to incorporate defense waste into the waste management system; pursuing a market-driven strategy for waste acceptance, storage, and transportation; and preserving the core capability to respond to an interim storage contingency. Overall, the elements of an integrated system for managing the Nation`s spent fuel and high-level radioactive waste are emerging, more soundly conceived, and more modestly designed, as the OCRWM works toward the physical reality of waste shipments to Federal facilities.

  13. Office of Civilian Radioactive Waste Management fiscal year 1996 annual report to Congress

    International Nuclear Information System (INIS)

    In Fiscal Year 1996 a revised program strategy was developed that reflects Administration policy and responds to sharply reduced funding and congressional guidance while maintaining progress toward long-term objectives. The program is on track, working toward an early, comprehensive assessment of the viability of the Yucca Mountain site; more closely determining what will be required to incorporate defense waste into the waste management system; pursuing a market-driven strategy for waste acceptance, storage, and transportation; and preserving the core capability to respond to an interim storage contingency. Overall, the elements of an integrated system for managing the Nation's spent fuel and high-level radioactive waste are emerging, more soundly conceived, and more modestly designed, as the OCRWM works toward the physical reality of waste shipments to Federal facilities

  14. 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.

  15. Radioactive wastes and discharges

    International Nuclear Information System (INIS)

    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

  16. Baseline data on radioactivity in drinking water, groundwater, waste water, sewage sludge, residues, and wastes, referring to annual report 1989 'Environmental radioactivity and radiation exposure'

    International Nuclear Information System (INIS)

    This issue of the WaBoLu series gives a comprehensive survey of the radioactivity in drinking water, groundwater, waste water, sewage sludge, residues and wastes in the FRG, as measured in the year 1989 and compiled by the Leitstelle of the WaBoLu Institute of the Federal Board of Health. (orig.)

  17. 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)

  18. Understanding radioactive waste

    International Nuclear Information System (INIS)

    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)

  19. Nevada Test Site 2000 Annual Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site

    Energy Technology Data Exchange (ETDEWEB)

    Y. E.Townsend

    2001-02-01

    This report is a compilation of the calendar year 2000 groundwater sampling results from the Area 5 Radioactive Waste Management Site (RWMS). Contamination indicator data are presented in control chart and tabular form with investigation levels (IL) indicated. Gross water chemistry data are presented in graphical and tabular form. Other information in the report includes, the Cumulative Chronology for Area 5 RWMS Groundwater Monitoring Program, a brief description of the site hydrogeology, and the groundwater sampling procedure.

  20. Predisposal Radioactive Waste Management

    International Nuclear Information System (INIS)

    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

  1. Radioactive waste disposal

    International Nuclear Information System (INIS)

    The current disposal concept for radioactive waste in the FRG was discussed in the framework of this seminar. In addition to this concept for the treatment of radioactive waste also the volume of this waste is indicated. The present state of the two repositories 'Konrad' and 'Gorleben' is explained, as well as the requirements on waste packages for transportation, intermediate and ultimate storage. The final part discusses the conditioning of this radioactive waste and the control of the barrels as regards the observance of the requirements. (orig.)

  2. Radioactive waste management

    International Nuclear Information System (INIS)

    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.)

  3. Radioactive wastes and discharges

    International Nuclear Information System (INIS)

    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.)

  4. Annual Report, Fall 2016: Alternative Chemical Cleaning of Radioactive High Level Waste Tanks - Corrosion Test Results

    Energy Technology Data Exchange (ETDEWEB)

    Wyrwas, R. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-09-01

    The testing presented in this report is in support of the investigation of the Alternative Chemical Cleaning program to aid in developing strategies and technologies to chemically clean radioactive High Level Waste tanks prior to tank closure. The data and conclusions presented here were the examination of the corrosion rates of A285 carbon steel and 304L stainless steel exposed to two proposed chemical cleaning solutions: acidic permanganate (0.18 M nitric acid and 0.05M sodium permanganate) and caustic permanganate. (10 M sodium hydroxide and 0.05M sodium permanganate). These solutions have been proposed as a chemical cleaning solution for the retrieval of actinides in the sludge in the waste tanks and were tested with both HM and PUREX sludge simulants at a 20:1 ratio.

  5. Microbial degradation of low-level radioactive waste. Volume 1, Annual report for FY 1993

    Energy Technology Data Exchange (ETDEWEB)

    Rogers, R.D.; Hamilton, M.A.; Veeh, R.H.; McConnell, J.W. Jr.

    1994-04-01

    The Nuclear Regulatory Commission stipulates that disposed low-level radioactive waste (LLW) be stabilized. Because of apparent ease of use and normal structural integrity, cement has been widely used as a binder to solidify LLW. However, the resulting waste forms are sometimes susceptible to failure due to the actions of waste constituents, stress, and environment. This report reviews laboratory efforts that are being developed to address the effects of microbiologically influenced chemical attack on cement-solidified LLW. Groups of microorganisms are being employed that are capable of metabolically converting organic and inorganic substrates into organic and mineral acids. Such acids aggressively react with cement and can ultimately lead to structural failure. Results on the application of mechanisms inherent in microbially influenced degradation of cement-based material are the focus of this report. Sufficient data-validated evidence of the potential for microbially influenced deterioration of cement-solidified LLW has been developed during the course of this study. These data support the continued development of appropriate tests necessary to determine the resistance of cement-solidified LLW to microbially induced degradation that could impact the stability of the waste form. They also justify the continued effort of enumeration of the conditions necessary to support the microbiological growth and population expansion.

  6. Radioactive waste disposal policy

    International Nuclear Information System (INIS)

    The responsibilities of the Minister of Agriculture, Fisheries and Food and Ministry policy on radioactive waste disposal are described. The disposal of solid radioactive waste at sea is subject to detailed safeguards developed within two international agreements to which the United Kingdom is a contracting party. The agreements are discussed together with a research and monitoring programme to provide scientific data for informed decisions on waste disposal authorisations and dumping licences. (U.K.)

  7. NRC high-level radioactive waste program. Annual progress report: Fiscal Year 1996

    International Nuclear Information System (INIS)

    This annual status report for fiscal year 1996 documents technical work performed on ten key technical issues (KTI) that are most important to performance of the proposed geologic repository at Yucca Mountain. This report has been prepared jointly by the staff of the Nuclear Regulatory Commission (NRC) Division of Waste Management and the Center for Nuclear Waste Regulatory Analyses. The programmatic aspects of restructuring the NRC repository program in terms of KTIs is discussed and a brief summary of work accomplished is provided. The other ten chapters provide a comprehensive summary of the work in each KTI. Discussions on probability of future volcanic activity and its consequences, impacts of structural deformation and seismicity, the nature of of the near-field environment and its effects on container life and source term, flow and transport including effects of thermal loading, aspects of repository design, estimates of system performance, and activities related to the U.S. Environmental Protection Agency standard are provided

  8. Encapsulation of radioactive waste

    International Nuclear Information System (INIS)

    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)

  9. The Community's research and development programme on radioactive waste management and storage shared cost action annual progress report 1989 volume 2

    International Nuclear Information System (INIS)

    In 1985 the Council of Ministers of the European Communities adopted a five-year R and D programme on 'Management and storage of radioactive waste' for the period 1985-89. The R and D programme was carried out by public organizations and private firms in the Member States. By the end of 1989 over 256 contracts had been concluded with some 70 bodies. This annual report, covering the year 1989, is the fourth of its type. For each contract it gives the objectives, working programme and a summary of progress and results obtained as prepared by the contractor under the responsibility of the project leader. The report contains sections on treatment and conditioning of radioactive waste, characterization of conditioned radioactive waste, general aspects of radioactive waste disposal, and the performance of isolation systems

  10. The Community's research and development programme on radioactive waste management and storage shared cost action annual progress report 1989 volume 1

    International Nuclear Information System (INIS)

    In 1985 the Council of Ministers of the European Communities adopted a five-year R and D programme on 'Management and storage of radioactive waste' for the period 1985-89. The R and D programme was carried out by public organizations and private firms in the Member States. By the end of 1989 over 256 contracts had been concluded with some 70 bodies. This annual report, covering the year 1989, is the fourth of its type. For each contract it gives the objectives, working programme and a summary of progress and results obtained as prepared by the contractor under the responsibility of the project leader. The report contains sections on treatment and conditioning of radioactive waste, characterization of conditioned radioactive waste, general aspects of radioactive waste disposal, and the performance of isolation systems

  11. Risk assessment methods for radioactive waste disposal: problems associated with the annual risk approach and how to avoid them

    International Nuclear Information System (INIS)

    It is shown that the method of assessing radioactive waste disposal options in terms of the annual risk to the critical group can lead to anomalous results, in which the risk is artificially diluted by averaging it over a number of generations, most of whom are actually unaffected. An alternative approach is proposed, based on the statistical expectation value of the lifetime risk to the critical group, which is not subject to this problem. The two methods are compared by analysing simple mathematical models of the patterns of radiation exposure that may follow closure of a repository; the origins and possible extent of risk dilution are identified and the relative importance of the risk from stochastic and acute effects is discussed. Finally, the problem of applying the proposed alternative method to a realistic analysis is discussed and an approximation scheme in terms of Laplace transforms is suggested. (author)

  12. Annual report for research on geosphere stability for long-term isolation of radioactive waste in fiscal years 2012

    International Nuclear Information System (INIS)

    This annual report documents the progress of R and D in the 3rd fiscal year during the JAEA 2nd Midterm Plan (FY 2010 - 2014) to provide the scientific base for assessing geosphere stability for long-term isolation of the high-level radioactive waste. The planned framework is structured into the following categories: 1) development and systematization of investigation techniques for selecting suitable sites in geosphere stability, 2) development, application and verification of prediction models for evaluating the changes of geological environment in thermal, hydraulic, mechanical and geochemical conditions for a long period of time, and 3) development of new dating techniques for providing information about geologic history and the timing of geologic events. In this report, the current status of R and D activities with previous scientific and technological progress is summarized. (author)

  13. Radioactive waste storage issues

    Energy Technology Data Exchange (ETDEWEB)

    Kunz, D.E.

    1994-08-15

    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.

  14. Radioactive waste storage issues

    International Nuclear Information System (INIS)

    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

  15. Radioactive waste processing method

    International Nuclear Information System (INIS)

    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.)

  16. Radioactive wastes in Oklo

    International Nuclear Information System (INIS)

    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

  17. Partitioning of long-lived nuclides from radioactive waste. FY 1975 annual report

    Energy Technology Data Exchange (ETDEWEB)

    Wheelwright, E.J.

    1976-04-01

    The status of the following studies is reported: characterization and treatment of solids in high-level waste; removal of long-lived nuclides from solidified waste and non-high-level wastes; development of low-additive flowsheets for removing long-lived nuclides from the fission products; evaluation of incentives for partitioning; and comparison of waste management systems with and without partitioning. (LK)

  18. Characterization of low and medium-level radioactive waste forms. Joint annual progress report 1982

    International Nuclear Information System (INIS)

    The work reported was carried out during the second year of the Commission of the European Communities programme on the characterization of low and medium-level waste forms. Ten reference waste forms plus others of special national interest have been identified covering PWR, BWR, GCR and reprocessing wastes. The immobilizing media include the three main matrices: cement, polymers and bitumen, and a glass. Characterization is viewed as one input to quality assurance of the waste form and covers: waste-matrix compatibility, radiation effects, leaching, microbiological attack, shrinkage and swelling, ageing processes and thermal effects. The aim is a balanced programme of comparative data, predictive modelling and an understanding of basic mechanisms

  19. Radioactive waste management; Gerencia de rejeitos radioativos

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-11-15

    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.

  20. Method of packaging radioactive wastes

    International Nuclear Information System (INIS)

    Purpose: To decrease the leaching of radioactive waste in marine environment. Method: Fillers are placed between a drum can and an inner cage for charging radioactive wastes in order to prevent the leakage of the radioactive wastes from the drum can. Leaching inhibitors for radioactive materials are mixed with the fillers made of organic substance such as asphalts and plastics. The leaching inhibitors are made of materials in the similar chemical form to that of the radioactive materials in the wastes and mixed into the fillers to the saturation limit of dissolution. For the radioactive wastes containing spent adsorbents for iodine, the inhibitors are made of silver nitrates. (Ikeda, J.)

  1. Fifteenth annual U.S. Department of Energy low-level radioactive waste management conference: Agenda and abstracts

    International Nuclear Information System (INIS)

    The goal of the conference was to give the opportunity to identify and discuss low-level radioactive waste management issues, share lessons learned, and hear about some of the latest advances in technology. Abstracts of the presentations are arranged into the following topical sections: (1) Performance Management Track: Performance assessment perspectives; Site characterization; Modeling and performance assessment; and Remediation; (2) Technical Track: Strategic planning; Tools and options; Characterization and validation; Treatment updates; Technology development; and Storage; (3) Institutional Track: Orders and regulatory issues; Waste management options; Legal, economic, and social issues; Public involvement; Siting process; and Low-level radioactive waste policy amendment acts

  2. Fifteenth annual U.S. Department of Energy low-level radioactive waste management conference: Agenda and abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-12-31

    The goal of the conference was to give the opportunity to identify and discuss low-level radioactive waste management issues, share lessons learned, and hear about some of the latest advances in technology. Abstracts of the presentations are arranged into the following topical sections: (1) Performance Management Track: Performance assessment perspectives; Site characterization; Modeling and performance assessment; and Remediation; (2) Technical Track: Strategic planning; Tools and options; Characterization and validation; Treatment updates; Technology development; and Storage; (3) Institutional Track: Orders and regulatory issues; Waste management options; Legal, economic, and social issues; Public involvement; Siting process; and Low-level radioactive waste policy amendment acts.

  3. Radioactive waste management profiles

    International Nuclear Information System (INIS)

    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

  4. Office of Civilian Radioactive Waste Management. Annual report to Congress, February 1984

    International Nuclear Information System (INIS)

    Chapters detail how the Department of Energy assembled resources, created an organizational structure, and carried out specific tasks during the past year in response to the complex mandate of the Nuclear Waste Policy Act. This report concludes with a brief preview of the many projects and tasks that remain to be accomplished in order to make certain that a safe and effective solution to the nuclear waste problem becomes a reality

  5. The radioactive wastes management

    International Nuclear Information System (INIS)

    The different types of radioactive waste are presented in this paper in the frame of the official categories which take into account their dangerousness and the lifetimes of their radioactivity. It is indicated how the less dangerous of them are handled in France. The ways of protecting the environment from the more dangerous ones (high activity and long lifetimes) are object of studies. Scientific questions, in the field of chemistry and physical chemistry, related to the implementation of deep underground repository facilities with full respect of nuclear safety are presented. (authors)

  6. The Community's research and development programme on radioactive waste management and storage. Shared cost action. Annual progress report 1988. Volume 2

    International Nuclear Information System (INIS)

    Third annual progress report of the European Community's 1985-89 programme of research and development 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. This report describes the work to be carried out under research contracts already concluded before the end of 1988, as well as the work performed and the results obtained so far

  7. The Community's research and development programme on radioactive waste management and storage. Shared cost action. Annual progress report 1988. Volume 1

    International Nuclear Information System (INIS)

    Third annual progress report of the European Community's 1985-89 programme of research and development 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. This report describes the work to be carried out under research contracts already concluded before the end of 1988, as well as the work performed and the results obtained so far

  8. Categorizing operational radioactive wastes

    International Nuclear Information System (INIS)

    The primary objective of this publication is to improve communications among waste management professionals and Member States relative to the properties and status of radioactive waste. This is accomplished by providing a standardized approach to operational waste categorization using accepted industry practices and experience. It is a secondary objective to draw a distinction between operational waste categorization and waste disposal classification. The approach set forth herein is applicable to waste generation by mature (major, advanced) nuclear programmes, small-to-medium sized nuclear programmes, and programmes with waste from other nuclear applications. It can be used for planning, developing or revising categorization methodologies. For existing categorization programmes, the approach set forth in this publication may be used as a validation and evaluation tool for assessing communication effectiveness among affected organizations or nations. This publication is intended for use by waste management professionals responsible for creating, implementing or communicating effective categorization, processing and disposal strategies. For the users of this publication, it is important to remember that waste categorization is a communication tool. As such, the operational waste categories are not suitable for regulatory purposes nor for use in health and safety evaluations. Following Section 1 (Introduction) Section 2 of this publication defines categorization and its relationship to existing waste classification and management standards, regulations and practices. It also describes the benefits of a comprehensive categorization programme and fundamental record considerations. Section 3 provides an overview of the categorization process, including primary categories and sub-categories. Sections 4 and 5 outline the specific methodology for categorizing unconditioned and conditioned wastes. Finally, Section 6 provides a brief summary of critical considerations that

  9. Final disposal of radioactive waste

    OpenAIRE

    Freiesleben H.

    2013-01-01

    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 c...

  10. Final disposal of radioactive waste

    Science.gov (United States)

    Freiesleben, H.

    2013-06-01

    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.

  11. Office of Civilian Radioactive Waste Management Fiscal Year 1994 annual report to Congress

    International Nuclear Information System (INIS)

    The events of Fiscal Year 1994 made it a notable year in OCRWN's history. Highlights include formulation of a new program approach; intensive consultation with other parties to build confidence in that approach; the delivery, assembly, and initial testing of the tunnel boring machine that is now digging into Yucca Mountain; steps toward acquisition of a standardized multipurpose canister system and planning for the accompanying environmental impact statement; and solicitation, through a Federal Register notice, of utilities' and other interested parties' recommendations toward resolving key waste-acceptance issues

  12. Office of Civilian Radioactive Waste Management Fiscal Year 1994 annual report to Congress

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    The events of Fiscal Year 1994 made it a notable year in OCRWN`s history. Highlights include formulation of a new program approach; intensive consultation with other parties to build confidence in that approach; the delivery, assembly, and initial testing of the tunnel boring machine that is now digging into Yucca Mountain; steps toward acquisition of a standardized multipurpose canister system and planning for the accompanying environmental impact statement; and solicitation, through a Federal Register notice, of utilities` and other interested parties` recommendations toward resolving key waste-acceptance issues.

  13. Radioactive waste: Issues and debates

    International Nuclear Information System (INIS)

    Waste management in general has always been in terms of regulation Environmental, a subject of attention but also voltages. Radioactive waste management is no exception to the rule and concentrates, sometimes irrationally, the vast majority industry fears nuclear. The first difficulty is to define radioactive waste, which raises further questions with regard to the case law on this topic and reactions of stakeholders. One of the other components of the debate on radioactive waste is the ability of different actors to ensure sustainable waste management Radioactive in optimum conditions in terms of nuclear safety.This results in the acceptance management solutions by the public.

  14. National inventory of radioactive wastes

    International Nuclear Information System (INIS)

    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.)

  15. 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)

    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

  16. Superconducting open-gradient magnetic separation for the pretreatment of radioactive or mixed waste vitrification feeds. 1997 annual progress report

    International Nuclear Information System (INIS)

    'Vitrification has been selected as a final waste form technology in the US for long-term storage of high-level radioactive wastes (HLW). However, a foreseeable problem during vitrification in some waste feed streams lies in the presence of elements (e.g., transition metals) in the HLW that may cause instabilities in the final glass product. The formation of spinel compounds, such as Fe3O4 and FeCrO4, results in glass phase separation and reduces vitrifier lifetime, and durability of the final waste form. A superconducting open gradient magnetic separation (OGMS) system maybe suitable for the removal of the deleterious transition elements (e.g. Fe, Co, and Ni) and other elements (lanthanides) from vitrification feed streams due to their ferromagnetic or paramagnetic nature. The OGMS systems are designed to deflect and collect paramagnetic minerals as they interact with a magnetic field gradient. This system has the potential to reduce the volume of HLW for vitrification and ensure a stable product. In order to design efficient OGMS and High gradient magnetic separation (HGMS) processes, a fundamental understanding of the physical and chemical properties of the waste feed streams is required. Using HLW simulant and radioactive fly ash and sludge samples from the Savannah River Technology Center, Rocky Flats site, and the Hanford reservation, several techniques were used to characterize and predict the separation capability for a superconducting OGMS system.'

  17. Radioactive waste management in Canada

    International Nuclear Information System (INIS)

    Reports and other Canadian literature on radioactive waste processing and disposal covering the period 1953-1979 are listed. A selected list of international conferences relating to waste management (1959-1979) is attached. (LL)

  18. Regulation on radioactive waste management

    International Nuclear Information System (INIS)

    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

  19. 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.

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

    International Nuclear Information System (INIS)

    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

  1. Neutronic measurements of radioactive waste

    International Nuclear Information System (INIS)

    This document presents the general matters involved in the radioactive waste management and the different non destructive assays of radioactivity. The neutronic measurements used in the characterization of waste drums containing emitters are described with more details, especially the active neutronic interrogation assays with prompt or delayed neutron detection: physical principle, signal processing and evaluation of the detection limit. (author)

  2. Public debate - radioactive wastes management

    International Nuclear Information System (INIS)

    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.)

  3. 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)

    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

  4. 1993 Annual progress report for subsidiary agreement No. 2 (1991--1996) between AECL and US/DOE for a radioactive waste management technical co-operative program

    International Nuclear Information System (INIS)

    A coordinated research program on radioactive waste disposal is being carried out by the Atomic Energy of Canada Limited and the US Department of Energy. This annual report describes progress in the following eight studies: Fundamental materials investigations; In-situ stress determination; Development of a spent fuel dissolution model; Large block tracer test--Experimental testing of retardation models; Laboratory and field tests of in-situ hydrochemical tools; Cigar Lake--Analogue study, actinide and fission product geochemistry; Performance assessment technology exchange; and Development of multiple-well hydraulic test and field tracer test methods

  5. Method of removing radioactive waste

    International Nuclear Information System (INIS)

    A paste prepared by mixing a mixed acid containing HF and at least one of HCl and HNO3 with a paste aid is coated at the surface of radioactive wastes, to dissolve the surface thereof. Water is jetted to remove the dissolved radioactive contaminants and the pastes from the surface of the radioactive wastes. Since the pastes are thus used, the amount of liquid wastes can be remarkably reduced compared with that in a conventional electrolysis method. Further, if it is confirmed that dose rate of the radioactive wastes after decontamination is lower than a predetermined level by adding a step of measuring the extent of contamination of the wastes before and after the steps, they can be handled hereinafter being regarded as ordinary wastes. (T.M.)

  6. Radioactive wastes on Kazakhstan territory

    International Nuclear Information System (INIS)

    Common amount of radioactive wastes in Kazakhstan makes up 235 million tons. In Semipalatinsk test site in the result of surface and underground explosions low-radioactive wastes have accumulated in the form of soils contaminated with radionuclides and these wastes could be buried during re-cultivation works. In the same time there are places contaminated with plutonium. These soils should be buried in special points. Volume of these wastes is estimated in 5,000 m3. In Kazakhstan there are one power nuclear reactor in Aktau, 3 research reactors on Semipalatinsk site territory and 1 in Almaty city. During operation of BN-350 power reactor in Aktau city till present day 10,000 m3 of different wastes have been accumulated. Great amount of wastes will appear in 2005 during the reactor decommissioning, common volume of processed and packaged wastes after BN-350 reactor out of operation will be estimated in 623,000 m3. In Kazakhstan system of gathering, processing, and transporting of radioactive wastes is not taken into operation yet. According of conception on radioactive wastes burial and IAEA recommendation part of wastes with volume 67,450 m3 (intermediate- and high-level radioactive wastes) are subjected to burial in points in geological formations

  7. Legal and regulator framework of radioactive waste

    International Nuclear Information System (INIS)

    The present work intends to develop the legislative and regulatory framework in the matter of radioactive waste. The legal frame of the radioactive waste conformed by the National Constitution, the treaties and conventions, laws and decrees and regulatory norm in Argentine . The subject is approached from the international point of view considering the slogan of 36 The Annual Meeting of the Association Argentine de Nuclear Technology: 'The Nuclear Energy in the Present World'. This work also contains a special paragraph dedicated to the analysis of practical cases related to the subject and the activity of the National Commission of Atomic Energy. (author)

  8. Radioactive waste disposal

    International Nuclear Information System (INIS)

    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

  9. 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.

  10. Solidification of radioactive liquid wastes

    International Nuclear Information System (INIS)

    Purpose: To decrease the amount of surface active agents required for solidifying sodium sulfate-containing concentrated radioactive liquid wastes with asphalts. Method: Water soluble calcium compounds (calcium nitrate, etc.) are added to alkaline radioactive concentrated liquid wastes essentially consisting of sodium sulfate to adjust the pH value of the liquid wastes to 4.5 - 8.5. The addition amount of the water soluble calcium compounds (based on the weight of the calcium ions) is set to about 2 - 5% of the sulfate ions in the liquid wastes. Then, surface active agents are added by 3 - 10 weight % to the solid contents in the liquid wastes. (Ikeda, J.)

  11. 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.

  12. 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...

  13. Radioactive waste: show time? - 16309

    International Nuclear Information System (INIS)

    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)

  14. Optimization of the radioactive waste storage

    International Nuclear Information System (INIS)

    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 dm3 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)

  15. Krsko NPP radioactive waste characteristics

    International Nuclear Information System (INIS)

    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

  16. Radioactive waste management in Tanzania

    International Nuclear Information System (INIS)

    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)

  17. Treatment of Radioactive Gaseous Waste

    International Nuclear Information System (INIS)

    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

  18. Design and construction of deinococcus radiodurans for biodegradation of organic toxins at radioactive DOE waste sites. 1998 annual progress report

    International Nuclear Information System (INIS)

    'A 1992 survey of DOE waste sites indicates that about 32% of soils and 45% of groundwaters at these sites contain radionuclides and metals plus an organic toxin class. The most commonly reported combinations of these hazardous compounds being radionuclides and metals (e.g., U, Pu, Cs, Pb, Cr, As) plus chlorinated hydrocarbons (e.g., trichloroethylene), fuel hydrocarbons (e.g., toluene), or polychlorinated biphenyls (e.g., Arochlor 1248). These wastes are some of the most hazardous pollutants and pose an increasing risk to human health as they leach into the environment. The objective of this research is to develop novel organisms, that are highly resistant to radiation and the toxic effects of metals and radionuclides, for in-situ bioremediation of organic toxins. Few organisms exist that are able to remediate such environmental organic pollutants, and among those that can, the bacteria belonging to the genus Pseudomonas are the most characterized. Unfortunately, these bacteria are very radiation sensitive. For example, Pseudomonas spp. is even more sensitive than Escherichia coli and, thus, is not suitable as a bioremediation host in environments subjected to radiation. By contrast, D. radiodurans, a natural soil bacterium, is the most radiation resistant organism yet discovered; it is several thousand times more resistant to ionizing radiation than Pseudomonas. The sophisticated gene transfer and expression systems the authors have developed for D. radiodurans over the last eight years make this organism an ideal candidate for high-level expression of genes that degrade organic toxins, in radioactive environments. The authors ultimate aim is to develop organisms and approaches that will be useful for remediating the large variety of toxic organic compounds found in DOE waste sites that are too radioactive to support other bioremediation organisms. This report summarizes work after the first 6 months of a 3-year project.'

  19. Radioactive waste processing and disposal

    International Nuclear Information System (INIS)

    This compilation contains 4144 citations of foreign and domestic reports, journal articles, patents, conference proceedings, and books pertaining to radioactive waste processing and disposal. Five indexes are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number

  20. National radioactive waste management strategy

    International Nuclear Information System (INIS)

    This article briefs out the strategic management of radioactive wastes in Malaysia. The criteria and methods discussed are those promoted by UTN (Nuclear Energy Unit) which has been given the authority to carry out local research programs in nuclear energy

  1. Radioactive waste management in Austria

    OpenAIRE

    Neubauer Josef

    2004-01-01

    At the Austrian Research Centers Seibersdorf, there are several facilities in stalled for treatment of waste of low and intermediate radioactivity level (radwaste). A separate company within Centers, Nuclear Engineering Seibersdorf, has been formed recently, acting as a centralized facility for treatment, conditioning and storing of such waste within the country. The relevant treatment technology is applied depending on the waste category. In total about 6900 m3 of solid waste of low and inte...

  2. 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

  3. Radioactive wastes problem in Poland

    International Nuclear Information System (INIS)

    The localization of CSOP Near Surface Repository of radioactive wastes in Rozan (Poland) and description of storage facilities was presented. This place is systematically controlled (e.g. measurements of radioactive contamination of the surface air, ground water, soil, grass and cereals). Contamination by tritium near by storage facilities was observed

  4. SELF SINTERING OF RADIOACTIVE WASTES

    Science.gov (United States)

    McVay, T.N.; Johnson, J.R.; Struxness, E.G.; Morgan, K.Z.

    1959-12-29

    A method is described for disposal of radioactive liquid waste materials. The wastes are mixed with clays and fluxes to form a ceramic slip and disposed in a thermally insulated container in a layer. The temperature of the layer rises due to conversion of the energy of radioactivity to heat boillng off the liquid to fomn a dry mass. The dry mass is then covered with thermal insulation, and the mass is self-sintered into a leach-resistant ceramic cake by further conversion of the energy of radioactivity to heat.

  5. Decontamination method for radioactive waste

    International Nuclear Information System (INIS)

    Metallic radioactive wastes are immersed in a liquid nitrogen vessel above a freezing crusher and they are frozen to about -196degC. Then, impact shocks are applied to crush the radioactive wastes frozen by a rotary shearing shock crusher disposed below the freezing crusher. The thus obtained crushed materials are sent to a decontamination device and decontaminated. In this case, since the objective materials are crushed, any of a blast decontamination method, an electrolytic polishing decontamination method, a redox decontamination method and a chemical agent immersion decontamination method can be applied. Thereafter, the dose of remaining radioactivity of the decontaminated crushed materials is measured. With such procedures, the decontamination and the subsequent measurement for the radiation contamination dose can easily and certainly be conducted for metallic radioactive wastes such as pipes of a small diameter and complicated structures. (I.N.)

  6. Characterization of radioactive hazardous waste

    International Nuclear Information System (INIS)

    The characterization of radioactive hazardous waste, also known as transuranic 'mixed waste' has to be completed before it can be classified for proper treatment (incinerator, mechanical compaction or thermal treatment), packing, and transport. The characterization of the TRU mixed waste is not only complex process but rather an expensive undertaking. The process knowledge is the basic foundation of characterization. It is the documented knowledge of processes and materials that generated the waste. The transuranic waste Quality Assurance Program Plan (QAPP) defines the Data Quality Objectives (DQO's) and provides the scope of analytical parameters and methods required to accurately characterize the radioactive mixed waste. Based on the historical data and process knowledge a sampling and analysis plan can be developed to characterize the radioactive hazardous waste. Based on the characterization, an assessment of the regulatory status can be made before the waste could be accepted for disposal at the WIPP facility. The Waste Acceptance Criteria (WAC) developed by WIPP defines the parameters for receiving and final disposal of the TRU waste. The sets of criteria, such as: heat generated, fissile gram equivalent (FGE), plutonium-equivalent (PE) curies, and specifications of a dose rate have to be met before the waste is accepted for deep geological disposal. The characterization of radioactive waste becomes even more complex due to the presence of iron base metals/alloys, aluminum base metals/alloys, organic, chelating agents that are mixed with plastic, rubber, cellulose, soils and cement. Some of the modern characterization technologies that are under development and currently used for TRU mixed wastes are: nondestructive examination, nondestructive assay, headspace gas analysis, and drum coring for Resources Conservation Recovery Act (RCRA) sampling. (author)

  7. Environmental aspects of commercial radioactive waste management

    International Nuclear Information System (INIS)

    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

  8. Environmental aspects of commercial radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    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. (LK)

  9. Research programme on radioactive wastes

    International Nuclear Information System (INIS)

    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

  10. Management of radioactive waste: A review

    Directory of Open Access Journals (Sweden)

    Luis Paulo Sant'ana

    2016-06-01

    Full Text Available 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 country to country. Furthermore, microbiological procedures, plasma vitrification process, chemical precipitation, ion exchange, evaporation and reverse osmosis are strategies used for the treatment of radioactive wastes. The major challenge is to manage these radioactive substances after being used and discharged. This report brings data from the literature published worldwide from 2009 to 2014 on radioactive waste management studies and it covers production, classification and management of radioactive solid, liquid and gas waste.

  11. Subsurface Investigations Program at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory: Annual progress report, FY-1987

    International Nuclear Information System (INIS)

    The Subsurface Investigations Program is obtaining program objectives of a field calibration of a model to predict long-term radionuclide migration and measurement of the actual migration to date. Three deep boreholes were drilled at the Radioactive Waste Management Complex (RWMC) to collect sample material for evaluation of radionuclide content in the interbeds, to determine geologic and hydrologic characteristics of the sediments, and to provide monitoring sites for moisture movement in these sediments. Suction lysimeters and heat dissipation sensors were installed in two deep boreholes to collect moisture data. Data from the moisture sensing instruments installed at the RWMC continued to be collected during FY-1987. Because of the large volume of collected data, the RWMC Data Management System was developed and implemented to facilitate the storage, retrieval, and manipulation of the database. Work on the Computer Model Development task focused on a detailed review of previous vadose zone modeling studies at INEL, acquisition and installation of a suite of computer models for unsaturated flow and contaminant transport, and preliminary applications of computer models using site-specific data. Computer models installed on the INEL CRAY computer for modeling transport through the subsurface pathway include SEMTRA, FEMTRA, TRACR3D, MAGNUM, and CHAINT. In addition to the major computer models, eight other codes, referred to as support codes and models, have been acquired and implemented. 27 refs., 70 figs., 22 tabs

  12. Radioactive wastes, disposal sites wanted

    International Nuclear Information System (INIS)

    Two towns that were selected by the French government to home a disposal site for low-level radioactive wastes, have withdrawn their bid. ANDRA (French national agency for the management of radioactive wastes) attributes this withdrawal to the unbearable pressure made by the opponents on the city councils despite the public information meetings that were held in the 2 cities. The selection rules included the presence of clay layers with a thickness of at least 50 m, the absence of seismic activity and zones containing exploitable resources like petroleum or metal ores were barred in order to avoid future unexpected drilling. (A.C.)

  13. Radioactive waste disposal and constitution

    International Nuclear Information System (INIS)

    The radioactive waste disposal has many dimensions with regard to the constitutional law. The central problem is the corret delimitation between adequate governmental precautions against risks and or the permitted risk which the state can impose on the citizen, and the illegal danger which nobody has to accept. The solution requires to consider all aspects which are relevant to the constitutional law. Therefore, the following analysis deals not only with the constitutional risks and the risks of the nuclear energy, but also with the liberal, overall-economic, social, legal, and democratic aspects of radioactive waste disposal. (HSCH)

  14. Management of Radioactive Wastes in Developing Countries

    International Nuclear Information System (INIS)

    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

  15. Radioactive waste management in Austria

    Directory of Open Access Journals (Sweden)

    Neubauer Josef

    2004-01-01

    Full Text Available At the Austrian Research Centers Seibersdorf, there are several facilities in stalled for treatment of waste of low and intermediate radioactivity level (radwaste. A separate company within Centers, Nuclear Engineering Seibersdorf, has been formed recently, acting as a centralized facility for treatment, conditioning and storing of such waste within the country. The relevant treatment technology is applied depending on the waste category. In total about 6900 m3 of solid waste of low and intermediate radioactivity level originating from Austria was treated in the period between 1976 and 2002. Presently, there exists no final repository for radwaste in Austria. A study is under way to identify the structure for a long term storage facility.

  16. Radioactive Waste management - v. 1

    International Nuclear Information System (INIS)

    The state of the art for each stage and activities correlated to the nuclear fuel cycle, describing the activities of main countries of the world in this area, is presented. In this volume, the principles which described the several sources of radioactive wastes from nuclear industry, the standardization of waste categories, the strategies adopted for treatment and disposal, the repository types and the practices and proposals of several countries in this field, are presented. (M.C.K.)

  17. Nuclear power and radioactive waste

    International Nuclear Information System (INIS)

    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)

  18. Indian programme on radioactive waste management

    Indian Academy of Sciences (India)

    P K Wattal

    2013-10-01

    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.

  19. Radioactive waste arising in the Federal Republic of Germany. 2000 waste inquiry

    International Nuclear Information System (INIS)

    The Federal Office for Radiation Protection performs an annual inquiry into the amounts of untreated radioactive residues as well as the conditioned radioactive wastes produced and intermediately stored and the amounts of wastes to be expected in the following year. This report comprises the results of this inquiry for the period until December 2000 and, additionally, prognoses for the amounts of conditioned radioactive wastes to be expected in future until 2080 and an outlook on the present situation of radioactive waste interim storage and disposal. (orig.)

  20. Geomechanical problems in study of radioactive wastes disposal

    International Nuclear Information System (INIS)

    Methods for both low-intermediate level radioactive wastes disposal and high level radioactive waste disposal were introduced briefly. Geomechanical problems in radioactive wastes disposal were discussed. Some suggestions were proposed for the radioactive wastes disposal in China

  1. Maintaining knowledge of radioactive waste

    International Nuclear Information System (INIS)

    Full text: [Knowledge - 'awareness or familiarity gained by experience (of a person, fact or thing)... a person's range of information ... the sum of what is known ... true, justified belief; certain understanding, as opposed to opinion.' The Oxford Concise English Dictionary.] Organisations responsible for the safe and effective management of radioactive waste will be aware of the value of information characterising the waste and the need for its preservation. In the United Kingdom the principal legal instrument controlling nuclear site activities is the Nuclear Installations Act (1990), which requires certain licence conditions to be fulfilled. One of the 35 conditions of the nuclear site licence demands that operators ensure that adequate records are kept relating to, inter alia, 'the location of all radioactive material, including nuclear fuel and radioactive waste'. Through the application of this licence condition, the relevant nuclear regulator, Nuclear Installations Inspectorate (NII), requires licensees to make arrangements for recording and preserving all the information that may be required in the future to ensure the safe management of radioactive material and radioactive waste. The majority of operators responsible for the long-term management of radioactive waste will establish systems for preserving information. In order for the system to deliver real benefits, there must be absolute clarity concerning what information is to be preserved, the reasons why it must be preserved, how it is to be managed over the long-term and who is responsible for its management. However, the decisive characteristic of this information management system that could make the difference between preserved liability and valued asset is the ability to access and interpret the information now and in the future. On first inspection, this characteristic appears obvious but how often are these systems established with the primary objective of preserving information when it should

  2. 2008 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada: Review of the Performance Assessments and Composite Analyses

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2009-03-30

    The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site requires an annual review to assess the adequacy of the Performance Assessments (PAs) and Composite Analyses (CAs) for each of the facilities, with the results submitted annually to U.S. Department of Energy (DOE) Headquarters. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan. The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO) performed an annual review in fiscal year (FY) 2008 by evaluating operational factors and research results that impact the continuing validity of the PAs and CAs. This annual summary report presents data and conclusions from the FY 2008 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada Test Site relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs.

  3. Management of small quantities of radioactive waste

    International Nuclear Information System (INIS)

    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

  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. 2009 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada: Review of the Performance Assessments and Composite Analysis

    International Nuclear Information System (INIS)

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 Radioactive Waste Management Site (RWMS) Performance Assessments (PAs) and Composite Analyses (CAs) in fiscal year (FY) 2009. This annual summary report presents data and conclusions from the FY 2009 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R and D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada Test Site relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R and D activities were reviewed to determine the adequacy of the CAs.

  6. Storage of Radioactive Waste. Safety Guide

    International Nuclear Information System (INIS)

    Radioactive waste is generated in a broad range of activities involving a wide variety of materials. The wastes arising from these activities have differing physical, chemical and radiological characteristics. This publication gives guidance on the storage of solid, liquid and gaseous radioactive wastes in a wide range of facilities, including those at which waste is generated, treated and conditioned. Contents: 1. Introduction; 2. Protection of human health and the environment; 3. Roles and responsibilities; 4. Common safety considerations for waste storage facilities; 5. Design and operation of small storage facilities for radioactive waste; 6. Design and operation of large storage facilities for radioactive waste; Appendix.

  7. Radioactive waste examination pilot plant

    International Nuclear Information System (INIS)

    The Stored Waste Examination Pilot Plant (SWEPP) is a contact-handled radioactive waste examination pilot facility at the Department of Energy's Idaho National Engineering Laboratory. The plant determines through computerized nondestructive examination (NDE) whether transuranic waste now stored at the INEL qualifies for shipment to DOE's Waste Isolation Pilot Plant in New Mexico or whether it needs further processing. As a container proceeds through the plant it is weighed, x-rayed with real-time radiography to determine actual contents, assayed to determine fissile contents, ultrasonically examined to determine container integrity, and surveyed for surface radiation and contamination. Because the facility handles transuranic waste, proper information management is essential. A microprocessor-based data management system has been developed for this purpose; a key feature is its direct communication with the computerized NDE equipment and with a mainframe computer on which the data is stored permanently. 4 references, 2 figures

  8. 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.

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

    International Nuclear Information System (INIS)

    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

  10. Shallow disposal of radioactive waste

    International Nuclear Information System (INIS)

    A review and evaluation of computer codes capable of simulating the various processes that are instrumental in determining the dose rate to individuals resulting from the shallow disposal of radioactive waste was conducted. Possible pathways of contamination, as well as the mechanisms controlling radionuclide movement along these pathways have been identified. Potential transport pathways include the unsaturated and saturated ground water systems, surface water bodies, atmospheric transport and movement (and accumulation) in the food chain. Contributions to dose may occur as a result of ingestion of contaminated water and food, inhalation of contaminated air and immersion in contaminated air/water. Specific recommendations were developed regarding the selection and modification of a model to meet the needs associated with the prediction of dose rates to individuals as a consequence of shallow radioactive waste disposal. Specific technical requirements with regards to risk, sensitivity and uncertainty analyses have been addressed

  11. Radioactive waste and public acceptance

    International Nuclear Information System (INIS)

    Radioactive waste just happens to be the major issue in the public eye now--it could be replaced by another issue later. A survey is quoted to prove that wastes are not really one of the burning national issues of the day. The people opposing the nuclear program cannot be said to represent the public. The taste of the press for the melodramatic is pointed out. The issue needs to be presented with the proper perspective, in the context of the benefits and risks of nuclear power

  12. Radioactive waste management in Canada

    International Nuclear Information System (INIS)

    This bibliography is a review of the Canadian literature on radioactive waste management from 1953 to the present. It incorporates the references from the previous AECL--6186 revisions, and adds the current data and some of the references that had been omitted. Publications from outside organizations of concern to the Canadian Nuclear Fuel Waste Program are included in addition to AECL Research reports and papers. This report is intended as an aid in the preparation of the Concept Assessment Document and is complementary to AECL Research's internal document-ready references on the MASS-11 word processing systems

  13. Chemical treatment of radioactive wastes

    International Nuclear Information System (INIS)

    This is the third manual of three commissioned by the IAEA on the three principal techniques used in concentrating radioactive liquid wastes, namely chemical precipitation, evaporation and ion exchange. The present manual deals with chemical precipitation by coagulation-flocculation and sedimentation, commonly called ''chemical treatment'' of low-activity wastes. Topics discussed in the manual are: (i) principles of coagulation on flocculation and sedimentation and associated processes; (ii) process and equipment; (iii) conditioning and disposal of flocculation sludge; (iv) sampling and the equipment required for experiments; and (v) factors governing the selection of processes. 99 refs, 17 figs, 4 tabs

  14. Public Education and Radioactive Waste

    International Nuclear Information System (INIS)

    Throughout the country the mention of anything nuclear or the word radiation ignites fear in the minds of many Americans. Political hype, news stories and the lack of basic understanding about nuclear power and radiation causes many people to reject what they do not understand. Often little, if any, thought may have been given to nearby nuclear weapons facilities where family members and neighbors were gainfully employed at these sites. As older nuclear facilities are closed being a result of the end of the Cold War, with indications that radioactive materials might be transported to other parts of the country, the public in expressing concern. It is important that the public have an understanding of how these materials are handled to insure public safety. It becomes important that both the companies handling these materials and the U.S. Department of Energy create an environment that will involve community participation in developing strategies that will promote and support an understanding of how radioactive wastes will be packaged, transported, and disposed. This is being performed in Oak Ridge, TN. through the efforts of the Oak Ridge Site Specific Advisory Board (ORSSAB). The ORSSAB is a DOE sponsored board of private citizens from all walks of life and professionalism's. The objective of this paper is to offer suggestions as to how public confidence, through education about nuclear, radioactive and associated and wastes are effectively handle the problems related to waste disposal, removal or on-site storage. It is essential that the public fully understand and become involved in the need for the reduction of the waste stream volumes and the technical problems being faced in reaching this goal. The effort of gaining public understanding and support of this important task cannot be limited to just those within close proximity to the facility presently housing these materials, but must extend to those outlying areas and along any potential route that might be

  15. Vitrification of hazardous and radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Bickford, D.F.; Schumacher, R.

    1995-12-31

    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.

  16. Final storage of radioactive waste

    International Nuclear Information System (INIS)

    As explained in the present article, operators of nuclear power plants are responsible for the safe final disposal of the radioactive wastes they produce on the strength of the polluter pays principle. To shift the burden of responsibility for safe disposal to society as a whole would violate this principle and is therefore not possible. The polluter pays principle follows from more general principles of the fair distribution of benefits and burdens. Instances of its implementation are to be found in the national Atomic Energy Law as well as in the European Radioactive Waste and Spent Fuel Management Directive. The polluters in this case are in particular responsible for financing the installation and operation of final disposal sites. The reserves accumulated so far for the decommissioning and dismantling of nuclear power plants and disposal of radioactive wastes, including the installation and operation of final disposal sites, should be transferred to a public-law fund. This fund should be supplemented by the polluters to cover further foreseeable costs not covered by the reserves accumulated so far, including a realistic cost increase factor, appropriate risk reserves as well as the costs of the site selection procedure and a share in the costs for the safe closure of the final disposal sites of Morsleben and Asse II. This would merely be implementing in the sphere of atomic law that has long been standard practice in other areas of environmental law involving environmental hazards.

  17. Predisposal management of high level radioactive waste

    International Nuclear Information System (INIS)

    The objective of this safety guide is to provide guidance on predisposal management of high-level radioactive waste to meet the safety requirements spelt out in the safety code on 'management of radioactive waste'. This safety guide provides recommendations to the waste generator/manager at various stages in the predisposal management of high level radioactive waste for ensuring safety of the occupational workers, public and the environment

  18. Filler for solidifying radioactive waste

    International Nuclear Information System (INIS)

    In an existent filler for solidifying radioactive wastes, fine powders generated upon pulverizing concrete waste materials and recovering coarse aggregates and fine aggregates are used as substitutes for a portion of cements and/or at least a portion of sands. Namely, the concrete waste materials are crushed by a crusher, and sieved to recover grains having a grain size of not less than 5mm as regenerated aggregate materials. Further, grains having a grain size of not more than 5mm are selectively collected as fine aggregate materials. Since a large quantity of fine powders and mortar are contained in the fine aggregate materials, they are cleaned by a recovering device. In this case, grains having a grain size of about 0.3mm are separately recovered as fine powders. Since the fine powders are porous and have good water retainability, fillers for radioactive wastes highly flowable and having excellent material-solidifying resistance can be obtained by using the fine powders. Further, they can also contribute with a view point of recycling of sources. (T.M.)

  19. Radioactive waste management - an educational challenge

    International Nuclear Information System (INIS)

    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

  20. Waterproofing improvement of radioactive waste asphalt solid

    International Nuclear Information System (INIS)

    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 600C, 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.)

  1. Solidification method for radioactive waste

    International Nuclear Information System (INIS)

    As a method for processing low level radioactive wastes, it has been known that they are solidified by using inorganic solidifying materials such as cement and water glass. In the present invention, it is considered that not only the low level wastes but also middle level wastes are solidified by cement or the like and then put to land disposal. Therefore, hydrophobic materials such as oils and silicon are coated in the solidification vessel, and solidification is conducted subsequently. With such procedures, even if water intrudes by some causes from the outside, since thin layers made of hydrophobic materials have a permanent water-repellent effect, the intrusion of water to the inside of the solidification material can be prevented as much as possible. Accordingly, integrity of the solidification materials can further be improved. (T.M.)

  2. Law on the management of radioactive waste

    International Nuclear Information System (INIS)

    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

  3. Thermal treatment of organic radioactive waste

    International Nuclear Information System (INIS)

    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

  4. Instructive for radioactive solid waste management

    International Nuclear Information System (INIS)

    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

  5. 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.

  6. Summary of radioactive solid waste received in the 200 Areas during calendar year 1995

    Energy Technology Data Exchange (ETDEWEB)

    Hladek, K.L.

    1996-06-06

    Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. 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 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1995. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, liquid waste data are not included in this document. This annual report provides a summary of the radioactive solid waste received in the both the 200-East and 200-West Areas during the calendar year 1995.

  7. Heat amount measuring method for radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Takakura, Masahide

    1998-10-09

    The present invention provides a device for easily and accurately measuring the amount of heat generated from high level radioactive wastes generated upon reprocessing of spent fuels. Namely, radioactive wastes are contained in a measuring vessel formed by using thick-walled iron plates. Air is circulated in the measuring vessel. The temperatures of charged air and discharged air are measured. Then the amount of heat dissipated from the radioactive wastes and the amount of heat dissipated from the iron plates due to absorption of {gamma}-rays to the iron plates are obtained based on the temperature difference. Accordingly, the amount of heat generated from the radioactive wastes can be measured accurately. In addition, there is provided an effect that the amount of heat generated from radioactive wastes can be measured by simple procedures of charging radioactive wastes in the measuring vessel and driving air circulation fans. (I.S.)

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

    International Nuclear Information System (INIS)

    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. Nuclear energy from radioactive waste

    International Nuclear Information System (INIS)

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

  10. Analysis through indicators of the management of radioactive waste in a radioactive facility

    International Nuclear Information System (INIS)

    The evaluation of the management of radioactive waste in the center of isotopes of the Republic of Cuba is the objective of this work. To do so, all the operations of the management system are evaluated through indicators used by this radioactive facility over a decade ago. Available information is processed from 1996 until 2012. The major waste generators are identified through the indicator of annual generation of each working group by local and by worker and it were analyzed the available store radioactive inventory, the relationship between the variation of annual technological waste volume of waste and the annual total manipulated activity, the relationship generation-declassification and the percent of liquid effluents managed as waste. Indicators of unconditional clearance, as well as the of the gaseous and liquid discharges are presented. It is concluded, with all these indicators, that it is possible to determine where are the causes of the behavior in the generation of radioactive waste if it is an increase of manipulated activity int the places of work or of worker, or improper application of the procedures of collection. It is controlled not only management, but also determines in which aspects can work to achieve the objective of minimizing the formation of these wastes, to be able to reduce the production costs. National shedding environmental regulations are met and the results are acceptable)

  11. Operation of the radioactive waste treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kil Jeong; Ahn, Seom Jin; Lee, Kang Moo; Lee, Young Hee; Sohn, Jong Sik; Bae, Sang Min; Kang, Kwon Ho; Lim, Kil Sung; Sohn, Young Joon; Kim, Tae Kook; Jeong, Kyung Hwan; Wi, Geum San; Park, Seung Chul; Park, Young Woong; Yoon, Bong Keun

    1996-12-01

    The radioactive wasted generated at Korea Atomic Energy Research Institute (KAERI) in 1996 are about 118m{sup 3} of liquid waste and 204 drums of solid waste. Liquid waste were treated by the evaporation process, the bituminization process, and the solar evaporation process. In 1996, 100.5m{sup 3} of liquid waste was treated. (author). 84 tabs., 103 figs.

  12. Operation of the radioactive waste treatment facility

    International Nuclear Information System (INIS)

    The radioactive wasted generated at Korea Atomic Energy Research Institute (KAERI) in 1996 are about 118m3 of liquid waste and 204 drums of solid waste. Liquid waste were treated by the evaporation process, the bituminization process, and the solar evaporation process. In 1996, 100.5m3 of liquid waste was treated. (author). 84 tabs., 103 figs

  13. Radioactive wastes management: what is the situation?

    International Nuclear Information System (INIS)

    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.)

  14. Underground disposal of radioactive wastes

    International Nuclear Information System (INIS)

    This report is an overview document for the series of IAEA reports dealing with underground waste disposal to be prepared in the next few years. It provides an introduction to the general considerations involved in implementing underground disposal of radioactive wastes. It suggests factors to be taken into account for developing and assessing waste disposal concepts, including the conditioned waste form, the geological containment and possible additional engineered barriers. These guidelines are general so as to cover a broad range of conditions. They are generally applicable to all types of underground disposal, but the emphasis is on disposal in deep geological formations. Some information presented here may require slight modifications when applied to shallow ground disposal or other types of underground disposal. Modifications may also be needed to reflect local conditions. In some specific cases it may be that not all the considerations dealt with in this book are necessary; on the other hand, while most major considerations are believed to be included, they are not meant to be all-inclusive. The book primarily concerns only underground disposal of the wastes from nuclear fuel cycle operations and those which arise from the use of isotopes for medical and research activities

  15. Management of the radioactive waste treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kil Jeong; An, Sum Jin; Lee, Kang Mu; Jeong, Kyeong Hwan; Lee, Young Hee; Sohn, Jong Sik; Bae, Sang Min; Kang, Kwon Ho; Yim, Kil Sung; Ui, Keum San; Kim, Tae Kuk; Sohn, Young Jun; You, Young Keol; Park, Young Yoong; Yoon, Bong Keun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1993-12-01

    The radioactive wastes generated in Korea Atomic Energy Research Institute (KAERI) in 1993 are about 107 m{sup 3} of liquid waste and 169 drums of solid waste. Liquid waste is treated by the evaporation process, the bituminization process, and the solar evaporation process. The solid waste is treated by the compaction process and the cementation process. The radioactive wastes treated in 1993 are about 194 m{sup 3} of liquid waste and 31 drums of solid waste, respectively. 28 tabs., 12 figs. (Author) .new.

  16. Equipment for radioactive waste treatment

    International Nuclear Information System (INIS)

    The equipment is used for the concentration, calcination, possibly denitration of high, medium and low level radioactive wastes. It is provided with a heated body and driving mechanism. In the heated body there is a horizontal or oblique shaft with a system of vanes, possibly with a screw. On one side of the heated body there is an opening for drop and vapour extraction. A lead screen may be placed in this area, opposite to it a shielding and between them a deactivation slot. The advantage of the discovery is in that the shaft including the bearings are placed outside of the working part of the equipment. (M.D.)

  17. 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.

  18. Controlling low-level radioactive waste

    International Nuclear Information System (INIS)

    This series of information sheets describes at a popular level the sources of low-level radioactive wastes, their associated hazards, methods of storage, transportation and disposal, and the Canadian regulations that cover low-level wastes

  19. 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.

  20. Microbiology and radioactive waste disposal

    International Nuclear Information System (INIS)

    The present Nirex Safety Assessment Research Programme on microbiology is based on experimental as well as theoretical work. It has concentrated on the study of how mixed, natural populations of microbes might survive and grow on the organic component of Low Level Radioactive Wastes (LLW) and PCM (Plutonium Contaminated Waste) in a cementitious waste repository. The present studies indicate that both carbon dioxide and methane will be produced by microbial action within the repository. Carbon dioxide will dissolve and react with the concrete to a limited extent so methane will be the principal component of the produced gas. The concentration of hydrogen, derived from corrosion, will be depressed by microbial action and that this will further elevate methane levels. Actual rates of production will be lower than that in a domestic landfill due to the more extreme pH. Microbial action will clearly affect the aqueous phase chemistry where organic material is present in the waste. The cellulosic fraction is the main determinant of cell growth and the appearance of soluble organics. The structure of the mathematical model which has been developed, predicts the general features which are intuitively expected in a developing microbial population. It illustrates that intermediate compounds will build up in the waste until growth of the next organism needed for sequential degradation is initiated. The soluble compounds in the pore water and the mixture of microbes present in the waste will vary with time and sustain biological activity over a prolonged period. Present estimates suggest that most microbial action in the repository will be complete after 400 years. There is scope for the model to deal with environmental factors such as temperature and pH and to introduce other energy sources such as hydrogen. (author)

  1. Radioactive Waste in Oil Exploration

    International Nuclear Information System (INIS)

    Naturally occurring radioactive material commonly known as NORM composes the majority of the dose received by a person each year at approximately 80% of the total amount. However, there is a noticeably higher concentration of radioisotopes present in technologically enhanced NORM, often called TENORM, which results directly from human industrial activities. NORM is formed in the process of mineral mining including phosphate production, where the end goal is to concentrate high quantities of metals or elements (e.g. phosphorous). However, NORM has also become a widely recognized problem in the oil and gas industry. It is approximately one hundred and fifty years since oil was discovered in the continental United States and the mention of radioactivity in mineral oils and natural gases occurred in 1904, just eight years after the discovery of radioactivity by Henri Bequerel in 1896. In just over three decades the problems from naturally occurring radioactive material (NORM) wastes arising from the oil and gas industry have been much more scrutinized. In the 1980’s 226Ra began to be noticed when scrap metal dealers would detect unacceptably high levels of radiation from oil-field piping1. In 1991 Raloff2 published an article on the new hot wastes in NORM and in 1992 Wilson et. al3 described the health physics aspects of radioactive petroleum piping scale. NORM will develop in high concentrations in by-product oil and gas waste streams4-7. The NORM will chemically separate from other piped material in the process of the extraction of oil, resulting in high concentrations of 226Ra, 228 Ra and 210Pb and other radioisotopes in a densely caked layer on the inner surfaces of the piping1 . The activity of the 226Ra from NORM ranges from 185 to several tens of thousands Bq/kg of sample. By comparison, the NORM concentrations of radium in rock and soil is, at a natural level, 18.5 - 185 Bq/kg1. Disposal of NORM becomes more problematic as higher concentrations of

  2. Integrated radioactive defense waste management plan

    International Nuclear Information System (INIS)

    The plan for controlling the releases of radioactivity and ensuring the safe storage of radioactive wastes generated by past, present, and future operation of the Savannah River Plant (SRP) is presented. The waste was categorized as solid, liquid, and gaseous, and the different waste management operations are categorized as treatment, storage, and release operations. Following a summary of the environmental effects of SRP emissions, the document includes in succession (1) a description of processes that generate wastes, (2) a description of the various waste treatment techniques, (3) a description of the waste holding facilities, and (4) a description of the plant's waste storage facilities

  3. Annual report on radioactive discharges from Winfrith and monitoring the environment 1987

    International Nuclear Information System (INIS)

    The 1987 Annual Report on radioactive discharges from Winfrith Atomic Energy Establishment and monitoring of the environment is given. The report covers waste discharges to the sea and the earth atmosphere and the associated environmental monitoring. (UK)

  4. Environmental chemistry of radioactive waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Duffield, J.R.; Williams, D.R.

    1986-09-01

    In this review the environmental chemistry problems associated with radioactive waste disposal are considered from the point of view of the threat to man of waste disposal, contamination pathways, the chemistry of waste containment, speciation of radio-isotopes, chemisorption, risk assessment and computerized simulation of waste disposal phenomena. A strategy for the future is discussed.

  5. A survey of radioactive waste disposal in Ireland

    International Nuclear Information System (INIS)

    This survey was undertaken by the Nuclear Energy Board (N.E.B) to assess the quantity of radioactive waste disposed of in Ireland and the methods used. The regulatory control of disposal is carried out on an ongoing basis by the Board's inspectors and is commented on routinely in the Board's annual report.(author)

  6. This is how we manage Sweden's radioactive waste. Activities 1995

    International Nuclear Information System (INIS)

    SKB operates systems and facilities for the management and final disposal of spent nuclear fuel and other radioactive waste in Sweden. SKB has conducted extensive R, D and D work with regard to constructing a spent fuel encapsulation plant and a deep repository in crystalline bedrock. This annual report treats all the different activities without going into technical details

  7. Repository for radioactive waste from petroleum operations

    International Nuclear Information System (INIS)

    In March 2008, the Norwegian Radiation Protection Authority (NRPA) gave the first authorisation to a new repository for radioactive waste from the petroleum industry on the Norwegian continental shelf. The authorisation is for four years initially. The repository will be the final storage destination for radioactive waste which contains enhanced levels of naturally occurring radioactive substances from petroleum extraction operations. Thus, it gives a safe and final storage facility for radioactive waste temporarily stored in facilities along the Norwegian coast. The repository is the first of its kind in Norway and is situated at Stangeneset Industrial Site in Gulen, Sogn og Fjordane County

  8. Management of radioactive waste from nuclear applications

    International Nuclear Information System (INIS)

    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

  9. Probabilistic safety assessment in radioactive waste disposal

    International Nuclear Information System (INIS)

    Probabilistic safety assessment codes are now widely used in radioactive waste disposal assessments. This report gives an overview of the current state of the field. The relationship between the codes and the regulations covering radioactive waste disposal is discussed and the characteristics of current codes is described. The problems of verification and validation are considered. (author)

  10. The computerized follow up of radioactive wastes

    International Nuclear Information System (INIS)

    After a short introduction about the goals and missions of the Andra, the French agency for the management of radioactive wastes, this educational booklet describes the principle and the different steps of the computerized follow up of radioactive waste containers: labelling, identification file, control, follow up during transport, compacting and storage. (J.S.)

  11. Establishment of Radioactive Waste Running Safely in Whole Year

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>In 2008, the radioactive wastes treatment and operation center received about 90 m3 of radioactiveliquid waste, about 30 m3 of radioactive solid waste, and about 160 million m3 of treated radioactive

  12. Management of radioactive wastes of iodine therapy

    International Nuclear Information System (INIS)

    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

  13. Method of processing radioactive wastes

    International Nuclear Information System (INIS)

    Purpose: After removing clads from radioactive wastes, to dry and pulverize the same thereby to reduce hazard of radiation exposure and to obtain a large volume reduction ratio. Method: Regenerated liquid wastes, sludges and spent ion-exchange resin slurries within the tanks are respectively introduced into separation tanks, and the regenerated liquid wastes are sent into a mixing tank after clads within the separation tanks have been precipitated and separated. The sludges are applied with a supersonic wave in the separation tanks, and thereafter are passed through an electromagnetic filter. Then, clads are removed from the sludges, and thereafter the sludges are sent into the mixing tank. The spent ion-exchange resin slurries are applied with a supersonic wave and stirred in the separation tanks, and sent into the mixing tank after the clads have been precipitated and separated. The mixture which has been prepared in the mixing tank is dried and pulverized by a centrifugal film drier, and mixed with burnt ashes discharged from a hopper. Then, the mixture is pelletized and asphalt-hardened. (Yoshino, Y.)

  14. Radioactive waste from non-power applications in Sweden

    International Nuclear Information System (INIS)

    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

  15. The political science of radioactive waste disposal

    International Nuclear Information System (INIS)

    This paper was first presented at the annual meeting of the HPS in New Orleans in 1984. Twelve years later, the basic lessons learned are still found to be valid. In 1984, the following things were found to be true: A government agency is preferred by the public over a private company to manage radioactive waste. Semantics are important--How you say it is important, but how it is heard is more important. Public information and public relations are very important, but they are the last thing of concern to a scientist. Political constituency is important. Don't overlook the need for someone to be on your side. Don't forget that the media is part of the political process-they can make you or break you. Peer technical review is important, but so is citizen review. Sociology is an important issue that scientists and technical people often overlook. In summary, despite the political nature of radioactive waste disposal, it is as true today as it was in 1984 that technical facts must be used to reach sound technical conclusions. Only then, separately and openly, should political factors be considered. So, what can be said today that wasn't said in 1984? Nothing. open-quotes It's deja vu all over again.close quotes

  16. 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.

  17. Shallow land disposal of radioactive waste

    International Nuclear Information System (INIS)

    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

  18. Management of radioactive waste nuclear power plants

    International Nuclear Information System (INIS)

    The authors give a survey of the sources, types and amounts of radioactive waste in LWR nuclear power stations (1,300 MWe). The amount of solid waste produced by a Novovorenezh-type PWR reactor (2 x 400 resp. 1 x 1,000 MWe) is given in a table. Treatment, solidification and final storage of radioactive waste are shortly discussed with special reference to the problems of final storage in the CSR. (HR)

  19. Assessment of Malaysia Institutional radioactive waste management

    International Nuclear Information System (INIS)

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

  20. Radioactive waste management in member states

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    The objective of this part of the report is to present a brief overview of key issues in radioactive waste management on a nation-by-nation basis. Member State representatives were asked to address nine questions in no more than three or four pages. Hence, by design, the presentations are not comprehensive. Even so, the information set out here should provide the reader valuable insights into the nature of problems associated with radioactive waste management. The materials may also be used as a ready reference for specific information about radioactive waste management in individual Member States as well as for comparative purposes. (author).

  1. Offgas treatment for radioactive waste incinerators

    International Nuclear Information System (INIS)

    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

  2. Portable radioactive waste tracking and inspection system

    International Nuclear Information System (INIS)

    Hardware has components such as host computer, Personal Digital Assistant(PDA), bar code scanner, and digital camera. Software consists of database about radioactive waste which covers date, generator, container type, activity, images, physical characteristics, and nuclide. The portable radioactive waste tracking and inspection system needs programs such as web communication between the host computer and PDA, database application of PDA, processing of bar codes and images. The inspector can track, inspect, and modify information such as date, generator, container type, activity, images, physical characteristics, and nuclide by reading two dimensional bar code on container of radioactive waste with bar code scanner on PDA

  3. Annual report of waste generation and pollution prevention progress 1995

    International Nuclear Information System (INIS)

    This fourth Annual Report presents and analyzes 1995 DOE complex-wide waste generation and pollution prevention activities at 40 reporting sites in 25 States, and trends DOE waste generation from 1991 through 1995. DOE has established a 50% reduction goal (relative to the 1993 baseline) for routine operations radioactive and hazardous waste generation, due by December 31, 1999. Routine operations waste generation decreased 37% from 1994 to 1995, and 43% overall from 1993--1995

  4. Proceedings of the specialists' meeting on radioactive wastes management

    International Nuclear Information System (INIS)

    The specialist research meeting on radioactive waste management was held in the Research Reactor Institute, Kyoto University, on November 13 and 14, 1990. This meeting has been held annually in the last several years. The meeting has taken up the topics related to both high and low level waste. This year, it was decided to place emphasis on low level waste and decommissioning waste. This report contains the proceedings of the research meeting. More than 70 persons from universities, government laboratories and private industries participated in the meeting and discussion. The lectures were given on the international trend of the disposal of low level radioactive waste, the performance evaluation test on natural barriers against the movement of radioactive nuclides in shallow underground, the environment parameters used for the calculation of dose equivalent, the construction of the high performance treatment system for fuel reprocessing waste, the present state and the technical development of nuclear facility decommissioning, and the investigation and evaluation of groundwater flow. The preparation of this proceedings was made possible by the cooperation of the authors and the assistance of Radioactive Waste Management Division of Research Reactor Institute. (K.I.)

  5. Remedial action for radioactive waste rock piles in China

    International Nuclear Information System (INIS)

    The Chinese government has conducted remedial action for radioactive waste rock piles since 1990. The radioactive waste rocks produced in the course of geological exploration of uranium deposits are widely distributed over several hundreds of locations in more than 20 provinces in China. The following remedial actions for radioactive waste rock piles have been undertaken in China: 1. Protecting dams for stabilizing the piles have been built. A total length of about 50,000 m of these dams has been completed. 2. Soil layers have been emplaced on the radioactive waste rock piles. The focus of the action is to eliminate the radiation harmful to public health. A total area of 750,000 square meters of soil has been placed on the piles in China. 3. Radioactive waste rock piles have been vegetated. Aesthetic shaping of the landscape in the exploratory district of the uranium deposits is our expectant goal. A total area of about 560,000 square meters of vegetation has been placed on the soil covering the piles. Through these remedial actions, the environmental situation has been extensively improved in the remedial districts. The individual annual effective dose equivalent is less than 1 Sv/a. The radon emission rate is less than 20 pCi/m2.s. The gamma ray external exposure rate has been greatly reduced. Copyright (2001) Material Research Society

  6. Radioactive gaseous waste processing device

    International Nuclear Information System (INIS)

    In a radioactive gaseous waste processing device, a dehumidifier in which a lot of hollow thread membranes are bundled and assembled is disposed instead of a dehumidifying cooling device and a dehumidifying tower. The dehumidifier comprises a main body, a great number of hollow thread membranes incorporated in the main body, a pair of fixing members for bundling and fixing both ends of the hollow thread membranes, a pair of caps for allowing the fixing members to pass through and fixing them on both ends of the main body, an off gas flowing pipe connected to one of the caps, a gas exhaustion pipe connected to the other end of the cap and a moisture removing pipeline connected to the main body. A flowrate control valve is connected to the moisture removing pipeline, and the other end of the moisture removing pipeline is connected between a main condensator and an air extraction device. Then, cooling and freezing devices using freon are no more necessary, and since the device uses the vacuum of the main condensator as a driving source and does not use dynamic equipments, labors for the maintenance is greatly reduced to improve economical property. The facilities are reduced in the size thereby enabling to use space effectively. (N.H.)

  7. Juridical and institutional aspects of radioactive wastes

    International Nuclear Information System (INIS)

    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

  8. Environmental aspects of commercial radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1979-05-01

    Environmental effects (including accidents) associated with facility construction, operation, decommissioning, and transportation in the management of commercially generated radioactive waste were analyzed for plants and systems assuming a light water power reactor scenario that produces about 10,000 GWe-yr through the year 2050. The following alternative fuel cycle modes or cases that generate post-fission wastes requiring management were analyzed: a once-through option, a fuel reprocessing option for uranium and plutonium recycle, and a fuel reprocessing option for uranium-only recycle. Volume 1 comprises five chapters: introduction; summary of findings; approach to assessment of environmental effects from radioactive waste management; environmental effects related to radioactive management in a once-through fuel cycle; and environmental effects of radioactive waste management associated with an LWR fuel reprocessing plant. (LK)

  9. Method of processing liquid radioactive wastes by calcination and vitrification

    International Nuclear Information System (INIS)

    The original liquid radioactive waste is added to the radioactive waste calcinate and glass-forming additions. The said components are converted into a paste form which is proportioned in the melting furnace. Moisturising the mixture with liquid radioactive waste eliminates dust, avoids radionuclide volatility and has an additional advantage that more radioactive waste can be processed. (E.S.)

  10. Commercial waste treatment program annual progress report for FY 1983

    Energy Technology Data Exchange (ETDEWEB)

    McElroy, J.L.; Burkholder, H.C. (comps.)

    1984-02-01

    This annual report describes progress during FY 1983 relating to technologies under development by the Commercial Waste Treatment Program, including: development of glass waste form and vitrification equipment for high-level wastes (HLW); waste form development and process selection for transuranic (TRU) wastes; pilot-scale operation of a radioactive liquid-fed ceramic melter (LFCM) system for verifying the reliability of the reference HLW treatment proces technology; evaluation of treatment requirements for spent fuel as a waste form; second-generation waste form development for HLW; and vitrification process control and product quality assurance technologies.

  11. Commercial waste treatment program annual progress report for FY 1983

    International Nuclear Information System (INIS)

    This annual report describes progress during FY 1983 relating to technologies under development by the Commercial Waste Treatment Program, including: development of glass waste form and vitrification equipment for high-level wastes (HLW); waste form development and process selection for transuranic (TRU) wastes; pilot-scale operation of a radioactive liquid-fed ceramic melter (LFCM) system for verifying the reliability of the reference HLW treatment proces technology; evaluation of treatment requirements for spent fuel as a waste form; second-generation waste form development for HLW; and vitrification process control and product quality assurance technologies

  12. Quality control in the radioactive waste management

    International Nuclear Information System (INIS)

    Radioactive waste management as in industrial activities must mantain in all steps a quality control programme. This control extended from materials acquisition, for waste treatment, to the package deposition is one of the most important activities because it aims to observe the waste acceptance criteria in repositories and allows to guarantee the security of the nuclear facilities. In this work basic knowledges about quality control in waste management and some examples of adopted procedures in other countries are given. (author)

  13. The 1985 United Kingdom radioactive waste inventory

    International Nuclear Information System (INIS)

    This report provides a compilation of stocks of radioactive wastes in the UK by volume, as at 1 January 1985, and estimates of future arisings to the year 2030. It includes radionuclide contents as available, together with specific activities, notional conditioning factors and disposal routes. In the main the stock volumes are given as unconditioned waste. However for clarity and precision some of the data relates to treated wastes (ie compacted wastes, incinerator ash, etc). These are clearly marked in the Tables. (author)

  14. Mental Models of Radioactivity and Attitudes towards Radioactive Waste

    International Nuclear Information System (INIS)

    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

  15. Radioactive wastes handling problems in Venezuela

    International Nuclear Information System (INIS)

    A brief description of the radioactive wastes problem in Venezuela is presented. The origins of the problem are shown in a squematic form. The requirements for its solution are divided into three parts: information system, control system, radioactive wastes hadling system. A questionnaire summarizing factors to be considered when looking for a solution to the problem in Venezuela is included, as well as conclusions and recomendations for further discussion

  16. Deep-sea burial of radioactive wastes

    International Nuclear Information System (INIS)

    State of the art of sea dumping of radioactive wastes, legal bases, problems of ecology and environmental safety, possibilities and prospects were the goal of this seminar. Moreover, experts in ministries and members of the parliament in the Federal Republic of Germany should be supported by the results and experiences given here in order to find the legal requirements for a marine disposal of special radioactive wastes. (RB)

  17. Microbiological treatment of low level radioactive waste

    International Nuclear Information System (INIS)

    This report summarises the work of an experimental programme investigating the anaerobic digestion of low-level radioactive wastes. The project focused on the selection of the optimum bioreactor design to achieve 95% removal or stabilisation of the biodegradable portion of low-level radioactive wastes. Performance data was obtained for the bioreactors and process scale-up factors for the construction of a full-scale reactor were considered. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-02-27

    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.

  19. Geological aspects of radioactive waste disposal

    International Nuclear Information System (INIS)

    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.)

  20. Policies and strategies for radioactive waste management

    International Nuclear Information System (INIS)

    A policy for spent fuel and radioactive waste management should include a set of goals or requirements to ensure the safe and efficient management of spent fuel and radioactive waste in the country. Policy is mainly established by the national government and may become codified in the national legislative system. The spent fuel and radioactive waste management strategy sets out the means for achieving the goals and requirements set out in the national policy. It is normally established by the relevant waste owner or nuclear facility operator, or by government (institutional waste). Thus, the national policy may be elaborated in several different strategy components. To ensure the safe, technically optimal and cost effective management of radioactive waste, countries are advised to formulate appropriate policies and strategies. A typical policy should include the following elements: defined safety and security objectives, arrangements for providing resources for spent fuel and radioactive waste management, identification of the main approaches for the management of the national spent fuel and radioactive waste categories, policy on export/import of radioactive waste, and provisions for public information and participation. In addition, the policy should define national roles and responsibilities for spent fuel and radioactive waste management. In order to formulate a meaningful policy, it is necessary to have sufficient information on the national situation, for example, on the existing national legal framework, institutional structures, relevant international obligations, other relevant national policies and strategies, indicative waste and spent fuel inventories, the availability of resources, the situation in other countries and the preferences of the major interested parties. The strategy reflects and elaborates the goals and requirements set out in the policy statement. For its formulation, detailed information is needed on the current situation in the country

  1. Low-level radioactive waste in the northeast: revised waste volume projections

    International Nuclear Information System (INIS)

    The volume of low-level radioactive waste generated in the eleven Northeast states has undergone significant change since the inital 1982 analysis and projection. These revised projections incorporate improved data reporting and evidence of sharp declines in certain categories of waste. Volumes in the 1982-1983 period reflect waste shipped for disposal as reported by disposal site operators. Projected waste volumes represent waste intended for disposal. The recent dramatic changes in source reduction and waste management practices underscore the need for annual review of waste volume projections. The volume of waste shipped for off-site disposal has declined approximately 12% in two years, from an average 1,092,500 ft3 annually in 1979 to 1981 to an average annual 956,500 ft3 in 1982 to 1983; reactor waste disposal volumes declined by about 39,000 ft3 or 7% during this period. Non-reactor waste volumes shipped for disposal declined by over 70,000 ft3 or 15% during this period. The data suggest that generators increased their use of such management practices as source reduction, compaction, or, for carbon-14 and tritium, temporary storage followed by disposal as non-radioactive waste under the NRC de minimus standard effective March 1981. Using the Technical Subcommittee projection methodology, the volume of low-level waste produced annually in the eleven states, individually and collectively, is expected to increase through the year 2000, but at a significantly lower rate of increase than initially projected. By the year 2000, the Northeast is projected to generate 1,137,600 ft3 of waste annually, an increase of about 20% over 1982 to 1983 average volume

  2. Urban Radioactive Waste Repositories in China

    International Nuclear Information System (INIS)

    In order to strengthen the storage and management of radioactive waste and disused radioactive sources, the Chinese Government decided in 2005 to construct urban radioactive waste repositories to achieve “one province, one repository”. This project constructed and renovated 31 urban repositories as well as one national repository. Through several years of unremitting efforts, all the repositories have been completed and put into use. The paper introduces the situation of this project and details information by taking the Jiangsu repository as an example, and analyses challenges and problems of disused sources in recovery, conditioning and disposal in China. (author)

  3. 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...

  4. Processing system for low level radioactive waste

    International Nuclear Information System (INIS)

    Low level radioactive wastes are successively charged into a container while sliding a partition plate such that the wastes are kept substantially in a fully charged state in the direction of the height. Radiation rays from the low level radioactive wastes contained in the container are measured by a radiation dose measuring means constituted so as to be slidable together with the partition plate. Further, the weight of the low level radioactive wastes in the container is measured by the weight measuring means, and the radioactivity concentration per unit container is calculated by a calculation means based on the result of the measurement. Accordingly, the optimum storage period and the radioactivity level can be estimated on every containers. Further, since the measuring vessel is used also as a storage vessel, long time measurement can be conducted by measuring the radioactivity for the wastes successively to enable exact evaluation. Accordingly, it is possible to save the labors for processing operation and save the storage facility. (T.M.)

  5. Disposal of radioactive waste. Some ethical aspects

    International Nuclear Information System (INIS)

    The threat posed to humans and nature by radioactive material is a result of the ionizing radiation released during the radioactive decay. The present use of radioactivity in medicine research and technologies produces steadily radioactive waste. It is therefore necessary to safely store this waste, particularly high level waste from nuclear facilities. The decisive factors determining the necessary duration of isolation or confinement are the physical half-life times ranging with some radionuclides up to many million years. It has therefore been accepted worldwide that the radioactive material needs to be confined isolated from the biosphere, the habitat of humans and all other organisms, for very long time periods. Although it is generally accepted that repositories for the waste are necessary, strong public emotions have been built up against the strategies to erect such installations. Apparently transparent information and public participation has been insufficient or even lacking. These problems have led to endeavours to achieve public acceptance and to consider ethical acceptability. Some aspects of such discussions and possibilities will be taken up in this contribution. This article is based on the work of an interdisciplinary group. The results have been published in 'Radioactive Waste - Technical and Normative Aspects of its Disposal' by C. Streffer, C.F. Gethmann, G. Kamp et al. in 'Ethics of Sciences and Technology Assessment', Volume 38, Springer-Verlag Berlin Heidelberg 2011.

  6. Disposal of radioactive waste. Some ethical aspects

    Energy Technology Data Exchange (ETDEWEB)

    Streffer, Christian

    2014-07-01

    The threat posed to humans and nature by radioactive material is a result of the ionizing radiation released during the radioactive decay. The present use of radioactivity in medicine research and technologies produces steadily radioactive waste. It is therefore necessary to safely store this waste, particularly high level waste from nuclear facilities. The decisive factors determining the necessary duration of isolation or confinement are the physical half-life times ranging with some radionuclides up to many million years. It has therefore been accepted worldwide that the radioactive material needs to be confined isolated from the biosphere, the habitat of humans and all other organisms, for very long time periods. Although it is generally accepted that repositories for the waste are necessary, strong public emotions have been built up against the strategies to erect such installations. Apparently transparent information and public participation has been insufficient or even lacking. These problems have led to endeavours to achieve public acceptance and to consider ethical acceptability. Some aspects of such discussions and possibilities will be taken up in this contribution. This article is based on the work of an interdisciplinary group. The results have been published in 'Radioactive Waste - Technical and Normative Aspects of its Disposal' by C. Streffer, C.F. Gethmann, G. Kamp et al. in 'Ethics of Sciences and Technology Assessment', Volume 38, Springer-Verlag Berlin Heidelberg 2011.

  7. Management of radioactive waste; Beheer van radioactief afval

    Energy Technology Data Exchange (ETDEWEB)

    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.

  8. Radioactive waste management of health services

    International Nuclear Information System (INIS)

    In health care establishment, radioactive waste is generated from the use of radioactive materials in medical applications such as diagnosis, therapy and research. Disused sealed sources are also considered as waste. To get the license to operate from Comissao Nacional de Energia Nuclear - CNEN, the installation has to present a Radiation Protection Plan, in which the Waste Management Programme should be included. The Waste Management Programme should contain detailed description on methodologies and information on technical and administrative control of generated waste. This paper presents the basic guidelines for the implementation of a safe waste management by health care establishments, taking into account the regulations from CNEN and recommendations from the International Atomic Energy Agency - IAEA. (author)

  9. Reduction of INTEC Analytical Radioactive Liquid Wastes

    International Nuclear Information System (INIS)

    This report details the evaluation of the reduction in radioactive liquid waste from the analytical laboratories sent to the Process Effluent Waste system (deep tanks). The contributors are the Analytical Laboratories Department (ALD), the Waste Operations Department, the laboratories at CPP-637, and natural run off. Other labs were contacted to learn the methods used and if any new technologies had emerged. A waste generation database was made from the current methods in used in the ALD. From this database, methods were targeted to reduce waste. Individuals were contacted on ways to reduce waste. The results are: a new method generating much less waste, several methods being handled differently, some cleaning processes being changed to reduce waste, and changes to reduce chemicals to waste

  10. Reduction of INTEC Analytical Radioactive Liquid Wastes

    Energy Technology Data Exchange (ETDEWEB)

    V. J. Johnson; J. S. Hu; A. G. Chambers

    1999-06-01

    This report details the evaluation of the reduction in radioactive liquid waste from the analytical laboratories sent to the Process Effluent Waste system (deep tanks). The contributors are the Analytical Laboratories Department (ALD), the Waste Operations Department, the laboratories at CPP-637, and natural run off. Other labs were contacted to learn the methods used and if any new technologies had emerged. A waste generation database was made from the current methods in used in the ALD. From this database, methods were targeted to reduce waste. Individuals were contacted on ways to reduce waste. The results are: a new method generating much less waste, several methods being handled differently, some cleaning processes being changed to reduce waste, and changes to reduce chemicals to waste.

  11. Reduction of INTEC Analytical Radioactive Liquid Waste

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, Virgil James; Hu, Jian Sheng; Chambers, Andrea

    1999-06-01

    This report details the evaluation of the reduction in radioactive liquid waste from the analytical laboratories sent to the Process Effluent Waste system (deep tanks). The contributors are the Analytical Laboratories Department (ALD), the Waste Operations Department, the laboratories at CPP-637, and natural run off. Other labs were contacted to learn of methods used and if any new technologies had emerged. A waste generation database was made from the current methods in use in the ALD. From this database, methods were targeted to reduce waste. Individuals were contacted on ways to reduce waste. The results are: a new method generating much less waste, several methods being handled differently, some cleaning processes being changed to reduce waste, and changes to reduce chemicals to waste.

  12. Radioactive waste disposal and public acceptance aspects

    International Nuclear Information System (INIS)

    Part of the public opinion around the world considers the wastes generated due to nuclear applications as the biggest environmental problem of the present time. The development of a solution that satisfies everybody is a great challenge, in that obtaining public acceptance for nuclear enterprises is much more challenging than solving the technical issues involved. Considering that the offering of a final solution that closes the radioactive waste cycle has a potentially positive impact on public opinion, the objective of this work is to evaluate the amount of the radioactive waste volume disposed in a five-year period in several countries and gauge the public opinion regarding nuclear energy. The results show that the volume of disposed radioactive waste increased, a fact that stresses the importance of promoting discussions about repositories and public acceptance. (author)

  13. The IAEA radioactive waste safety standards programme

    Energy Technology Data Exchange (ETDEWEB)

    Tourtellotte, James R.

    1995-12-31

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

  14. Radioactive tank waste remediation focus area

    International Nuclear Information System (INIS)

    EM's Office of Science and Technology has established the Tank Focus Area (TFA) to manage and carry out an integrated national program of technology development for tank waste remediation. The TFA is responsible for the development, testing, evaluation, and deployment of remediation technologies within a system architecture to characterize, retrieve, treat, concentrate, and dispose of radioactive waste stored in the underground stabilize and close the tanks. The goal is to provide safe and cost-effective solutions that are acceptable to both the public and regulators. Within the DOE complex, 335 underground storage tanks have been used to process and store radioactive and chemical mixed waste generated from weapon materials production and manufacturing. Collectively, thes tanks hold over 90 million gallons of high-level and low-level radioactive liquid waste in sludge, saltcake, and as supernate and vapor. Very little has been treated and/or disposed or in final form

  15. Development of a Radioactive Waste Assay System

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Duck Won; Song, Myung Jae; Shin, Sang Woon; Sung, Kee Bang; Ko, Dae Hach [Korea Electric Power Research Institute, Taejon (Korea, Republic of); Kim, Kil Jeong; Park, Jong Mook; Jee, Kwang Yoong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-12-31

    Nuclear Act of Korea requires the manifest of low and intermediate level radioactive waste generated at nuclear power plants prior to disposal sites.Individual history records of the radioactive waste should be contained the information about the activity of nuclides in the drum, total activity, weight, the type of waste. A fully automated nuclide analysis assay system, non-destructive analysis and evaluation system of the radioactive waste, was developed through this research project. For the nuclides that could not be analysis directly by MCA, the activities of the representative {gamma}-emitters(Cs-137, Co-60) contained in the drum were measured by using that system. Then scaling factors were used to calculate the activities of {alpha}, {beta}-emitters. Furthermore, this system can automatically mark the analysis results onto the drum surface. An automated drum handling system developed through this research project can reduce the radiation exposure to workers. (author). 41 refs., figs.

  16. Radioactive waste disposal and public acceptance aspects

    Energy Technology Data Exchange (ETDEWEB)

    Ulhoa, Barbara M.A.; Aleixo, Bruna L.; Mourao, Rogerio P.; Ferreira, Vinicius V.M., E-mail: mouraor@cdtn.b, E-mail: vvmf@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    Part of the public opinion around the world considers the wastes generated due to nuclear applications as the biggest environmental problem of the present time. The development of a solution that satisfies everybody is a great challenge, in that obtaining public acceptance for nuclear enterprises is much more challenging than solving the technical issues involved. Considering that the offering of a final solution that closes the radioactive waste cycle has a potentially positive impact on public opinion, the objective of this work is to evaluate the amount of the radioactive waste volume disposed in a five-year period in several countries and gauge the public opinion regarding nuclear energy. The results show that the volume of disposed radioactive waste increased, a fact that stresses the importance of promoting discussions about repositories and public acceptance. (author)

  17. The management and disposal of radioactive waste

    International Nuclear Information System (INIS)

    This article describes the origin and nature of high, intermediate and low-level radioactive wastes and discusses the NIREX proposals for the effective packaging, storage and disposal of these wastes. The transportation of packaged wastes from their source of origin to a repository and the possible radiation hazards to workers and the public are discussed. The importance of careful selection of repository sites based on local geology, population density and scenic interest are also discussed. (U.K.)

  18. Hazardous and radioactive waste incineration studies

    International Nuclear Information System (INIS)

    Development and demonstration of a transuranic (TRU) waste volume-reduction process is described. A production-scale controlled air incinerator using commercially available equipment and technology has been modified for solid radioactive waste service. This unit successfully demonstrated the volume reduction of transuranic (TRU) waste with an average TRU content of about 20 nCi/g. The same incinerator and offgas treatment system is being modified further to evaluate the destruction of hazardous liquid wastes such as polychlorinated biphenyls (PCBs) and hazardous solid wastes such as pentachlorophenol (PCP)-treated wood

  19. Radioactive waste management: yesterday, today and tomorrow

    International Nuclear Information System (INIS)

    The public believes that there is a radioactive waste problem, but knowledge in the field is so well advanced that the only problem left is how to choose the most economically effective method among many available. Tailings from uranium ore processing could be made harmless by removing the majority of the radium and storing the remaining waste in well-designed retention areas. Non-fuel reactor wastes may be handled by incineraton, reverse osmosis, and evaporation in a central waste management centre. The dry storage of spent fuel in concrete cannisters is being investigated. Ultimate disposal of high-level wastes will be in deep, stable geologic formations. (LL)

  20. Radioactive waste package acceptance criteria

    International Nuclear Information System (INIS)

    Preliminary acceptance criteria have been developed for packages containing nuclear waste which must be stored or disposed of by the US Department of Energy. Acceptance criteria are necessary to ensure that the waste packages are compatible with all elements of the Waste Management System. The acceptance criteria are subject to revision since many of the constraints that will be imposed on the waste packages by the Waste Management System have either not been defined or are being revised. Delineation of the acceptance criteria will provide bases for handling, transporting and disposing of the commercial waste

  1. Prospects of nuclear waste management and radioactive waste management

    International Nuclear Information System (INIS)

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

  2. Radioactive waste management status and trends. An overview of international status and trends in radioactive waste management. No. 3

    International Nuclear Information System (INIS)

    The purpose of this report is to compile and disseminate information about the status of and trends in radioactive waste management in Agency Member States in a timely manner. The report is suitable for radioactive waste managers and regulators, decision making organizations in both governmental and private sectors, and for Agency Departments, in both the regular and Technical Co-operation programmes. Currently, the report is targeted at readers with a good knowledge of radioactive waste management. The plan is to have the document evolve to serve a broader audience using easy-to-understand graphical and tabular data. For this, the third report in the series, contributions on a variety of topics in radioactive waste management were solicited from persons and organizations external to the Agency. Throughout the report, submissions received from external contributors are denoted. The preparation of this annual report involves (a) a meeting with a team of consultants from a variety of government and industrial organizations to compile a first draft, (b) the optional issuance of special service contracts to polish and supplement the first draft, (c) review by Agency staff and external contributors to the report and (d) final review and approval by the Director of the Nuclear Energy and Waste Technology Division, Nuclear Energy Department, in the Agency

  3. Strategy on radioactive waste management in Lithuania

    Energy Technology Data Exchange (ETDEWEB)

    Poskas, P.; Adomaitis, J.E. [Lithuanian Energy Inst., Nuclear Engineering Lab., Kaunas (Lithuania)

    2003-07-01

    In Lithuania about 70-80% of all electricity is generated at a single power station, Ignalian NPP which has two non-upgradable RBMK-1500 type reactors. The unit 1 will be closed by 2005. The decision on unit 2 should be made in Lithuanian Parliament very soon taking into consideration substantial long-term financial assistance from the EU, G7 and other states as well as international institutions. The Government approved the Strategy on Radioactive Waste Management in 2002. Objectives of this strategy are to develop the radioactive waste management infrastructure based on modern technologies and provide for the set of practical actions that shall bring management of radioactive waste in Lithuania in compliance with radioactive waste management principles of IAEA and with good practices in force in EU Member States. Ignalina NPP is undertaking a program of decommissioning support projects, financed by grants from the International Ignalina Decommissioning Support Fund, administered by the European Bank for Reconstruction and Development. This program comprises also the implementation of investment projects in a number of pre-decommissioning facilities including the management of radioactive waste and spent nuclear fuel. (orig.)

  4. Management of radioactive waste from reprocessing plants

    International Nuclear Information System (INIS)

    Reprocessing and recycling of both fissile and fertile components back into appropriate reactor systems is an integral part of three stage nuclear energy programme of India. Different steps involved in processing of spent nuclear fuel (SNF) are decladding, dissolution and recovery of fissile and fertile materials. Reprocessing of SNF is a complex process involving handling of large quantity of radioactive materials and processing chemicals. There are three reprocessing plants in operation in the country at Trombay, Tarapur and Kalpakkam. Out of these plants, Trombay reprocessing plant is engaged in reprocessing of SNF from research reactors and other two plants are processing of SNF from PHWRs. A facility is being built for reprocessing of thorium based spent fuel at BARC, Trombay based on the experience of pilot plant scale. Like other industrial activities of nuclear fuel cycle, fuel reprocessing facilities too generate various types of radioactive waste streams. These are generated in all the three physical forms namely solid, liquid and gas. These waste streams are primarily categorized on the basis of concentration of radionuclides, their half lives and toxicity. Management of these wastes aims at (a) recovery and recycle of useful materials, (b) concentration and confinement of radioactivity in inert and stable matrices, (c) minimization of final waste volume for disposal, (d) decontamination of effluents following ALARA principle and (e) minimization of radioactive discharge to the environment. The present paper outlines the salient features of management of different types of radioactive waste generated in reprocessing plants handling SNF from research reactors and PHWR

  5. Cements in Radioactive Waste Disposal

    International Nuclear Information System (INIS)

    The use of cement and concrete to immobilise radioactive waste is complicated by the wide- ranging nature of inorganic cementing agents available as well as the range of service environments in which cement is used and the different functions expected of cement. For example, Portland cement based concretes are widely used as structural materials for construction of vaults and tunnels. These constructions may experience a long pre-closure performance lifetime during which they are required to protect against collapse and ingress of water: strength and impermeability are key desirable characteristics. On the other hand, cement and concrete may be used to form backfills, ranging in permeability. Permeable formulations allow gas readily to escape, while impermeable barriers retard radionuclide transport and reduce access of ground water to the waste. A key feature of cements is that, while fresh, they pass through a fluid phase and can be formed into any shape desired or used to infiltrate other materials thereby enclosing them into a sealed matrix. Thereafter, setting and hardening is automatic and irreversible. Where concrete is used to form structural elements, it is also natural to use cement in other applications as it minimises potential for materials incompatibility. Thus cement- mainly Portland cement- has been widely used as an encapsulant for storage, transport and as a radiation shield for active wastes. Also, to form and stabilise structures such as vaults and silos. Relative to other potential matrices, cement also has a chemical immobilisation potential, reacting with and binding with many radionuclides. The chemical potential of cements is essentially sacrificial, thus limiting their performance lifetime. However performance may also be required in the civil engineering sense, where strength is important, so many factors, including a geochemical description of service conditions, may require to be assessed in order to predict performance lifetime. The

  6. Radioactive waste management centers: an approach

    International Nuclear Information System (INIS)

    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

  7. Public involvement in radioactive waste management decisions

    International Nuclear Information System (INIS)

    Current repository siting efforts focus on Yucca Mountain, Nevada, where DOE's Office of Civilian Radioactive Waste Management (OCRWM) is conducting exploratory studies to determine if the site is suitable. The state of Nevada has resisted these efforts: it has denied permits, brought suit against DOE, and publicly denounced the federal government's decision to study Yucca Mountain. The state's opposition reflects public opinion in Nevada, and has considerably slowed DOE's progress in studying the site. The Yucca Mountain controversy demonstrates the importance of understanding public attitudes and their potential influence as DOE develops a program to manage radioactive waste. The strength and nature of Nevada's opposition -- its ability to thwart if not outright derail DOE's activities -- indicate a need to develop alternative methods for making decisions that affect the public. This report analyzes public participation as a key component of this openness, one that provides a means of garnering acceptance of, or reducing public opposition to, DOE's radioactive waste management activities, including facility siting and transportation. The first section, Public Perceptions: Attitudes, Trust, and Theory, reviews the risk-perception literature to identify how the public perceives the risks associated with radioactivity. DOE and the Public discusses DOE's low level of credibility among the general public as the product, in part, of the department's past actions. This section looks at the three components of the radioactive waste management program -- disposal, storage, and transportation -- and the different ways DOE has approached the problem of public confidence in each case. Midwestern Radioactive Waste Management Histories focuses on selected Midwestern facility-siting and transportation activities involving radioactive materials

  8. Public involvement in radioactive waste management decisions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-04-01

    Current repository siting efforts focus on Yucca Mountain, Nevada, where DOE`s Office of Civilian Radioactive Waste Management (OCRWM) is conducting exploratory studies to determine if the site is suitable. The state of Nevada has resisted these efforts: it has denied permits, brought suit against DOE, and publicly denounced the federal government`s decision to study Yucca Mountain. The state`s opposition reflects public opinion in Nevada, and has considerably slowed DOE`s progress in studying the site. The Yucca Mountain controversy demonstrates the importance of understanding public attitudes and their potential influence as DOE develops a program to manage radioactive waste. The strength and nature of Nevada`s opposition -- its ability to thwart if not outright derail DOE`s activities -- indicate a need to develop alternative methods for making decisions that affect the public. This report analyzes public participation as a key component of this openness, one that provides a means of garnering acceptance of, or reducing public opposition to, DOE`s radioactive waste management activities, including facility siting and transportation. The first section, Public Perceptions: Attitudes, Trust, and Theory, reviews the risk-perception literature to identify how the public perceives the risks associated with radioactivity. DOE and the Public discusses DOE`s low level of credibility among the general public as the product, in part, of the department`s past actions. This section looks at the three components of the radioactive waste management program -- disposal, storage, and transportation -- and the different ways DOE has approached the problem of public confidence in each case. Midwestern Radioactive Waste Management Histories focuses on selected Midwestern facility-siting and transportation activities involving radioactive materials.

  9. Technology for commercial radioactive waste management

    International Nuclear Information System (INIS)

    A general analysis of transportation requirements for postfission radioactive wastes that are produced from the commercial light water reactor (LWR) fuel cycle and that are assumed to require Federal custody for storage or disposal is given. Possible radioactive wastes for which transportation requirements are described include: spent fuel, solidified high-level waste, fuel residues (cladding wastes), plutonium, and non-high-level transuranic (TRU) wastes. Transportation is described for wastes generated in three fuel cycle options: once-through fuel cycle, uranium recycle only, and recycle of uranium and plutonium. The geologic considerations essential for repository selection, the nature of geologic formations that are potential repository media, the thermal criteria for waste placement in geologic repositories, and conceptual repositories in four different geologic media are described. The media are salt deposits, granite, shale, and basalt. Possible alternatives for managing retired facilities and procedures for decommissioning are reviewed. A qualitative comparison is made of wastes generated by the uranium fuel cycle and the thorium fuel cycle. This study presents data characterizing wastes from prebreeder light water breeder reactors using thorium and slightly enriched uranium-235. The prebreeder LWBRs are essentially LWRs using thorium. The operation of HTGR and LWBR cycles are conceptually designed, and wastes produced in these cycles are compared for potential differences

  10. Radioactive waste management - v. 2

    International Nuclear Information System (INIS)

    In this second part, the program of waste management of non-military origin of the following countries: USA, United Kingdom, France, Canada, Federal Republic of Germany, and Japan, is presented. For each country, a brief overview on its nuclear program, to identify the reason of the major emphasis done by this country for a specific waste management, is presented. The legislation control, the classification, the treatment and, the options for waste disposal are also presented. (M.C.K.)

  11. Waste water shows traces of radioactive substances

    International Nuclear Information System (INIS)

    Sludge at sewage treatment plants has been found to contain radioactive substances originating in hospitals, nuclear weapon tests, the Chernobyl accident, the Finnish nuclear power plants and natural sources. Radioactive substances also enter sewers together with excretions after patients have left the hospital. Hospitals used to let the excretions of patients receiving the iodine 131 treatment into the sewer system only after the activity of the excretions had decreased. Today, excretions can be led into the sewer directly. Calculations have shown that hospital staff receive higher radiation doses when the waste is collected than sewage treatment plant staff receive when the radioactive iodine is led directly into the sewer

  12. Annual report of waste generation and pollution prevention progress 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    This sixth Annual Report presents and analyzes DOE Complex-wide waste generation and pollution prevention activities at 36 reporting sites from 1993 through 1997. In May 1996, the Secretary of Energy established a 50 percent Complex-Wide Waste Reduction Goal (relative to the 1993 baseline) for routine operations radioactive and hazardous waste generation, to be achieved by December 31, 1999. Excluding sanitary waste, routine operations waste generation increased three percent from 1996 to 1997, and decreased 61 percent overall from 1993 to 1997. DOE has achieved its Complex-Wide Waste Reduction Goals for routine operations based upon a comparison of 1997 waste generation to the 1993 baseline. However, it is important to note that increases in low-level radioactive and low-level mixed waste generation could reverse this achievement. From 1996 to 1997, low-level radioactive waste generation increased 10 percent, and low-level mixed waste generation increased slightly. It is critical that DOE sites continue to reduce routine operations waste generation for all waste types, to ensure that DOE`s Complex-Wide Waste Reduction Goals are achieved by December 31, 1999.

  13. Annual report of waste generation and pollution prevention progress 1997

    International Nuclear Information System (INIS)

    This sixth Annual Report presents and analyzes DOE Complex-wide waste generation and pollution prevention activities at 36 reporting sites from 1993 through 1997. In May 1996, the Secretary of Energy established a 50 percent Complex-Wide Waste Reduction Goal (relative to the 1993 baseline) for routine operations radioactive and hazardous waste generation, to be achieved by December 31, 1999. Excluding sanitary waste, routine operations waste generation increased three percent from 1996 to 1997, and decreased 61 percent overall from 1993 to 1997. DOE has achieved its Complex-Wide Waste Reduction Goals for routine operations based upon a comparison of 1997 waste generation to the 1993 baseline. However, it is important to note that increases in low-level radioactive and low-level mixed waste generation could reverse this achievement. From 1996 to 1997, low-level radioactive waste generation increased 10 percent, and low-level mixed waste generation increased slightly. It is critical that DOE sites continue to reduce routine operations waste generation for all waste types, to ensure that DOE's Complex-Wide Waste Reduction Goals are achieved by December 31, 1999

  14. Process for the encapsulation of radioactive wastes

    International Nuclear Information System (INIS)

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

  15. Radioactive waste management in the former USSR

    Energy Technology Data Exchange (ETDEWEB)

    Bradley, D.J.

    1992-06-01

    Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

  16. Radioactive waste management in the former USSR

    International Nuclear Information System (INIS)

    Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes

  17. The Radioactive Waste Management Programme in Spain

    International Nuclear Information System (INIS)

    In 1984 the Empresa Nacional de Residuos Radiactivos (ENRESA) was set up in order to be responsible for all radioactive waste management activities in the country. ENRESA is a state-owned company, the shareholders of which are CIEMAT (Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas, formerly (JEN) and SEPI (Sociedad Estatal de Participaciones Industriales), both institutions dependent on the Ministry of Industry and Energy. ENRESA has a broad scope of responsibilities, including not only the management of L/ILW, HLW and spent fuel but also the decommissioning of nuclear installations, as well as the rehabilitation of uranium mining and milling facilities when required. The policy on radioactive waste management is defined by the Government, and the strategies are developed by ENRESA in accordance with the General Radioactive Waste Management Plan. This Plan is a strategic document which must be submitted yearly by ENRESA to the Government, for its approval when the Ministry of Industry and Energy decided so. The plan, in general terms, contains the main aspects related to waste generation and forecasts, as well as the strategies and technical solutions to be prepared, along with the associated economic and financial aspects. ENRESA's activities are financed by the waste producers. On the one hand the nucleoelectric sector pays a percentage fee on all the electricity sales, while small producers pay tariffs according to the services provided, both are approved by the Government. The fifth General Radioactive Waste Plan, approved by the Government in July 1999, is currently in force and contains the strategies for the management of radioactive wastes and decommissioning of nuclear installations in Spain. (author)

  18. Hanford Facility Annual Dangerous Waste Report Calendar Year 2002

    International Nuclear Information System (INIS)

    Hanford CY 2002 dangerous waste generation and management forms. The Hanford Facility Annual Dangerous Waste Report (ADWR) is prepared to meet the requirements of Washington Administrative Code Sections 173-303-220, Generator Reporting, and 173-303-390, Facility Reporting. In addition, the ADWR is required to meet Hanford Facility RCRA Permit Condition I.E.22, Annual Reporting. The ADWR provides summary information on dangerous waste generation and management activities for the Calendar Year for the Hanford Facility EPA ID number assigned to the Department of Energy for RCRA regulated waste, as well as Washington State only designated waste and radioactive mixed waste. The Solid Waste Information and Tracking System (SWITS) database is utilized to collect and compile the large array of data needed for preparation of this report. Information includes details of waste generated on the Hanford Facility, waste generated offsite and sent to Hanford for management, and other waste management activities conducted at Hanford, including treatment, storage, and disposal. Report details consist of waste descriptions and weights, waste codes and designations, and waste handling codes. In addition, for waste shipped to Hanford for treatment and/or disposal, information on manifest numbers, the waste transporter, the waste receiving facility, and the original waste generators are included. In addition to paper copies, electronic copies of the report are also transmitted to the regulatory agency

  19. Strategy and methodology for radioactive waste characterization

    International Nuclear Information System (INIS)

    Over the past decade, significant progress has been achieved in the development of waste characterization as well as control procedures and equipment. This has been as a direct response to ever-increasing requirements for quality and reliability of information on waste characteristics. Failure in control procedures at any step can have important, adverse consequences and may result in producing waste packages which are not compliant with the waste acceptance criteria for disposal, thereby adversely impacting the repository. The information and guidance included in this publication corresponds to recent achievements and reflects the optimum approaches, thereby reducing the potential for error and enhancing the quality of the end product. This publication discusses the strategy and methodology to be adopted in conceiving a characterization programme for the various kinds of radioactive waste fluxes or packages. No international publications have dealt with this topic in such depth. The strategy elaborated here takes into account the international State of the art in the different characterization methodologies. The strategy and methodology of the characterization programme will depend on the type of radioactive waste. In addition, the accuracy and quality of the characterization programme very much depends on the requirements to demonstrate compliance with the waste acceptance criteria. This publication presents a new subdivision of radioactive waste based on its physicochemical composition and its time dependence: simple/stable, complex/stable, simple/variable and complex/variable. Decommissioning and historical waste deserve special attention in this publication, and they can belong to any of the four categories. Identifying the life cycle of the radioactive waste is a cornerstone in defining the strategy for radioactive waste characterization. The waste acceptance criteria and the performance assessment of the repository are other key factors in the strategy and

  20. Radioactive waste management at ANSTO - Managing current and historic waste

    International Nuclear Information System (INIS)

    The Australian Nuclear Science and Technology Organisation (ANSTO) carries out nuclear research and development at Lucas Heights about 40 km southeast of Sydney, Australia. The 10 MW heavy water research reactor (HIFAR) has operated at Lucas Heights site for over 40 years with associated radioisotope and radiopharmaceutical production facilities and a wide range of nuclear science and technology R and D is carried out. Most of the radioactive waste generated by these activities is stored at the site. Following a review of ANSTO's waste management facilities and practices in 1996, an integrated five-year Waste Management Action Plan (WMAP) was established to address legacy issues and ensure that ANSTO waste management met international standards. Topics undertaken under the Waste Management Action Plan (WMAP) included construction and operation of improved storage facilities for low-level solid radioactive waste, better monitoring of storage facilities for spent research reactor fuel and intermediate level liquid wastes, development of processes to convert liquid and solid wastes into forms more suitable for long term storage and disposal, improved characterisation of wastes and development of a database for radioactive waste. (author)

  1. Passive storage of radioactive waste

    International Nuclear Information System (INIS)

    The absence of a policy for long-term management of either intermediate- or high-level waste has led to increased emphasis by both regulators and waste producers on long-term storage in regimes in which the need for human intervention is minimised. The concepts of 'passivity' of waste and its 'passive storage' have been much discussed, and their attributes defined. However, there has been a tendency to take 'passive' as an absolute, which it simply cannot be. This paper discusses passivity and passive storage, suggests definitions for relevant terms, and makes a case for a semi-quantitative index to measure the level of passivity represented by a given waste inventory. It also suggests that such an index would prove a valuable tool for judging the progress of waste treatment and decommissioning programmes. Further, increasing passivity may well reduce security concerns, and a preliminary discussion of this concept is presented. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Kang Il; Jeong, Noh Gyeom; Moon, Young Pyo; Jeong, Mi Seon; Park, Jin Beak [Korea Radioactive Waste Agency, Daejeon (Korea, Republic of)

    2016-03-15

    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.

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

    International Nuclear Information System (INIS)

    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

  4. FUETAP concrete - an alternative radioactive waste host

    International Nuclear Information System (INIS)

    These tailored autoclaved concretes (FUETAP concentrates) offer a number of advantages as hosts for a wide variety of radioactive wastes. They are formed at low temperatures and pressures (1000C and 0.1 MPa) from readily available raw materials and require no new processing technology. The extreme latitude in concrete formulations ensures the acceptance of the gamut of waste materials. The leachability of nuclides from the resulting ceramic-like concretes is quite low with essentially no prospect of pressure build-up from long-term self-irradiation in the final storage containers. The solids are thermally stable up to at least 9000C. Additional studies are in progress to verify that FUETAP concretes are acceptable alternative waste hosts for defense, TRU, and commercial high-level radioactive waste. (orig.)

  5. Characterization of radioactive waste forms. Volume 2

    International Nuclear Information System (INIS)

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

  6. Characterization of radioactive waste forms. Volume 1

    International Nuclear Information System (INIS)

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

  7. Probabilistic interpretation of radioactive waste assay

    International Nuclear Information System (INIS)

    The non-destructive assay of radioactive wastes from nuclear power plants and fuel cycle facilities is required for assessing the disposal risks. Such assay is influenced by two distinct facts: the statistical uncertainty of the measurement and the spatial uncertainty due to the random or at least unknown spatial distribution of the assayed material in a waste container. In this paper a probabilistic interpretation procedure is presented for a single-detector assay system of nuclear waste by one-shot passive gamma technique. The key parameter for this study, the average escape probability for photons, has been obtained by a specific-purpose Monte Carlo code, MCRW. The code has been developed to simulate the entire pulse height spectral responses for point sources located within the compartment which is the basic idea describing the degree of spatial homogeneity of the nuclear and matrix materials. The methodology presented here can be extended to actual radioactive waste assay

  8. File: contaminated sites and old radioactive wastes

    International Nuclear Information System (INIS)

    The present file treats old wastes and contaminated sites. The purpose is to realize an inventory of sites in relation with the right of future generations in matter of radioactive wastes management. The military and civil sites are reviewed, the nuclear and conventional industry, the french and foreign practices are compared. The process of site rehabilitation is exposed, in practice and administration procedures. (N.C.)

  9. Combustion synthesis of radioactive waste immobilization

    Institute of Scientific and Technical Information of China (English)

    ZHANG Ruizhu; GUO Zhimeng; LU Xin; JIA Chengchang; LIN Tao

    2005-01-01

    Using chromium oxide (CrO3) as an oxidant, the immobilization of simulating radioactive waste in perovskite (CaTiO3) structure by a combustion synthesis (CS) method was tested. The products were characterized by Archimedes liquid displacement technique, microhardness technique, X-ray diffraction, and scanning electron microscopy. The leaching rate was measured by the method of MCC-1 or MCC-2.The primary results show that the CS method can be used to solidify the immobilizate waste effectively.

  10. Conflict, public communication, and radioactive waste management

    International Nuclear Information System (INIS)

    Of the technical, political, and social problems associated with radioactive waste management, least is known about the latter two. Lay persons tend to generalize negative attitudes about other nuclear activity to radioactive waste management. Thus, conflict appears inevitable between the general public, citizen action groups, and decision-makers on radioactive waste management. The basis of conflict can be found in the value orientation of certain groups and in differing perceptions of risk. The paper is in three parts. First the sources of conflict over radioactive waste management issues are reviewed. The negative attitudes and fears of the public toward different types of projects involving radioactivity, value conflicts, and differential perceptions of risk are cited as sources. Next are discussed the consequences of conflict in terms of sociological theory. Finally, discussed is how conflict can be directed and managed to produce an informed decision-making process. When the public is sensitized to an issue, when prevailing attitudes on the issue are negative, and when perceived risks are high - all of which are characteristic of waste management issues - specific steps should be taken to establish a legitimate process of communication and interaction between the public and the sponsor agency. When conflict is recognized as inevitable, the goal of a communications programs is no longer to avoid it. It is to use the increased awareness to increase knowledge about waste management issues and public participation in decisions so that the final solution is acceptable at some level to all parties. Other benefits, such as increased agency/group cohesion, can also be realized as consequence of conflict

  11. Guide for the control and recording of radioactive wastes

    International Nuclear Information System (INIS)

    This guide present the aspects related to the control and recording of radioactive wastes in their points of origin. Then it is of great importance to fulfill these instructions so as to achieve a successful management of radioactive waste

  12. 2013 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site, Nye County, Nevada; Review of the Performance Assessments and Composite Analyses

    Energy Technology Data Exchange (ETDEWEB)

    Shott, Gregory [NSTec

    2014-03-01

    The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (National Security Technologies, LLC 2007a) requires an annual review to assess the adequacy of the performance assessments (PAs) and composite analyses (CAs), with the results submitted to the U.S. Department of Energy (DOE) Office of Environmental Management. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (DOE 1999a, 2000). The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office performed an annual review of the Area 3 and Area 5 RWMS PAs and CAs for fiscal year (FY) 2013. This annual summary report presents data and conclusions from the FY 2013 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada National Security Site (NNSS) relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs. Important developments in FY 2013 include the following: • Development of a new Area 5 RWMS closure inventory estimate based on disposals through FY 2013 • Evaluation of new or revised waste streams by special analysis • Development of version 4.115 of the Area 5 RWMS GoldSim PA/CA model The Area 3 RWMS has been in inactive status since July 1, 2006, with the last shipment received in April 2006. The FY 2013 review of operations

  13. Progress in radioactive graphite waste management

    International Nuclear Information System (INIS)

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

  14. Radioactive waste products - suitability for final disposal

    International Nuclear Information System (INIS)

    48 papers were read at the conference. Separate records are available for all of them. The main problem in radioactive waste disposal was the long-term sealing to prevent pollution of the biosphere. Problems of conditioning, acceptance, and safety measures were discussed. Final disposal models and repositories were presented. (PW)

  15. Radioactive waste products 2002 (RADWAP 2002). Proceedings

    International Nuclear Information System (INIS)

    The 4th International Seminar on Radioactive Waste Products was organised by the Forschungszentrum Juelich in co-operation with the Bundesamt fuer Strahlenschutz and the European Commission. On behalf of the Bundesamt, I would like to welcome all participants of this scientific-technical meeting. I very much appreciate the participation not only of numerous German scientists, engineers and technicians as well as governmental and industrial representatives, but would particularly express my gratitude for the participation of many colleagues from abroad. Radioactive waste management and disposal is a worldwide issue and international co-operation to support national programmes is therefore much appreciated. The international organisations provide, among other things, guidance to member countries on safe, economic and environmentally acceptable solutions for radioactive waste disposal. On a national basis respective programmes are developed, modified or successfully realized. Nevertheless, the challenge of radioactive waste management and disposal is no longer a scientific and technical exclusivity. The importance of ethical and social aspects, the dialogue with the public and transparency in decision-making processes increase more and more. Thus, when addressing safety-related key questions one needs to be as open as possible on scientific-technical aspects and to consider the involvement of the public requiring a clear, open-minded and transparent communication. (orig.)

  16. Radioactive waste management: A status report

    International Nuclear Information System (INIS)

    This publication briefly summarizes the activities of the IAEA and its Member States in the area of radioactive waste management. The information is presented in two major sections. One section presents a brief overview of the Agency's programme, and the other section provides a status report on the activities in many of the Agency's Member States

  17. The overall strategy for radioactive waste management

    International Nuclear Information System (INIS)

    Irrespective of the future use of nuclear technologies, there will continue to be a need for the safe management of radioactive waste. UK Nirex Ltd was established to perform this task. Whilst not technically difficult, the work has involved responding to government policy, and highlighted the challenging problem of public acceptance. (author)

  18. High-level radioactive wastes. Supplement 1

    International Nuclear Information System (INIS)

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

  19. Some new concepts in the field of radioactive waste management

    International Nuclear Information System (INIS)

    The author would like to introduce some new concepts in the field of radioactive waste management, which was presented by the ICRP and the IAEA in recent years, such as whole process of management for radioactive wastes; safe assessment applying constrained optimization for the disposal of long-lived solid radioactive wastes, and the optimization is a judgmental process, and so on. These new concepts are helpful to the safe management of radioactive wastes

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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.)

  2. Report of safety of the characterizing system of radioactive waste

    International Nuclear Information System (INIS)

    Report of safety of the system of radioactive waste of the ININ: Installation, participant personnel, selection of the place, description of the installation, equipment. Proposed activities: operations with radioactive material, calibration in energy, calibration in efficiency, types of waste. Maintenance: handling of radioactive waste, physical safety. Organization: radiological protection, armor-plating, personal dosemeter, risks and emergency plan, environmental impact, medical exams. (Author)

  3. Must we be afraid by the radioactive waste?

    International Nuclear Information System (INIS)

    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.)

  4. National facilities for the management of institutional radioactive waste in Romania

    International Nuclear Information System (INIS)

    The management of the non-fuel cycle radioactive wastes from all over Romania is centralized at IFIN-HH in the Radioactive Waste Treatment Plant (STDR). Final disposal is carried out at the National Repository of Radioactive Wastes (DNDR) at Baita Bihor. Radioactive waste treated at STDR arise from three main sources: 1. Wastes arising from the WWR-S research reactor during operation and the future decommissioning works; 2. Local waste from other facilities operating on IFIN-HH site. These sources include wastes generated during the normal activities of the STDR; 3. Wastes from IFIN-HH off site facilities and activities including medical, biological, and industrial applications all over the country. The Radiochemical Production Center, operating within IFIN-HH is the most important source of low and intermediate level radioactive wastes (liquid and solid), as the operational wastes arising from processing at STDR are. The STDR basically consists of liquid and solid waste treatment and conditioning facilities, a radioactive decontamination centre, a laundry and an intermediate storage area. The processing system of the STDR are located at six principal areas performing the following activities: 1. Liquid effluent treatment; 2. Burning of combustible solid stuff; 3. Compaction of solid non-combustible stuff; 4. Cement conditioning; 5. Radioactive decontamination; 6. Laundry. The annual designed treatment capacity of the plant is 1500 m3 Low Level Aqueous Waste, 100 m3 Low Level Solid Waste and shielded drums for Intermediate Level Waste. The temporary storage within and final disposal of waste in the frame of DNDR are explained as well as the up-dating of institutional radioactive waste infrastructure

  5. Radioactive Waste Burial Grounds. Environmental Information Document

    Energy Technology Data Exchange (ETDEWEB)

    Jaegge, W.J.; Kolb, N.L.; Looney, B.B.; Marine, I.W.; Towler, O.A.; Cook, J.R.

    1987-03-01

    This document provides environmental information on postulated closure options for the Radioactive Waste Burial Grounds at the Savannah River Plant and was developed as background technical documentation for the Department of Energy`s proposed Environmental Impact Statement (EIS) on waste management activities for groundwater protection at the plant. The results of groundwater and atmospheric pathway analyses, accident analysis, and other environmental assessments discussed in this document are based upon a conservative analysis of all foreseeable scenarios as defined by the National Environmental Policy Act (CFR, 1986). The scenarios do not necessarily represent actual environmental conditions. This document is not meant to be used as a closure plan or other regulatory document to comply with required federal or state environmental regulations. The closure options considered for the Radioactive Waste Burial Grounds are waste removal and closure, no waste removal and closure, and no action. The predominant pathways for human exposure to chemical and/or radioactive constituents are through surface, subsurface, and atmospheric transport. Modeling calculations were made to determine the risks to human population via these general pathways for the three postulated closure options. An ecological assessment was conducted to predict the environmental impacts on aquatic and terrestrial biota. The relative costs for each of the closure options were estimated.

  6. Radioactive waste disposal in the United Kingdom

    International Nuclear Information System (INIS)

    Currently the policy of the United Kingdom Government is that HLW should be stored in a suitable facility for at least fifty years before considering further storage or final disposal. This period allows many short-lived radionuclides, but more importantly, the associated radioactive decay heat, to diminish ahead of disposal. For intermediate-level solid wastes current policy is to develop, as soon as possible, a suitable deep geological facility for its permanent disposal. LLW constitutes the majority by volume of all radioactive waste. The waste arises not only from the nuclear industry, but also from all users of radioactive substances, such as hospitals, research establishments and industry. At present, it is mainly disposed of at a 300-acre site at Drigg in Cumbria, operated by British Nuclear Fuels plc (BNEL). It is packed into containers and placed in concrete-lined trenches which are subsequently sealed. Drigg is expected to continue to take solid low-level wastes for many years. Original plans-term disposal route for LLW involved disposal in a new near-surface repository. However, in 1987, this proposal was abandoned, on cost-benefit arguments, and the Government agreed that a yet to be developed national deep repository should also be used for some LLW. Drigg is expected to continue to take solid low-level wastes for many years.

  7. Ceramic and glass radioactive waste forms

    Energy Technology Data Exchange (ETDEWEB)

    Readey, D.W.; Cooley, C.R. (comps.)

    1977-01-01

    This report contains 14 individual presentations and 6 group reports on the subject of glass and polycrystalline ceramic radioactive waste forms. It was the general consensus that the information available on glass as a waste form provided a good basis for planning on the use of glass as an initial waste form, that crystalline ceramic forms could also be good waste forms if much more development work were completed, and that prediction of the chemical and physical stability of the waste form far into the future would be much improved if the basic synergistic effects of low temperature, radiation and long times were better understood. Continuing development of the polycrystalline ceramic forms was recommended. It was concluded that the leach rate of radioactive species from the waste form is an important criterion for evaluating its suitability, particularly for the time period before solidified waste is permanently placed in the geologic isolation of a Federal repository. Separate abstracts were prepared for 12 of the individual papers; the remaining two were previously abstracted.

  8. Leaching tests of cemented organic radioactive waste

    International Nuclear Information System (INIS)

    The use of radioisotopes in research, medical and industrial activities generates organic liquid radioactive wastes. At Centro de Desenvolvimento da Tecnologia Nuclear (CDTN) are produced organic liquid wastes from different sources, one of these are the solvent extraction activities, whose the waste volume is the largest one. Therefore a research was carried out to treat them. Several techniques to treat organic liquid radioactive wastes have been evaluated, among them incineration, oxidation processes, alkaline hydrolysis, distillation, absorption and cementation. Laboratory experiments were accomplished to establish the most adequate process in order to obtain qualified products for storage and disposal. Absorption followed by cementation was the procedure used in this study, i.e. absorbent substances were added to the organic liquid wastes before mixing with the cement. Initially were defined the absorbers, and evaluated the formulation in relation to the compressive strength of its products. Bentonite from different suppliers (B and G) and vermiculite in two granulometries (M - medium and F - small) were tested. In order to assess the product quality the specimens were submitted to the leaching test according the Standard ISO 6961 and its results were evaluated. Then they were compared with the values established by Standard CNEN NN 6.09 Acceptance criteria for waste products to be disposed, to verify if they meet the requirements for safely storage and disposal. Through this study the best formulations to treat the organic wastes were established. (author)

  9. Soluble pig for radioactive waste transfer lines

    International Nuclear Information System (INIS)

    Flushing transfer pipe after radioactive waste transfers generates thousands of gallons of additional radioactive waste each year at the Hanford site. The use of pneumatic pigging with waste soluble pigs as a means to clear transfer piping may be an effective alternative to raw water flushes. A feasibility study was performed by a group of senior mechanical engineering students for their senior design project as part of their curriculum at Washington State University. The students divided the feasibility study into three sub-projects involving: (1) material research, (2) delivery system design, and (3) mockup fabrication and testing. The students screened through twenty-three candidate materials and selected a thermoplastic polymer combined 50:50 wt% with sucrose to meet the established material performance criteria. The students also prepared a conceptual design of a remote pneumatic delivery system and constructed a mockup section of transfer pipe for testing the prototype pigs

  10. Handbook of high-level radioactive waste transportation

    Energy Technology Data Exchange (ETDEWEB)

    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.

  11. Radioactive waste management in the Czech Republic

    International Nuclear Information System (INIS)

    Radioactive waste and spent nuclear fuel are generated in the Czech Republic as a consequence of the peaceful use of nuclear energy and ionising radiation in many industries, particularly in the generation of nuclear energy, health care (therapy, diagnostics), research, and agriculture. The current extent of utilisation of nuclear energy and ionising radiation in the Czech Republic is comparable with that of other developed countries. The Concept of Radioactive Waste and Spent Nuclear Fuel Management is a fundamental document formulating government and state authority strategy for the period up to approximately 2025 (affecting policy up to the end of the 21st century), concerning the organizations which generate radioactive waste and spent nuclear fuel. The Concept puts forward solutions to provide for the disposal of waste in compliance with requirements for the protection of human health and the environment without excessively transferring any of the current impacts of nuclear energy and ionising radiation utilisation to future generations. The Concept was approved by the government of the Czech Republic in 2002. According to the Concept high level waste and spent nuclear fuel generated at the Dukovany and Temelin nuclear power plants will eventually be disposed of in a deep geological repository. Such a repository should commence operation in 2065. Work aimed at selecting potentially suitable sites began in 1992, but the final site has not yet been determined. In compliance with the aforementioned Concept, the Radioactive Waste Repository Authority (RAWRA) is responsible for finding two suitable sites before 2015. The current stage of evaluation covers the whole of the Czech Republic and includes detailed criteria and requirements. Based on the latest findings RAWRA suggested six potential sites for further investigation at the beginning of 2003. (author)

  12. 2009 National inventory of radioactive material and wastes. Synthesis report

    International Nuclear Information System (INIS)

    Third edition of the ANDRA's national inventory report on radioactive wastes that are present on the French territory (as recorded until december, 2007). After a brief historical review of the national inventory and the way it is constructed, the report gives the basics on radioactive wastes, their classification, origins and management processes, followed by a general presentation and discussion of the inventory results (radioactive wastes and materials). Results are then detailed for the different activity sectors using radioactive materials (nuclear industry, medical domain, scientific research, conventional industry, Defense...). Information is also given concerning radioactive polluted areas (characterization and site management) and radioactive waste inventories in various foreign countries

  13. Radioactive waste vitrification: A review

    International Nuclear Information System (INIS)

    The research and development of an immobilization process for the containment of nuclear high-level liquid waste has been underway for well-over the past four decades. The method that has become the state-of-the-art is the liquid-fed ceramic melter process which converts a mixture of high-level liquid waste and glass forming frit to a borosilicate glass product. This report gives a chronological review of the various vitrification processes starting with the very first reported process in 1960. Information on the early methods of frit selection as well as information on the currently computerized method are presented. The importance of all these parameters is discussed with regard to product durability. 26 refs., 8 figs., 1 tab

  14. CEA and its radioactive wastes; Le CEA a l'epreuve de ses dechets

    Energy Technology Data Exchange (ETDEWEB)

    Marano, S

    1999-06-01

    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.)

  15. An update of a national database of low-level radioactive waste in Canada

    Energy Technology Data Exchange (ETDEWEB)

    De, P.L.; Barker, R.C. [Atomic Energy Canada Ltd. Research, Ottawa, Ontario (Canada). Low-Level Radioactive Waste Management Office

    1993-03-01

    This paper gives an overview and update of a national database of low-level radioactive waste in Canada. To provide a relevant perspective, Canadian data are compared with US data on annual waste arisings and with disposal initiatives of the US compacts and states. Presented also is an assessment of the data and its implications for disposal solutions in Canada.

  16. Radioactive waste containment - a literature study

    International Nuclear Information System (INIS)

    One of the basic requirements of safe radioactive waste disposal is isolation of the radioactive substances to prevent leakage into the biosphere. The multi-barrier concept has been developed to meet this requirement. Within the framework of the concept, barriers can be either natural or man-made. Natural barriers, i.e. geologic formations,have been investigated for their suitability, with host rock and their different properties being determined and compared. It has been found that the qualification of a proposed repository medium cannot be defined on the basis of physical, chemical, and mineralogical criteria alone, but that these data have to be completed by a global evaluation of the entire system consisting of waste products and waste forms, host rock, and surrounding rock. The study in hand reviews the reports and also lists the studies made on engineered barriers, as e.g. immobilisation barriers, container and package barriers, of various waste forms. A review of the studies dealing with the various waste disposal techniques shows that the sub-surface waste disposal and the deep underground disposal in mines are the best developed techniques currently. A review of ultimate disposal concepts adopted abroad shows that most countries favour the mining technology approach, with the exception of Denmark where R and D work in this field is focused on deep well disposal. (orig./HP)

  17. Annual Report on Waste Generation and Waste Minimization Progress, 1991--1992

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    This report is DOE`s first annual report on waste generation and waste minimization progress. Data presented in this report were collected from all DOE sites which met minimum threshold criteria established for this report. The fifty-seven site submittals contained herein represent data from over 100 reporting sites within 25 states. Radioactive, hazardous and sanitary waste quantities and the efforts to minimize these wastes are highlighted within the fifty-seven site submittals. In general, sites have made progress in moving beyond the planning phase of their waste minimization programs. This is evident by the overall 28 percent increase in the total amount of materials recycled from 1991 to 1992, as well as individual site initiatives. During 1991 and 1992, DOE generated a total of 279,000 cubic meters of radioactive waste and 243,000 metric tons of non-radioactive waste. These waste amounts include significant portions of process wastewater required to be reported to regulatory agencies in the state of Texas and the state of Tennessee. Specifically, the Pantex Plant in Texas treats an industrial wastewater that is considered by the Texas Water Commission to be a hazardous waste. In 1992, State regulated wastewater from the Pantex Plant represented 3,620 metric tons, 10 percent of the total hazardous waste generated by DOE. Similarly, mixed low-level wastewater from the TSCA Incinerator Facility at the Oak Ridge K-25 Site in Tennessee represented 55 percent of the total radioactive waste generated by DOE in 1992.

  18. Annual Report on Waste Generation and Waste Minimization Progress, 1991--1992

    International Nuclear Information System (INIS)

    This report is DOE's first annual report on waste generation and waste minimization progress. Data presented in this report were collected from all DOE sites which met minimum threshold criteria established for this report. The fifty-seven site submittals contained herein represent data from over 100 reporting sites within 25 states. Radioactive, hazardous and sanitary waste quantities and the efforts to minimize these wastes are highlighted within the fifty-seven site submittals. In general, sites have made progress in moving beyond the planning phase of their waste minimization programs. This is evident by the overall 28 percent increase in the total amount of materials recycled from 1991 to 1992, as well as individual site initiatives. During 1991 and 1992, DOE generated a total of 279,000 cubic meters of radioactive waste and 243,000 metric tons of non-radioactive waste. These waste amounts include significant portions of process wastewater required to be reported to regulatory agencies in the state of Texas and the state of Tennessee. Specifically, the Pantex Plant in Texas treats an industrial wastewater that is considered by the Texas Water Commission to be a hazardous waste. In 1992, State regulated wastewater from the Pantex Plant represented 3,620 metric tons, 10 percent of the total hazardous waste generated by DOE. Similarly, mixed low-level wastewater from the TSCA Incinerator Facility at the Oak Ridge K-25 Site in Tennessee represented 55 percent of the total radioactive waste generated by DOE in 1992

  19. Geological problems in radioactive waste isolation

    Energy Technology Data Exchange (ETDEWEB)

    Witherspoon, P.A. (ed.)

    1991-01-01

    The problem of isolating radioactive wastes from the biosphere presents specialists in the fields of earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high level waste (HLW) which must be isolated in the underground and away from the biosphere for thousands of years. Essentially every country that is generating electricity in nuclear power plants is faced with the problem of isolating the radioactive wastes that are produced. The general consensus is that this can be accomplished by selecting an appropriate geologic setting and carefully designing the rock repository. Much new technology is being developed to solve the problems that have been raised and there is a continuing need to publish the results of new developments for the benefit of all concerned. The 28th International Geologic Congress that was held July 9--19, 1989 in Washington, DC provided an opportunity for earth scientists to gather for detailed discussions on these problems. Workshop W3B on the subject, Geological Problems in Radioactive Waste Isolation -- A World Wide Review'' was organized by Paul A Witherspoon and Ghislain de Marsily and convened July 15--16, 1989 Reports from 19 countries have been gathered for this publication. Individual papers have been cataloged separately.

  20. Geological problems in radioactive waste isolation

    International Nuclear Information System (INIS)

    The problem of isolating radioactive wastes from the biosphere presents specialists in the fields of earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high level waste (HLW) which must be isolated in the underground and away from the biosphere for thousands of years. Essentially every country that is generating electricity in nuclear power plants is faced with the problem of isolating the radioactive wastes that are produced. The general consensus is that this can be accomplished by selecting an appropriate geologic setting and carefully designing the rock repository. Much new technology is being developed to solve the problems that have been raised and there is a continuing need to publish the results of new developments for the benefit of all concerned. The 28th International Geologic Congress that was held July 9--19, 1989 in Washington, DC provided an opportunity for earth scientists to gather for detailed discussions on these problems. Workshop W3B on the subject, ''Geological Problems in Radioactive Waste Isolation -- A World Wide Review'' was organized by Paul A Witherspoon and Ghislain de Marsily and convened July 15--16, 1989 Reports from 19 countries have been gathered for this publication. Individual papers have been cataloged separately

  1. Bulgaria: Novi Han radioactive waste repository

    International Nuclear Information System (INIS)

    The Novi Han radioactive waste repository is the only national radioactive waste disposal site in Bulgaria. It is located in Losen mountain, 6.5 km from the small village of Novi Han and 35 km from the capital, Sofia. The repository accepts radioactive waste generated from nuclear applications in industry, medicine, research and education. The facility was constructed according to a modified Soviet design (type TP-4891). Its construction licence was issued in 1959 and that for commissioning in 1964. The repository was specially built for the needs of the IRT-2000 research reactor operated by the Institute of Physics and other academic and medical facilities. In 1959, the Government appointed the Physical Institute of the Bulgarian Academy of Sciences, whose successor is now the Institute for Nuclear Research and Nuclear Energy (INRNE), as the central authority for the collection and disposal of radioactive waste from nuclear applications. The Novi Han repository site covers an area of 4.25 ha.1 The site is divided into two areas separated by a fence. One area contains the administrative buildings, garage and maintenance shops. The other contains the disposal facilities, radiochemical laboratory and decontamination station. The repository consists of (1) a concrete vault for low and intermediate level solid wastes, which consists of 3 separate cells with a total volume of 237 m3, (2) a concrete vault for biological wastes with a volume of 80 m3, (3) four steel tanks for storage of low level liquid wastes with a total volume of 48 m3, (4) a special 1 m3 concrete vault for spent sealed sources and (5) a concrete trench for solid waste, which consists of 7 separate units with a total volume of 200 m3. Waste acceptance criteria follow Regulation No. 7 of the Committee on the Use of Atomic Energy for Peaceful Purposes on Collection, Treatment, Storage, Transport and Disposal of Radioactive Wastes in the Territory of the Republic of Bulgaria. They take into account origin

  2. Environmental aspects of commercial radioactive waste management

    International Nuclear Information System (INIS)

    Volume 3 contains eight appendices: a reference environment for assessing environmental impacts associated with construction and operation of waste treatment, interim storage and/or final disposition facilities; dose calculations and radiologically related health effects; socioeconomic impact assessments; release/dose factors and dose in 5-year intervals to regional and world wide population from reference integrated systems; resource availability; environmental monitoring; detailed dose results for radionuclide migration groundwater from a waste repository; and annual average dispersion factors for selected release points

  3. Environmental aspects of commercial radioactive waste management

    Energy Technology Data Exchange (ETDEWEB)

    1979-05-01

    Volume 3 contains eight appendices: a reference environment for assessing environmental impacts associated with construction and operation of waste treatment, interim storage and/or final disposition facilities; dose calculations and radiologically related health effects; socioeconomic impact assessments; release/dose factors and dose in 5-year intervals to regional and world wide population from reference integrated systems; resource availability; environmental monitoring; detailed dose results for radionuclide migration groundwater from a waste repository; and annual average dispersion factors for selected release points. (LK)

  4. Combustible radioactive waste treatment by incineration and chemical digestion

    International Nuclear Information System (INIS)

    A review is given of present and planned combustible radioactive waste treatment systems in the US. Advantages and disadvantages of various systems are considered. Design waste streams are discussed in relation to waste composition, radioactive contaminants by amount and type, and special operating problems caused by the waste

  5. Radioactive waste management and decommissioning in The United States

    International Nuclear Information System (INIS)

    With their missions and access to disposal sites changing over the last decade, radioactive waste management and decommissioning practice in the U.S. commercial and federal nuclear markets has evolved to keep pace. This paper reviews the changes that have occurred and the differing waste management practices that have resulted depending on whether a nuclear facility is situated on federally owned or privately owned property in the United States, confirming that the cost of disposal generally dictates waste management and decommissioning practices. Of the 123 utility-owned licensed commercial reactors in U.S., 19 are undergoing decomissioning, with the balance of 104 reactors focusing on plant life extension, power upgrades, and power generation. As a result, almost all of the approximately dollar 400 million in annual expenditures on waste processing and disposal comes from waste generated from operations. In contrast, the U.S. Department of Energy (DOE), under its Environmental Management (EM) program, is focused on decommissioning the facilities, tanks, and ground contamination resulting from 50-years of Cold War activities and spending about dollar 7 billion a year on these activities. Other than spent fuel, U.S. federal law precludes disposal of commercial nuclear power plant radioactive wastes at DOE disposal sites. In contrast to the commercial disposal market, which must go through extensive public hearings and decision-making, the DOE has a much freer hand in siting new disposal capacity on federal land. As a result, the DOE has ample disposal capacity, 'routinely' opens new disposal sites, and enjoys disposal pricing well below the commercial market. Waste composition, volume, and activity levels drive disposal costs, which is the key life cycle parameter in determining radioactive waste management practice. Differences in these parameters drive the differences in how radioactive waste management practice is performed in the commercial and DOE markets

  6. Underground repository for radioactive wastes

    International Nuclear Information System (INIS)

    In the feasibility study for an underground repository in Argentina, the conceptual basis for the final disposal of high activity nuclear waste was set, as well as the biosphere isolation, according to the multiple barrier concept or to the engineering barrier system. As design limit, the container shall act as an engineering barrier, granting the isolation of the radionuclides for approximately 1000 years. The container for reprocessed and vitrified wastes shall have three metallic layers: a stainless steel inner layer, an external one of a metal to be selected and a thick intermediate lead layer preselected due to its good radiological protection and corrosion resistance. Therefore, the study of the lead corrosion behaviour in simulated media of an underground repository becomes necessary. Relevant parameters of the repository system such as temperature, pressure, water flux, variation in salt concentrations and oxidants supply shall be considered. At the same time, a study is necessary on the galvanic effect of lead coupled with different candidate metals for external layer of the container in the same experimental conditions. Also temporal evaluation about the engineering barrier system efficiency is presented in this thesis. It was considered the extrapolated results of corrosion rates and literature data about the other engineering barriers. Taking into account that corrosion is of a generalized type, the integrity of the lead shall be maintained for more than 1000 years and according to temporal evaluation, the multiple barrier concept shall retard the radionuclide dispersion to the biosphere for a period of time between 104 and 106 years. (Author)

  7. Transportation of radioactive wastes from nuclear fuel cycles

    International Nuclear Information System (INIS)

    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

  8. Radioactive Waste Management in the Republic of Lithuania

    International Nuclear Information System (INIS)

    Description of regulation of radioactive waste management in Lithuania, waste processing in Ignalina NPP is presented. On 2001 VATESI approved the regulations governing pre disposal waste management at the Ignalina NPP. The classification of radioactive waste was modified in accordance with the practice of the IAEA. Short information on radioactive waste forms in the cause of operation of Ignalina NPP is presented. Comparison with previous years is made. On July 2001 Radioactive Waste Management Agency (RATA) was established. Description of RATA's aims and activities is provided

  9. The 1989 United Kingdom radioactive waste inventory

    International Nuclear Information System (INIS)

    This report describes the stocks of radioactive wastes in the United Kingdom, together with projections of future arisings. Operational and decommissioning wastes are considered for both committed and prospective plant. Arisings are from power reactors, commercial reprocessing, fuel manufacture, medical and industrial sources and research and development. Data are presented for the wastes in their raw form and as conditioned for disposal. The data which refer to the situation on 1.1.89 are shown by producer and globally, in summary tables. The information presented for each producer includes a discussion of how stocks and arisings have changed from earlier predictions. This is supplemented by a stream by stream tabulation showing the waste type, volume, density, conditioning factor and specific activity for stocks and arisings. The global projections are presented in tabular and graphical manner, and the changes from earlier projections are discussed. The scenarios which underly the projections are presented. (author)

  10. Improvement of BWR radioactive waste disposal system

    International Nuclear Information System (INIS)

    Description is made here about the improvement of the disposal systems for liquid and solid radioactive waste in recent BWR plants. Regarding the improvement of liquid waste disposal systems in Toshiba, emphasis was laid on crud removal and laundry drain treatment; as a result, a crud removal system utilizing a centrifugal separation mechanism and an evaporative enriching system using anti-foaming agent have been practicalized. An important problem left for solution is the method of volume reduction of solid waste. A method attracting attention of late is the plastic solidification which is far superior to the conventional cement and bitumen solidification. In Toshiba, this method is promising to be practicalized, in which the waste is dried and then solidified with thermosetting resin. (author)

  11. Radioactive waste today - an asset tomorrow

    Energy Technology Data Exchange (ETDEWEB)

    Holmstrand, M. [Norwegian Radiation Protection Authority (Norway)

    2014-07-01

    Mining of Rare Earth Elements (REE) causes radioactive pollution, as ores which contain REE also contain an elevated concentration of naturally occurring radioactive materials (NORM). Wastes from REE mining are therefore regarded as being inherently radioactive. One of the potential economically viable REE resources in Norway is in the Fensfield area in Telemark County, which is recognized as one of the world's largest thorium resources. If REE was mined in this area, a large volume of radioactive waste would be created. The authorities would then need to know how to regulate the waste so that the environmental impact would be as low as reasonably achievable when societal and economic factors having been accounted for (ALARA). Radioactive pollution from REE tailings could be a threat to the environment, biota and humans. However, naturally occurring thorium is practically not mobile nor bioavailable and has a relatively low specific activity and might therefore safely be deposited in a landfill. An environmental risk assessment should be used to evaluate if it is justifiable to deposit the radioactive tailings in a landfill or if alternative ways of handling, such as extraction of thorium in addition to extraction of REE from the ore, might be better. The risk assessment must start with a source term, the native carbonatite rocks, and an investigation on how the chemical properties of the rock changes when it's milled and treated with chemicals. Changes in the physical and chemical properties and changes in the environment where the processed rock are deposited might mobilize and/or make thorium bioavailable, thus increasing the environmental risk. Removal of thorium from the raw materials or tailings from the REE mining industry prior to deposition could be seen as one form of environmental protection with many benefits, for instance reducing the potential of external and internal radiation in biota and humans. We could also speculate about the

  12. Radioactive waste today - an asset tomorrow

    International Nuclear Information System (INIS)

    Mining of Rare Earth Elements (REE) causes radioactive pollution, as ores which contain REE also contain an elevated concentration of naturally occurring radioactive materials (NORM). Wastes from REE mining are therefore regarded as being inherently radioactive. One of the potential economically viable REE resources in Norway is in the Fensfield area in Telemark County, which is recognized as one of the world's largest thorium resources. If REE was mined in this area, a large volume of radioactive waste would be created. The authorities would then need to know how to regulate the waste so that the environmental impact would be as low as reasonably achievable when societal and economic factors having been accounted for (ALARA). Radioactive pollution from REE tailings could be a threat to the environment, biota and humans. However, naturally occurring thorium is practically not mobile nor bioavailable and has a relatively low specific activity and might therefore safely be deposited in a landfill. An environmental risk assessment should be used to evaluate if it is justifiable to deposit the radioactive tailings in a landfill or if alternative ways of handling, such as extraction of thorium in addition to extraction of REE from the ore, might be better. The risk assessment must start with a source term, the native carbonatite rocks, and an investigation on how the chemical properties of the rock changes when it's milled and treated with chemicals. Changes in the physical and chemical properties and changes in the environment where the processed rock are deposited might mobilize and/or make thorium bioavailable, thus increasing the environmental risk. Removal of thorium from the raw materials or tailings from the REE mining industry prior to deposition could be seen as one form of environmental protection with many benefits, for instance reducing the potential of external and internal radiation in biota and humans. We could also speculate about the possibility that

  13. USDOE radioactive waste incineration technology: status review

    International Nuclear Information System (INIS)

    Early attempts were made to incinerate radioactive wastes met with operation and equipment problems such as feed preparation, corrosion, inadequate off-gas cleanup, incomplete combustion, and isotope containment. The US Department of Energy (DOE) continues to sponsor research, development, and the eventual demonstration of radioactive waste incineration. In addition, several industries are developing proprietary incineration system designs to meet other specific radwaste processing requirements. Although development efforts continue, significant results are available for the nuclear community and the general public to draw on in planning. This paper presents an introduction to incineration concerns, and an overview of the prominent radwaste incineration processes being developed within DOE. Brief process descriptions, status and goals of individual incineration systems, and planned or potential applications are also included

  14. Membrane permeation employed for radioactive wastes treatment

    International Nuclear Information System (INIS)

    In the paper certain aspects of development process aiming at reducing the radioactivity of liquid low-level waste streams (LLLW) are presented. The influence of gamma and electron radiation on ultrafiltration membranes has been studied and changes of their transport properties have been determined at different doses. Membrane processes: ultrafiltration (UF), seeded ultrafiltration (SUF), low-pressure reverse osmosis (LPRO) and membrane distillation (MD) have been examined. The UF/RO pilot plant for purification/concentration of low-level liquid waste is described. 4 refs., 2 figs

  15. Maintenance of records for radioactive waste disposal

    International Nuclear Information System (INIS)

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

  16. Guide to radioactive waste management literature

    Energy Technology Data Exchange (ETDEWEB)

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

    1977-10-01

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

  17. Guide to radioactive waste management literature

    International Nuclear Information System (INIS)

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

  18. Treatment of radioactive wastes from uranium concentrating

    International Nuclear Information System (INIS)

    Radioactive wastes from uranium and thorium ore processing pose potential environmental and public health problems because of their radioactivity and chemical composition. The radionuclides exist in these wastes are those resulting from the uranium 238, uranium 235 and thorium 232 decay series. The most important radionuclide in U 238 decay series are uranium 234, thorium 230, radium 226 and some short lived radionuclides such as radon-222. Radium 226 is the nuclide of principal concern from the standpoint of the assessment and control of the radiological hazard associated with the wastes. Thus determination of uranium, thorium and radium concentration in wastes resulting from nuclear fuel cycle is very important because of its potential hazard. Various analytical methods such as fluorimetry, neutron activation analysis, radon emanation, spectrophotometry and spectroscopy are used for determination of these radionuclides. Uranium and thorium are separated from interfering element by ion exchange chromatography and measured by spectrophotometry method using arsenazo III and thorin as indicator. Radium is separated from interfering elements and α-emitters by coprecipitation of radium barium sulphate and measured by counting α-particles with surface barrier detector. Regarding to physical and chemical characteristic of waste being investigated, decontamination factors and treatment methods, chemical precipitation and coprecipitation procedure were carried out in this research work. By adding barium chloride, radium is separated from liquid waste and optimum condition were determined. Precipitation with lime and sodium-hydroxide were also studied and good result were obtained. The results show that by neutralization of waste by lime and sodium hydroxide more than 99.9% of activity was removed from stream. Advantage and disadvantage of each methods were studied and finally, effluent resulted from treatment were discharged after analysis with γ-spectroscopy and

  19. Eleventh annual U.S. DOE low-level radioactive waste management conference: Executive summary, opening plenary, technical session summaries, and attendees

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-01-01

    The conference consisted of ten technical sessions, with three sessions running simultaneously each day. Session topics included: regulatory updates; performance assessment;understanding remedial action efforts; low-level waste strategy and planning (Nuclear Energy); low-level waste strategy and planning (Defense); compliance monitoring; decontamination and decommissioning; waste characterization; waste reduction and minimization; and prototype licensing application workshop. Summaries are presented for each of these sessions.

  20. Classification of Radioactive Waste. General Safety Guide (Spanish Edition)

    International Nuclear Information System (INIS)

    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

  1. 4th Quarter Transportation Report FY 2014: Radioactive Waste Shipments to and from the Nevada National Security Site (NNSS)

    Energy Technology Data Exchange (ETDEWEB)

    Gregory, Louis [National Security Technologies, LLC. (NSTec), Mercury, NV (United States)

    2014-12-02

    This report satisfies the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Field Office (NNSA/NFO) commitment to prepare a quarterly summary report of radioactive waste shipments to and from the Nevada National Security Site (NNSS) Radioactive Waste Management Complex (RWMC) at Area 5. There were no shipments sent for offsite treatment and returned to the NNSS this quarter. There was one shipment of two drums sent for offsite treatment and disposal. This report summarizes the 4th quarter of Fiscal Year (FY) 2014 low-level radioactive waste (LLW) and mixed low-level radioactive waste (MLLW) shipments. This report also includes annual summaries for FY 2014.

  2. The DMC process for radioactive waste treatment

    International Nuclear Information System (INIS)

    This paper describes AEA Technology's patented Direct Membrane Cleaning (DMC) technology for enhancing the filtration of finely divided solids from aqueous streams. Electrolytically generated, microscopic gas bubbles at the membrane surface remove the superficial fouling layer, enching the permeation rate of the membrane. DMC technology has been demonstrated for ultrafilters and microfilters; several applications are summarized, including radioactive waste treatment and non-nuclear applications

  3. Commercial radioactive waste disposal: marriage or divorce

    International Nuclear Information System (INIS)

    It is shown that the state (South Carolina) is doing a good job in regulating the South Carolina disposal facility of Chemo-Nuclear Inc., and that there is no need for the NRC to reassert Federal control. The efforts in developing a low-level site in New Mexico are described. The NRC Task Force report on Federal/state regulation of commercial low-level radioactive waste burial grounds is discussed

  4. High-level radioactive wastes. Supplement 1

    Energy Technology Data Exchange (ETDEWEB)

    McLaren, L.H. (ed.)

    1984-09-01

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

  5. Social impacts of radioactive waste disposal

    International Nuclear Information System (INIS)

    In this report an approach is developed for the assessment of socio-economic impacts from radioactive waste disposal. The approach provides recommendations on procedures to be used in identification and prediction of impacts. Two decision-aiding methods are also included. The first provides for the identification of key issues and the illustration of the trade-offs involved in the decision. Multi-attribute scoring and weighting techniques are then proposed for the illustration of impacts using quantitative measures. (author)

  6. Radioactive waste repository of high ecological safety

    International Nuclear Information System (INIS)

    With the purpose to construct a radioactive waste repository of high ecological safety and reliable containment, MosNPO 'Radon' specialists have developed an advanced type repository - large diameter well (LBD) one. A project is started for the development of a technology for LDW repository construction and pilot operation of the new repository for 25-30 years. The 2 LDW repositories constructed at the 'Radon' site and the developed monitoring system are described

  7. Radioactive waste unpacking device and method

    International Nuclear Information System (INIS)

    Radioactive wastes packed in a containing bag comprising vinyl chloride and vinyl acetate are transported to a crushing chamber by way of a transporting device. The crushing chamber is sealed, vibrated and, further, supplied with a low temperature gas by a supply device. The containing bag is frozen and embrittled by a low temperature atmosphere and, especially, it is weakened against impact shocks. The mechanical strength of the radioactive wastes scarcely changes by the low temperature gas. Impactshocks are applied to the surface of the containing bag by an impact device. In addition, since the crushing chamber itself is vibrated, the containing bag is crushed also by its own weight to provide a satisfactory crushing efficiency. In this case, since the crushing chamber is sealed, there is no worry that the finely crushed pieces are leaked to the outside. It is possible to apply fully automated control requiring no particular skills in the operation, and there is no danger of radiation exposure. Radioactive wastes can be unpacked continuously in a short period of time. (T.M.)

  8. Handling and treatment of radioactive aqueous wastes

    International Nuclear Information System (INIS)

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

  9. ECOLOGICAL AND TECHNICAL REQUIREMENTS OF RADIOACTIVE WASTE UTILISATION

    OpenAIRE

    Gabriel Borowski; Michał Wośko

    2013-01-01

    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 rad...

  10. 2011 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site, Nye County, Nevada: Review of the Performance Assessments and Composite Analyses

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2012-03-20

    The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (National Security Technologies, LLC, 2007a) requires an annual review to assess the adequacy of the Performance Assessments (PAs) and Composite Analyses (CAs), with the results submitted annually to U.S. Department of Energy (DOE) Office of Environmental Management. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (DOE, 1999a; 2000). The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 RWMS PAs and CAs for fiscal year (FY) 2011. This annual summary report presents data and conclusions from the FY 2011 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R and D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada National Security Site (NNSS) (formerly the Nevada Test Site) relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R and D activities were reviewed to determine the adequacy of the CAs. Important developments in FY 2011 include the following: (1) Operation of a new shallow land disposal unit and a new Resource Conservation and Recovery Act (RCRA)-compliant lined disposal unit at the Area 5 RWMS; (2) Development of new closure inventory estimates based on disposals through FY 2011; (3) Evaluation of new or revised waste streams by special analysis; (4) Development of

  11. Chapter 5-Radioactive Waste Management

    International Nuclear Information System (INIS)

    The ore pitchblende was discovered in the 1750's near Joachimstal in what is now the Czech Republic. Used as a colorant in glazes, uranium was identified in 1789 as the active ingredient by chemist Martin Klaproth. In 1896, French physicist Henri Becquerel studied uranium minerals as part of his investigations into the phenomenon of fluorescence. He discovered a strange energy emanating from the material which he dubbed 'rayons uranique.' Unable to explain the origins of this energy, he set the problem aside. About two years later, a young Polish graduate student was looking for a project for her dissertation. Marie Sklodowska Curie, working with her husband Pierre, picked up on Becquerel's work and, in the course of seeking out more information on uranium, discovered two new elements (polonium and radium) which exhibited the same phenomenon, but were even more powerful. The Curies recognized the energy, which they now called 'radioactivity,' as something very new, requiring a new interpretation, new science. This discovery led to what some view as the 'golden age of nuclear science' (1895-1945) when countries throughout Europe devoted large resources to understand the properties and potential of this material. By World War II, the potential to harness this energy for a destructive device had been recognized and by 1939, Otto Hahn and Fritz Strassman showed that fission not only released a lot of energy but that it also released additional neutrons which could cause fission in other uranium nuclei leading to a self-sustaining chain reaction and an enormous release of energy. This suggestion was soon confirmed experimentally by other scientists and the race to develop an atomic bomb was on. The rest of the development history which lead to the bombing of Hiroshima and Nagasaki in 1945 is well chronicled. After World War II, development of more powerful weapons systems by the United States and the Soviet Union continued to advance nuclear science. It was this defense

  12. CHAPTER 5-RADIOACTIVE WASTE MANAGEMENT

    Energy Technology Data Exchange (ETDEWEB)

    Marra, J.

    2010-05-05

    The ore pitchblende was discovered in the 1750's near Joachimstal in what is now the Czech Republic. Used as a colorant in glazes, uranium was identified in 1789 as the active ingredient by chemist Martin Klaproth. In 1896, French physicist Henri Becquerel studied uranium minerals as part of his investigations into the phenomenon of fluorescence. He discovered a strange energy emanating from the material which he dubbed 'rayons uranique.' Unable to explain the origins of this energy, he set the problem aside. About two years later, a young Polish graduate student was looking for a project for her dissertation. Marie Sklodowska Curie, working with her husband Pierre, picked up on Becquerel's work and, in the course of seeking out more information on uranium, discovered two new elements (polonium and radium) which exhibited the same phenomenon, but were even more powerful. The Curies recognized the energy, which they now called 'radioactivity,' as something very new, requiring a new interpretation, new science. This discovery led to what some view as the 'golden age of nuclear science' (1895-1945) when countries throughout Europe devoted large resources to understand the properties and potential of this material. By World War II, the potential to harness this energy for a destructive device had been recognized and by 1939, Otto Hahn and Fritz Strassman showed that fission not only released a lot of energy but that it also released additional neutrons which could cause fission in other uranium nuclei leading to a self-sustaining chain reaction and an enormous release of energy. This suggestion was soon confirmed experimentally by other scientists and the race to develop an atomic bomb was on. The rest of the development history which lead to the bombing of Hiroshima and Nagasaki in 1945 is well chronicled. After World War II, development of more powerful weapons systems by the United States and the Soviet Union continued to

  13. Minimization and segregation of radioactive wastes

    International Nuclear Information System (INIS)

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

  14. High-level radioactive waste management

    International Nuclear Information System (INIS)

    The policy problem of waste management facing the U.S. Government is outlined in this article. The discussion is limited to the management of high-level radioactive waste or its equivalent. The lack of coordinated institutional mechanism for implementing the technology of waste disposal is cited as the heaviest indictment of the Government waste management program. The waste management policy problem is described as a series of issue clusters. Three driving forces, (1) demand for energy, (2) state of world tensions over possibility and consequences of war, and (3) pace of advance of scientific knowledge, are proported to be driving for solutions of these series of issue clusters. Six steps necessary to the Governmental development of a waste management policy are outlined and discussed. These steps are (1) access national efforts in the past, (2) estimate future national energy demand and evaluate that against existing plants to supply energy, (3) identify national goals relevant to the waste management policy problem, (4) evaluate proposed solutions, (5) decide on the course to follow, and (6) implement that decision

  15. How do social systems treat and dispose nuclear waste? : -A comparison of general and radioactive wastes -

    OpenAIRE

    YUASA, Yoichi||ユアサ, ヨウイチ

    2013-01-01

    All countries that have nuclear reactors are confronted with the problem of treating or disposing radioactive waste. What factors decide which countries are successful at radioactive waste management? We propose an assumption that the method a country selects for treating or disposing radioactive waste depends on the way social systems function. From the perspective of social systems, we will compare the disposal of general waste to the disposal of radioactive waste. The social system for gen...

  16. Overview of management of low level radioactive wastes in Canada

    International Nuclear Information System (INIS)

    In Canada, the programme for the management of low level radioactive wastes is one of continued reliance on interim storage methods while putting in place the policies, regulations and technologies for the transition to permanent disposal which should begin early in the 1990s. The Canadian regulatory authority has issued a policy statement on the objectives, requirements and guidelines for the disposal of radioactive wastes and has proposed a basis for the identification of a de minimis category. The regulations impose a maximum annual risk of 10-6 and are directed at minimizing the burden placed on future generations as well as protecting human health and the environment. Several conceptual and site specific repositories have been designed and evaluated by the major producers in Canada. Proposals for the disposal of uranium contaminated wastes, which comprise the majority of the existing inventory, encountered strong public opposition to suggested sites. This led to the formation of a federal task force which has recommended a community driven siting process. Little opposition has been evident, however, to the operation of most of the existing storage sites for the wastes continuing to arise from the nuclear industry. Processing and storage techniques are being further developed to improve their efficiency. Also, funding for the construction of the first prototype disposal vault has been committed. (author). 22 refs, 1 tab

  17. Radioactive Waste Disposal into the Sea

    International Nuclear Information System (INIS)

    Preventing pollution of the seas from the discharge of radioactive wastes has been recognized as an international problem of considerable magnitude. In April 1958 the United Nations Conference on the Law of the Sea adopted a Convention on the High Seas, Article 25 of which provides that every State shall take measures to prevent pollution of the seas from the dumping of radioactive wastes, taking into account any standards and regulations which may be formulated by the competent international organizations. The Conference also adopted a resolution recommending that the IAEA pursue studies and take action to assist States in controlling the discharge of radioactive materials into the sea. Later the same year, a Panel of experts was invited by me to meet in Vienna to study the technical and scientific problems connected with radioactive waste disposal into the sea, and Mr. H. Brynielsson of Sweden was designated Chairman of the Panel. Representatives of the United Nations, the Food and Agriculture Organization of the United Nations, the World Health Organization and the United Nations Educational, Scientific and Cultural Organization participated in the work of the Panel. After a second series of meetings in 1959, the Panel completed its study, setting forth the result of its work in a report dated 6 April 1960, which has been submitted to the Agency's Scientific Advisory Committee and to Member States for their information. The Panel's report is now published in the present volume of the Agency's Safety Series in the form in which it was submitted by the Chairman of the Panel. I should like to add that the report represents the views of the experts participating in their individual capacity in the work of the Panel. It is offered as an information document and it should not be regarded as an official statement by the Agency of its views or policies in relation to the subject discussed.

  18. Mobile Processing Systems for Radioactive Waste Management

    International Nuclear Information System (INIS)

    One of the IAEA's statutory objectives is to 'seek to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world.' One way this objective is achieved is through the publication of a range of technical series. Two of these are the IAEA Nuclear Energy Series and the IAEA Safety Standards Series. According to Article III.A.6 of the IAEA Statute, the safety standards establish 'standards of safety for protection of health and minimization of danger to life and property'. The safety standards include the Safety Fundamentals, Safety Requirements and Safety Guides. These standards are written primarily in a regulatory style, and are binding on the IAEA for its own programmes. The principal users are the regulatory bodies in Member States and other national authorities. The IAEA Nuclear Energy Series comprises reports designed to encourage and to assist R and D on, and application of, nuclear energy for peaceful uses. This includes practical examples to be used by owners and operators of utilities in Member States, implementing organizations, academia and government officials, among others. This information is presented in guides, reports on technology status and advances, and best practices for peaceful uses of nuclear energy based on inputs from international experts. The IAEA Nuclear Energy Series complements the IAEA Safety Standards Series. Radioactive waste is generated from the operation of nuclear power plants, fuel cycle facilities and other nuclear applications. It consists of distinct 'waste types' with a variety of characteristics. Mobile systems have recently been increasingly deployed for predisposal management of radioactive waste streams (e.g. pretreatment, treatment and conditioning). In addition, considerations of performance, cost and flexibility may render mobile systems attractive for future nuclear facilities. This publication provides guidance for evaluating and implementing processing technologies

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

    International Nuclear Information System (INIS)

    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

  20. Radioactive waste disposal fees—Methodology for calculation

    International Nuclear Information System (INIS)

    This paper summarizes the methodological approach used for calculation of fee for low- and intermediate-level radioactive waste disposal and for spent fuel disposal. The methodology itself is based on simulation of cash flows related to the operation of system for waste disposal. The paper includes demonstration of methodology application on the conditions of the Czech Republic. - Highlights: • Policy of radioactive waste management in the Czech Republic. • Methodology for calculation of fees for radioactive waste disposal. • Comparison of fee for radioactive waste disposal for selected countries. • The most important factors influencing fee-case example of the Czech Republic

  1. 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.

  2. Modelling gas generation in radioactive waste repositories

    International Nuclear Information System (INIS)

    In a repository containing low- and intermediate-level waste, gas generation will occur principally by the coupled processes of metal corrosion and microbial degradation of cellulosic waste. This Paper describes a mathematical model design to address gas generation by these mechanisms. The metal corrosion model incorporates a three-stage process encompassing both aerobic and anaerobic corrosion regimes; the microbial degradation model simulates the activities of eight different microbial populations, which are maintained as functions both of pH and of the concentrations of particular chemical species. Gas concentrations have been measured over a period of three years in large-scale drum experiments designed to simulate repository conditions. Model predictions are confirmed against the experimental measurements, and a prediction is then made of gas concentrations and generation rates over an assessment period of one million years in a radioactive waste repository. (author)

  3. Modelling gas generation in radioactive waste repositories

    International Nuclear Information System (INIS)

    In a repository containing low- and intermediate-level waste, gas generation will occur principally by the coupled processes of metal corrosion and microbial degradation of cellulosic waste. This paper describes a mathematical model designed to address gas generation by these mechanisms. The metal corrosion model incorporates a three-stage process encompassing both aerobic and anaerobic corrosion regimes; the microbial degradation model simulates the activities of eight different microbial populations, which are maintained as functions both of pH and of the concentrations of particular chemical species. Gas concentrations have been measured over a period of three years in large-scale drum experiments designed to simulate repository conditions. Model predictions are confirmed against the experimental measurements, and a prediction is then made of gas concentrations and generation rates over an assessment period of one million years in a radioactive waste repository. (Author)

  4. Predicting transportation routes for radioactive wastes

    International Nuclear Information System (INIS)

    Oak Ridge National Laboratory (ORNL) has been involved in transportation logistics of radioactive wastes as part of the overall waste transportation program. A Spent Fuel Logistics Model (SFLM), was developed to predict overall material balances representing the flow of spent fuel assemblies from reactors to away-from-reactor storage facilities and/or to federal repositories. The transportation requirements to make these shipments are also itemized. The next logical step in the overall transportation project was the development of a set of computer codes which would predict likely transportation routes for waste shipments. Two separate routing models are now operational at ORNL. Routes for truck transport can be estimated with the HIGHWAY program, and rail and barge routes can be predicted with the INTERLINE model. This paper discusses examples of the route estimates and applications of the routing models

  5. Management of radioactive waste packaging drum

    Energy Technology Data Exchange (ETDEWEB)

    Kang, Il-Sik; Shon, Kang J. S.; Lee, Y. H.; Song, I. T.; Lee, B. C.; Kim, K. J. [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-02-01

    Radioactive waste drums of dismantled equipment and contaminated soil waste generated from KAERI research reactor, Seoul in 1988 were transferred to KAERI in Taejeon and are stored at low and medium level storage building until now. As a result of relatively long term storage, a corrosion on the surface of the drums was progressed and a remedial action was conducted to take a measure for the enhancement of safety. Thus, we examined the corrosion status on the surface of waste drums and studied mostly applicable methods. Resultingly, the seriously corroded drums were repackaged and the slightly corroded drums were painted after removing a corroded part on the surface. 12 refs., 14 figs., 12 tabs. (Author)

  6. Future radioactive liquid waste streams study

    Energy Technology Data Exchange (ETDEWEB)

    Rey, A.S.

    1993-11-01

    This study provides design planning information for the Radioactive Liquid Waste Treatment Facility (RLWTF). Predictions of estimated quantities of Radioactive Liquid Waste (RLW) and radioactivity levels of RLW to be generated are provided. This information will help assure that the new treatment facility is designed with the capacity to treat generated RLW during the years of operation. The proposed startup date for the RLWTF is estimated to be between 2002 and 2005, and the life span of the facility is estimated to be 40 years. The policies and requirements driving the replacement of the current RLW treatment facility are reviewed. Historical and current status of RLW generation at Los Alamos National Laboratory are provided. Laboratory Managers were interviewed to obtain their insights into future RLW activities at Los Alamos that might affect the amount of RLW generated at the Lab. Interviews, trends, and investigation data are analyzed and used to create scenarios. These scenarios form the basis for the predictions of future RLW generation and the level of RLW treatment capacity which will be needed at LANL.

  7. Demonstration Project of Radioactive Solid Waste Retrieval and Conditioning

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>The construction goal of the project is to construct a set of special equipments for radioactive solid waste retrieval, sorting, pre-compacting and radioactive measurement, to provide a set of engineering

  8. National policy for control of radioactive sources and radioactive waste from non-power applications in Lithuania

    International Nuclear Information System (INIS)

    According to the Law on Radiation Protection of the Republic of Lithuania (passed in 1999), the Radiation Protection Centre of the Ministry of Health is the regulatory authority responsible for the radiation protection of public and of workers using sources of ionizing radiation in Lithuania. One of its responsibilities is the control of radioactive sources from the beginning of their 'life cycle', when they are imported in, used, transported and placed as spent into the radioactive waste storage facilities. For the effective control of sources there is national authorization system (notification- registration-licensing) based on the international requirements and recommendations introduced, which also includes keeping and maintaining the Register of Sources, controlling and investigating events while illegally carrying on or in possession of radioactive material, decision making and performing the state radiation protection supervision and control of users of radioactive sources, controlling, within the limits of competence, the radioactive waste management activities in nuclear and non-nuclear power applications. According to the requirements set out in the Law on Radiation Protection and the Government Resolution 'On Establishment of the State Register of the Sources of Ionizing Radiation and Exposure of Workers' (1999) and supplementary legal acts, all licence-holders conducting their activities with sources of ionizing radiation have to present all necessary data to the State Register after annual inventory of sources, after installation of new sources, after decommissioning of sources, after disposal of spent sources, after finishing the activities with the generators of ionizing radiation. The information to the Radiation Protection Centre has to be presented every week from the Customs Department of the Ministry of Finance about all sources of ionizing radiation imported to or exported from Lithuania and the information about the companies performed these

  9. Annual report on radioactive discharges and monitoring of the environment 1990. V. 1

    International Nuclear Information System (INIS)

    This Annual Report supplements the Health and Safety Annual Report of British Nuclear Fuels plc by providing more detailed information on radioactive discharges, monitoring of the environment and critical group doses. This report has been sub-divided into two complementary parts. Volume I includes annual data for each of the Company sites on radioactive discharges into the environment and the associated environmental monitoring programmes. The sites involved are: Sellafield where the main activities are irradiated nuclear fuel reprocessing and the Calder Hall nuclear station; the Drigg radioactive waste storage and disposal site; the Chapelcross nuclear power station; Springfields Works which manufactures nuclear fuels; Capenhurst Works where uranium isotopic enrichment plants are operated. Volume II reproduces the Certificates of Authorisation under which the Company operates and the statutory environmental monitoring programmes which relate to them. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

    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.

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

    International Nuclear Information System (INIS)

    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

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

    International Nuclear Information System (INIS)

    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)

  13. Radioactive waste disposal - ethical and environmental considerations - A Canadian perspective

    International Nuclear Information System (INIS)

    This work deals with ethical and environmental considerations of radioactive waste disposal in Canada. It begins with the canadian attitudes toward nature and environment. Then are given the canadian institutions which reflect an environmental ethic, the development of a canadian radioactive waste management policy, the establishment of formal assessment and review process for a nuclear fuel waste disposal facility, some studies of the ethical and risk dimensions of nuclear waste decisions, the canadian societal response to issues of radioactive wastes, the analysis of risks associated with fuel waste disposal, the influence of other energy related environmental assessments and some common ground and possible accommodation between the different views. (O.L.). 50 refs

  14. Radioactive-waste incineration at Purdue University

    International Nuclear Information System (INIS)

    A study conducted at Purdue University to evaluate the feasibility of using a small (45 kg/h), inexpensive (less than $10K) incinerator for incinerating low-level radioactive waste is described. An oil-fired, dual-chamber pathological waste incinerator was installed on a 12.7-cm-thick concrete floor in a metal quonset building. A standard EPA Method 5 sampling train was used to obtain stack samples. Also, stack gas velocity was measured with a type 5 pitot tube; stack temperature was measured with a thermocouple and pyrometer. The incinerator was tested for emissions from incineration of laboratory animal carcasses, liquid scintillation fluid, and trash. Emissions measured were particulates, SO/sub x/, NO/sub x/, Cl, CO, CO2, H2O, and unburned hydrocarbons in the particulate fraction. Three analyses were then averaged to arrive at the final determinations. Results of the study demonstrated the feasibility and cost-effectiveness of incinerating radioactive animal carcasses and liquid scintillation fluids, since emissions from those waste types were within EPA and State of Indiana limits. However, emissions from burning of trash exceeded State of Indiana limits. Therefore, incineration of trash alone, particularly if it contains glass or significant amounts of plastic, is not a recommended use of the tested equipment

  15. Geological disposal of heat generating radioactive waste

    International Nuclear Information System (INIS)

    A number of options for the disposal of vitrified heat-generating radioactive waste are being studied to ensure that safe methods are available when the time comes for disposal operations to commence. This study has considered the feasibility of three designs for containers which would isolate the waste from the environment for a minimum period of 500 to 1000 years. The study was sub-divided into the following major sections: manufacturing feasibility; stress analysis; integrity in accidents; cost benefit review. The candidate container designs were taken from the results of a previous study by Ove Arup and Partners (1985) and were developed as the study progressed. Their major features can be summarised as follows: (A) a thin-walled corrosion-resistant metal shell filled with lead or cement grout. (B) an unfilled thick-walled carbon steel shell. (C) an unfilled carbon steel shell planted externally with corrosion-resistant metal. Reference repository conditions in clay, granite and salt, reference disposal operations and metals corrosion data have been taken from various European Community radioactive waste management research and engineering projects. The study concludes that design Types A and B are feasible in manufacturing terms but design Type C is not. It is recommended that model containers should be produced to demonstrate the proposed methods of manufacture and that they should be tested to validate the analytical techniques used. (author)

  16. Intergenerational ethics of high level radioactive waste

    International Nuclear Information System (INIS)

    The validity of intergenerational ethics on the geological disposal of high level radioactive waste originating from nuclear power plants was studied. The result of the study on geological disposal technology showed that the current method of disposal can be judged to be scientifically reliable for several hundred years and the radioactivity level will be less than one tenth of the tolerable amount after 1,000 years or more. This implies that the consideration of intergenerational ethics of geological disposal is meaningless. Ethics developed in western society states that the consent of people in the future is necessary if the disposal has influence on them. Moreover, the ethics depends on generally accepted ideas in western society and preconceptions based on racism and sexism. The irrationality becomes clearer by comparing the dangers of the exhaustion of natural resources and pollution from harmful substances in a recycling society. (author)

  17. Intergenerational ethics of high level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Takeda, Kunihiko [Nagoya Univ., Graduate School of Engineering, Nagoya, Aichi (Japan); Nasu, Akiko; Maruyama, Yoshihiro [Shibaura Inst. of Tech., Tokyo (Japan)

    2003-03-01

    The validity of intergenerational ethics on the geological disposal of high level radioactive waste originating from nuclear power plants was studied. The result of the study on geological disposal technology showed that the current method of disposal can be judged to be scientifically reliable for several hundred years and the radioactivity level will be less than one tenth of the tolerable amount after 1,000 years or more. This implies that the consideration of intergenerational ethics of geological disposal is meaningless. Ethics developed in western society states that the consent of people in the future is necessary if the disposal has influence on them. Moreover, the ethics depends on generally accepted ideas in western society and preconceptions based on racism and sexism. The irrationality becomes clearer by comparing the dangers of the exhaustion of natural resources and pollution from harmful substances in a recycling society. (author)

  18. Management of radioactive wastes from nuclear power plants

    International Nuclear Information System (INIS)

    This Code of Practice defines the minimum requirements for the design and operation of structures, systems and components important for the management of radioactive wastes from thermal neutron nuclear power plants. The topics covered include design and operation of gaseous, liquid and solid waste systems, waste transport, storage and disposal, decommissioning wastes and wastes from unplanned events

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

    OpenAIRE

    T. Marpaung

    2012-01-01

    In the past few years, the utilization of sealed source for medical, industrial and research purposes has shown an accelerating increase. This situation will lead to increases in the amount of sealed radioactive. During its use, a sealed radioactive waste will eventually become either a spent sealed source or disused sealed radioactive source (DSRS), due to certain factors. The reduction of the amount of radioactive waste can be executed through the application of reuse and recycle of sealed ...

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

    International Nuclear Information System (INIS)

    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)

  1. National inventory of radioactive wastes; Inventaire national des dechets radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    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.). 16 refs.

  2. Licensing framework of radioactive waste management in Indonesia

    International Nuclear Information System (INIS)

    The utilization of nuclear energy has been developed in Indonesia in research, agriculture, health, industry and other fields. Besides the positive aspects, nuclear energy has the potential of radiation hazard. A potential radiation hazard derives from radioactive waste. To control the radioactive waste, BAPETEN has, in the year 2002, established Government Regulation No. 27. This paper addresses present regulation relating to the management of radioactive waste, including the licensing system. (author)

  3. Radioactive waste management practices in India: achievements and challenges

    International Nuclear Information System (INIS)

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

  4. International co-operation for safe radioactive waste management

    International Nuclear Information System (INIS)

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

  5. Policy framework for radioactive waste disposal in Canada

    International Nuclear Information System (INIS)

    The elements of a comprehensive radioactive waste policy framework consist of a set of principles governing the institutional and financial arrangements for disposal of radioactive waste by waste producers and owners. Principle 1 - The federal government will ensure that radioactive waste disposal is carried out in a safe, environmentally sound, comprehensive, cost-effective and integrated manner where: Principle 2 - The federal government had the responsibility to develop policy, to regulate, and to oversee producers and owners to ensure they comply with legal requirements and meet their funding and operational responsibilities in accordance with approved waste disposal plans; and, Principle 3 - The waste producers and owners are responsible, in accordance with the principle of 'polluter pays', for the funding, organisation, management and operation of disposal and other facilities required for their wastes, recognizing that arrangements may be different for nuclear fuel waste, low-level radioactive waste, and uranium mine and mill tailings. (author)

  6. Annual report 1984. Radioactive isotope department

    International Nuclear Information System (INIS)

    New technologies for production and application of radionuclides and synthesis of radioactive compounds are reported. Special importance is attributed to the characterization of radioactive compounds and the quality check of /sup 99m/Tc- and 14C-labelled complexes within animal tests. An extensive list of publications and lectures illustrates the international cooperation of research in the field of radiochemistry

  7. Partnering with stakeholders in radioactive waste management

    International Nuclear Information System (INIS)

    Site selection for radioactive waste management (RWM) facilities draws considerable attention from implementers, government bodies, local communities and the public at large. Facility siting processes have generally tended to be marred by conflicts, disagreements and delays. In response, efforts have been made to shift from a more traditional 'decide, announce and defend' model to one of 'engage, interact and co-operate'. The essence of the new approach is co-operation or partnership between the implementer and the affected communities, involving dialogue between experts and citizens, mutual learning and public participation in the decision-making process. National ministries and authorities have also been called to and do play a more visible role. The intensity and degree of partnering can vary from country to country and in different phases of project development. Important changes have taken place in citizen participation in radioactive waste management over the past decade. These changes can be summarised as follows: - shift from information and consultation towards partnership, i.e. from token involvement to citizen influence and power; - shift from a passive to an active role of local communities: from resigned acceptance to collaboration, volunteering and veto; - development of a great variety of administrative formats for collaboration; - recognition of the need for, and legitimacy of, community empowerment measures and socio-economic benefits; - emergence of new ideals and bases for collaboration including mutual learning, adding values to the host community/region and sustainable development. Involving local actors in the design of the facility and community benefits are likely to result in solutions that will add value to the host region. In all cases, social capital is augmented as local stakeholders develop new skills and increase their knowledge about the interests and ideals of their community. Implementers and other institutional players also

  8. Current radioactive waste utilization at PA 'MAYAK'

    International Nuclear Information System (INIS)

    The Production Association 'Mayak' is one of the largest production union of Nuclear Fuel Cycle (NFC) in Russia. In 1988 the last military reactor, which worked for making military plutonium was stopped. From this time civic history of 'Mayak' was began. Today 'Mayak' is the complex production union of NFC, which utilizes the Radiated Nuclear Fuel (RNF). The combine is dynamically develops, new technologies are domesticate and intrude, large works for liquidation of accidents and mistakes of lapsed years are in progress. The short review of radioactive waste utilization methods is present in this account. (author)

  9. Volume reduction techniques for solid radioactive wastes

    International Nuclear Information System (INIS)

    This report gives an account of some of the techniques in current use in the UK for the treatment of solid radioactive wastes to reduce their volume prior to storage or disposal. Reference is also made to current research and development projects. It is based on a report presented at a recent International Atomic Energy Agency Technical Committee when this subject was the main theme. An IAEA Technical Series report covering techniques in use in all parts of the world should be published within the next two years. (author)

  10. Radioactive waste disposal into the ground

    International Nuclear Information System (INIS)

    Disposal into ground has sometimes proved to be an expedient and simple method. Where ground disposal has become an established practice, the sites have so far been limited to those remote from population centres; but in other respects, such as in climate and soil conditions, their characteristics vary widely. Experience gained at these sites has illustrated the variety of problems in radioactive waste migration and the resulting pollution and environmental radiation levels that may reasonably be anticipated at other sites, whether remote from population centres or otherwise.

  11. Management program on radioactive wastes in research

    International Nuclear Information System (INIS)

    This document has the objective to orient and advise the researchers to practice a safety management of radioactive wastes in each research laboratory, based upon the technical norms of the Brazilian Nuclear Energy Commission and the recommendations of the International Atomic Energy Agency. Additionally, basic information on the main radioisotopes used in research are presented, including the processes used for production of radioisotopes, methods for radiation detection, range of alpha and beta particles, background radiation, as well as principles on radioprotection and biological effects of radiation

  12. Treatment technology for organic radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, S. J.; Lee, Y. H.; Shon, J. S. [Korea Atomic Energy Research Institute, Taejon (Korea)

    1999-12-01

    In this report, various alternative technologies to the incineration for the treatment of radioactive organic wastes were described and reviewed, fallen into two groups of low temperature technologies and high temperature technologies. These technologies have the advantages of low volume gaseous emission, few or no dioxin generation, and operation at low enough temperature that radionuclides are not volatilized. Delphi chemical oxidation, mediated electrochemical oxidation, and photolytic ultraviolet oxidation appear to be the most promising low temperature oxidation process and steam reforming and supercritical water oxidation in the high temperature technologies. 52 refs., 39 figs., 2 tabs. (Author)

  13. Radioactive waste disposal via electric propulsion

    Science.gov (United States)

    Burns, R. E.

    1975-01-01

    It is shown that space transportation is a feasible method of removal of radioactive wastes from the biosphere. The high decay heat of the isotopes powers a thermionic generator which provides electrical power for ion thrust engines. The massive shields (used to protect ground and flight personnel) are removed in orbit for subsequent reuse; the metallic fuel provides a shield for the avionics that guides the orbital stage to solar system escape. Performance calculations indicate that 4000 kg. of actinides may be removed per Shuttle flight. Subsidiary problems - such as cooling during ascent - are discussed.

  14. Report on current research into organic materials in radioactive waste

    International Nuclear Information System (INIS)

    A preliminary review of relevant recent papers on organic materials in radioactive waste is presented. In particular, the effects of chelating or complexing agents, the influence of bacteria and the role of colloids are assessed. The requirement for further radioactive waste inventory detail is indicated. Potential problem areas associated with the presence of organic materials in radioactive waste are identified and appropriate experimental work to assess their significance is proposed. Recommendations for specific further work are made. A list and diagrams of some of the more important polymer structures likely to be present in radioactive waste and their possible degradation products are appended. (author)

  15. Public perceptions of aspects of radioactive waste management

    International Nuclear Information System (INIS)

    The paper concerns a study of peoples' attitude towards the siting of radioactive waste repositories, carried out by the University of Surrey, United Kingdom. The work has been commissioned by the Department of the Environment as part of its radioactive waste management research programme. The people taking part were asked to mark on a map of Great Britain places they felt radioactive waste repositories would be least objectionable. The degree to which people worried about the technology and the management of radioactive waste disposal was monitored. Questions were asked about storage, disposal and transportation aspects, and about present and future worries. (UK)

  16. Annual survey of radioactive discharges in Great Britain 1978

    International Nuclear Information System (INIS)

    Details are given of main discharges to the environment of radioactive waste in 1978 together with those in 1977 and 1976 for comparison with comment on the environmental effect of the discharges in 1977. The statutory control over the discharges of radioactive wastes in Great Britain is outlined in the Introduction. Details of the discharges are set out in tabular form, grouped under: UKAEA establishments; the Radiochemical Centre Limited; British Nuclear Fuels Limited; CEGB and SSEB nuclear power stations; Ministry of Defence. Part 7 deals with radioactivity in drinking waters and rivers. (U.K.)

  17. Inverse osmotic process for radioactive laundry waste

    International Nuclear Information System (INIS)

    Purpose: To effectively recover the processing amount reduced in a continuous treatment. Method: Laundry waste containing radioactive substances discharged from a nuclear power plant is processed in an inverse osmotic process while adding starch digesting enzymes such as amylase and takadiastase, as well as soft spherical bodies such as sponge balls of a particle diameter capable of flowing in the flow of the liquid wastes along the inverse osmotic membrane pipe and having such a softness and roundness as not to damage the inverse osmotic membrane. This process can remove the floating materials such as thread dusts or hairs deposited on the membrane surface by the action of the soft elastic balls and remove paste or the like through decomposition by the digesting enzymes. Consequently, effective recovery can be attained for the reduced processing amount. (Furukawa, Y.)

  18. Process of disposing radioactive washed waste

    International Nuclear Information System (INIS)

    Object: To use a surface active agent, which produces no bubble when vaporized and concentrated, as a cleaning material, to effect processes of vaporization and concentration without removing the surface active agent from the cleaned waste. Structure: A cleaning agent containing 10 - 30% of a non-ion surface active agent comprising a combination of polyethylene-alkyl-ether and polyethylene-alkyl-phenylether in a ratio of 1 to 1, 0 - 30% of chelate, 1% of re-adhesion prohibitor (CMC), and 1 - 5% of emulsion stabilizer is used to wash a radioactive contamination, an anti-foaming agent in a small amount is added to the washed waste only when in start to directly vaporize and concentrate the same, after which it is heated and dried and thereafter, it is decomposed at a temperature less than 4000C for treatment of reduction in volume. (Kawakami, Y.)

  19. Radioactive waste burial grounds: Environmental information document

    International Nuclear Information System (INIS)

    This document provides environmental information on postulated closure options for the Radioactive Waste Burial Grounds at the Savannah River Plant and was developed as background technical documentation for the Department of Energy's proposed Environmental Impact Statement (EIS) on waste management activities for groundwater protection at the plant. The results of groundwater and atmospheric pathway analyses, accident analysis, and other environmental assessments discussed in this document are based upon a conservative analysis of all foreseeable scenarios as defined by the National Environmental Policy Act (40 CFR 1500-1508). The scenarios do not necessarily represent actual environmental conditions. This document is not meant to be used as a regulatory closure plan or other regulatory document to comply with required federal or state environmental regulations

  20. Radioactive Waste Management Complex performance assessment: Draft

    International Nuclear Information System (INIS)

    A radiological performance assessment of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory was conducted to demonstrate compliance with appropriate radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the general public. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the general public via air, ground water, and food chain pathways. Projections of doses were made for both offsite receptors and individuals intruding onto the site after closure. In addition, uncertainty analyses were performed. Results of calculations made using nominal data indicate that the radiological doses will be below appropriate radiological criteria throughout operations and after closure of the facility. Recommendations were made for future performance assessment calculations

  1. Radioactive Waste Management Complex performance assessment: Draft

    Energy Technology Data Exchange (ETDEWEB)

    Case, M.J.; Maheras, S.J.; McKenzie-Carter, M.A.; Sussman, M.E.; Voilleque, P.

    1990-06-01

    A radiological performance assessment of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory was conducted to demonstrate compliance with appropriate radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the general public. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the general public via air, ground water, and food chain pathways. Projections of doses were made for both offsite receptors and individuals intruding onto the site after closure. In addition, uncertainty analyses were performed. Results of calculations made using nominal data indicate that the radiological doses will be below appropriate radiological criteria throughout operations and after closure of the facility. Recommendations were made for future performance assessment calculations.

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

    CERN Document Server

    2004-01-01

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

  3. Radioactive waste management complex low-level waste radiological composite analysis

    Energy Technology Data Exchange (ETDEWEB)

    McCarthy, J.M.; Becker, B.H.; Magnuson, S.O.; Keck, K.N.; Honeycutt, T.K.

    1998-05-01

    The composite analysis estimates the projected cumulative impacts to future members of the public from the disposal of low-level radioactive waste (LLW) at the Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Waste Management Complex (RWMC) and all other sources of radioactive contamination at the INEEL that could interact with the LLW disposal facility to affect the radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA) at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used in the composite analysis consists of all historical SDA subsurface disposals of radionuclides as well as the authorized LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in the composite analysis include all the all-pathways and groundwater protection scenarios. The projected dose of 58 mrem/yr exceeds the composite analysis guidance dose constraint of 30 mrem/yr; therefore, an options analysis was conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2) maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional control beyond the 100 years assumed in the composite analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL appears to be feasible and cost effective.

  4. Issue briefs on low-level radioactive wastes

    International Nuclear Information System (INIS)

    This report contains 4 Issue Briefs on low-level radioactive wastes. They are entitled: Handling, Packaging, and Transportation, Economics of LLW Management, Public Participation and Siting, and Low Level Waste Management

  5. Attention: no radioactive waste accepted on 7 September

    CERN Multimedia

    2012-01-01

    Anouncement by the RW section of the Radiation Protection Group: The Treatment Centre for Radioactive Waste will not be accepting waste on Friday, 7 September 2012. Thank you for adjusting your activities accordingly.

  6. The Dutch policy with regard to radioactive waste. Chapter 1

    International Nuclear Information System (INIS)

    The objectives of the Dutch government with regard to radioactive waste, the character, amount anbd origin of this waste, and the policy, as pursued in the past decennia, are discussed, resulting in an exposition of the actual policy. (author)

  7. New paradigms in radioactive waste management

    International Nuclear Information System (INIS)

    The social dimension of nuclear power has so far been seen as mostly a communication problem and has been addressed, as such, periodically over the years in workshops, conferences and studies. It is only in the last years in relation to the siting of waste repositories, that this issue is more broadly understood as stakeholder involvement, and finally as an element of participatory democracy. Based on work of various standing technical committees of the OECD Nuclear Energy Agency (NEA), and in particular the Radioactive Waste Management Committee's (RWMC) Forum on Stakeholder Confidence (FSC), the paper reviews the recent development from public risk communication to stakeholder involvement in the area of waste management. Key findings of the FSC national workshops in Finland, Canada, Belgium and Germany are presented and main factors influencing the debate and public acceptance of waste facilities are identified. The need for clarifying the role of all actors in this dialog and the particular challenges for regulatory institutions in a stakeholder dialogue are addressed. (author)

  8. Regulating Radioactive Waste Management at the National Level

    International Nuclear Information System (INIS)

    National and local governments design and enforce rules concerning the safe transport, treatment, storage, disposal, and classification of radioactive waste. These rules are intended to protect people and the environment, and to provide a legal and regulatory framework within which radioactive waste management can be planned and safely carried out. Radioactive waste regulations also cover “who” is responsible for “what” at each stage of the waste management process, and define the optimal decision making process over the different stages in the lifetime of the waste facility, including development, operation, and closure or decommissioning

  9. Application bar-code system for solid radioactive waste management

    International Nuclear Information System (INIS)

    Solid radioactive wastes are generated from the post-irradiated fuel examination facility, the irradiated material examination facility, the research reactor, and the laboratories at KAERI. A bar-code system for a solid radioactive waste management of a research organization became necessary while developing the RAWMIS(Radioactive Waste Management Integration System) which it can generate personal history management for efficient management of a waste, documents, all kinds of statistics. This paper introduces an input and output application program design to do to database with data in the results and a stream process of a treatment that analyzed the waste occurrence present situation and data by bar-code system

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

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

  11. Storing solid radioactive wastes at the Savannah River Plant

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-06-01

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

  12. Treatment of radioactive waste - Routine or challenge? Proceedings

    International Nuclear Information System (INIS)

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

  13. Area 5 Radioactive Waste Management Site Safety Assessment Document

    International Nuclear Information System (INIS)

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

  14. Low-level radioactive waste management in Canada

    International Nuclear Information System (INIS)

    In Canada, all low-level radioactive wastes are presently stored. The wastes are classified into two major categories, that is, historic wastes for which the original generator/producer can no longer be held responsible and for which the federal government has assumed residual management responsibility, and ongoing wastes, which are the responsibility of the present waste producers. This paper will present the approach being taken for the management of each class of waste and will also briefly discuss the community-based, cooperative and consultative approach being used to find sites for the long-term management/disposal of historic low-level radioactive wastes

  15. The status of radioactive waste management

    International Nuclear Information System (INIS)

    It is suggested that policies dictating procedures for management of nuclear wastes are being subject to unnecessary influences and regulations should be re-examined. An example is cited of the difficulties faced by the U.S. biomedical facilities because of the closure of low level burial grounds. These problems could have been avoided, since most of the wastes could have been disposed of by on site incineration and other methods applicable to nonradioactive wastes. It is also pointed out that for relatively short-lived nuclides, the reported annual shipment must be corrected for decay. Resistance to marine disposal is discussed; relationships between fish consumption and population dose are mentioned, together with examples based on consumption of Pacific albacor, and sea-food consumption in the San Francisco and New York areas. British experiments in marine waste disposal are cited. In the field of high-level waste management it is suggested that further knowledge of the factors influencing mobilization rates of mineral deposits would help in predicting the behaviour of long-lived nuclides in a geological repository. (U.K.)

  16. Plasma separation process: Disposal of PSP radioactive wastes

    International Nuclear Information System (INIS)

    Radioactive wastes, in the form of natural uranium contaminated scrap hardware and residual materials from decontamination operations, were generated in the PSP facilities in buildings R1 and 106. Based on evaluation of the characteristics of these wastes and the applicable regulations, the various options for the processing and disposal of PSP radioactive wastes were investigated and recommended procedures were developed. The essential features of waste processing included: (1) the solidification of all liquid wastes prior to shipment; (2) cutting of scrap hardware to fit 55-gallon drums and use of inerting agents (diatomaceous earth) to eliminate pyrophoric hazards; and (3) compaction of soft wastes. All PSP radioactive wastes were shipped to the Hanford Site for disposal. As part of the waste disposal process, a detailed plan was formulated for handling and tracking of PSP radioactive wastes, from the point of generation through shipping. In addition, a waste minimization program was implemented to reduce the waste volume or quantity. Included in this document are discussions of the applicable regulations, the types of PSP wastes, the selection of the preferred waste disposal approach and disposal site, the analysis and classification of PSP wastes, the processing and ultimate disposition of PSP wastes, the handling and tracking of PSP wastes, and the implementation of the PSP waste minimization program. 9 refs., 1 fig., 8 tabs

  17. 2012 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site, Nye County, Nevada: Review of the Performance Assessments and Composite Analyses

    Energy Technology Data Exchange (ETDEWEB)

    Shott, G. [National Security Technologies, LLC

    2013-03-18

    The Maintenance Plan for the Performance Assessments and Composite Analyses for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (National Security Technologies, LLC 2007a) requires an annual review to assess the adequacy of the performance assessments (PAs) and composite analyses (CAs), with the results submitted to the U.S. Department of Energy (DOE) Office of Environmental Management. The Disposal Authorization Statements for the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) also require that such reviews be made and that secondary or minor unresolved issues be tracked and addressed as part of the maintenance plan (DOE 1999a, 2000). The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office performed an annual review of the Area 3 and Area 5 RWMS PAs and CAs for fiscal year (FY) 2012. This annual summary report presents data and conclusions from the FY 2012 review, and determines the adequacy of the PAs and CAs. Operational factors (e.g., waste forms and containers, facility design, and waste receipts), closure plans, monitoring results, and research and development (R&D) activities were reviewed to determine the adequacy of the PAs. Likewise, the environmental restoration activities at the Nevada National Security Site (NNSS) relevant to the sources of residual radioactive material that are considered in the CAs, the land-use planning, and the results of the environmental monitoring and R&D activities were reviewed to determine the adequacy of the CAs. Important developments in FY 2012 include the following: Release of a special analysis for the Area 3 RWMS assessing the continuing validity of the PA and CA; Development of a new Area 5 RWMS closure inventory estimate based on disposals through FY 2012; Evaluation of new or revised waste streams by special analysis; and Development of version 4.114 of the Area 5 RWMS GoldSim PA model. The Area 3 RWMS has been in inactive status since

  18. Karlsruhe Database for Radioactive Wastes (KADABRA) - Accounting and Management System for Radioactive Waste Treatment - 12275

    Energy Technology Data Exchange (ETDEWEB)

    Himmerkus, Felix; Rittmeyer, Cornelia [WAK Rueckbau- und Entsorgungs- GmbH, 76339 Eggenstein-Leopoldshafen (Germany)

    2012-07-01

    The data management system KADABRA was designed according to the purposes of the Cen-tral Decontamination Department (HDB) of the Wiederaufarbeitungsanlage Karlsruhe Rueckbau- und Entsorgungs-GmbH (WAK GmbH), which is specialized in the treatment and conditioning of radioactive waste. The layout considers the major treatment processes of the HDB as well as regulatory and legal requirements. KADABRA is designed as an SAG ADABAS application on IBM system Z mainframe. The main function of the system is the data management of all processes related to treatment, transfer and storage of radioactive material within HDB. KADABRA records the relevant data concerning radioactive residues, interim products and waste products as well as the production parameters relevant for final disposal. Analytical data from the laboratory and non destructive assay systems, that describe the chemical and radiological properties of residues, production batches, interim products as well as final waste products, can be linked to the respective dataset for documentation and declaration. The system enables the operator to trace the radioactive material through processing and storage. Information on the actual sta-tus of the material as well as radiological data and storage position can be gained immediately on request. A variety of programs accessed to the database allow the generation of individual reports on periodic or special request. KADABRA offers a high security standard and is constantly adapted to the recent requirements of the organization. (authors)

  19. Karlsruhe Database for Radioactive Wastes (KADABRA) - Accounting and Management System for Radioactive Waste Treatment - 12275

    International Nuclear Information System (INIS)

    The data management system KADABRA was designed according to the purposes of the Cen-tral Decontamination Department (HDB) of the Wiederaufarbeitungsanlage Karlsruhe Rueckbau- und Entsorgungs-GmbH (WAK GmbH), which is specialized in the treatment and conditioning of radioactive waste. The layout considers the major treatment processes of the HDB as well as regulatory and legal requirements. KADABRA is designed as an SAG ADABAS application on IBM system Z mainframe. The main function of the system is the data management of all processes related to treatment, transfer and storage of radioactive material within HDB. KADABRA records the relevant data concerning radioactive residues, interim products and waste products as well as the production parameters relevant for final disposal. Analytical data from the laboratory and non destructive assay systems, that describe the chemical and radiological properties of residues, production batches, interim products as well as final waste products, can be linked to the respective dataset for documentation and declaration. The system enables the operator to trace the radioactive material through processing and storage. Information on the actual sta-tus of the material as well as radiological data and storage position can be gained immediately on request. A variety of programs accessed to the database allow the generation of individual reports on periodic or special request. KADABRA offers a high security standard and is constantly adapted to the recent requirements of the organization. (authors)

  20. Radioactive waste management challenges and progress in Iraq - 59164

    International Nuclear Information System (INIS)

    The government of Iraq, through the Ministry of Science and Technology (MoST) is decommissioning Iraq's former nuclear facilities. The 18 former facilities at the Al-Tuwaitha Nuclear Research Center near Baghdad include partially destroyed research reactors, a fuel fabrication facility and radioisotope production facilities. These 18 former facilities contain large numbers of silos and drums of un-characterized radioactive waste and approximately 30 tanks that contain or did contain un-characterized liquid radioactive wastes. Other key sites outside of Al Tuwaitha include facilities at Jesira (uranium processing and waste storage facility), Rashdiya (centrifuge facility) and Tarmiya (enrichment plant). The newly created Radioactive Waste Treatment Management Directorate (RWTMD) within MoST is responsible for Iraq's centralized management of radioactive waste, including safe and secure disposal. In addition to being responsible for the un-characterized wastes at Al Tuwaitha, the RWTMD will be responsible for future decommissioning wastes, approximately 900 disused sealed radioactive sources, and unknown quantities of NORM wastes from oil production in Iraq. This paper presents the challenges and progress that the RWTMD has made in setting-up a radioactive waste management program. The progress includes the establishment of a staffing structure, staff, participation in international training, rehabilitation of portions of the former Radioactive Waste Treatment Station at Al-Tuwaitha and the acquisition of equipment. (authors)

  1. Storage and disposal of radioactive waste as glass in canisters

    Energy Technology Data Exchange (ETDEWEB)

    Mendel, J.E.

    1978-12-01

    A review of the use of waste glass for the immobilization of high-level radioactive waste glass is presented. Typical properties of the canisters used to contain the glass, and the waste glass, are described. Those properties are used to project the stability of canisterized waste glass through interim storage, transportation, and geologic disposal.

  2. This is how we manage Sweden`s radioactive waste. Activities 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-31

    SKB operates systems and facilities for the management and final disposal of spent nuclear fuel and other radioactive waste in Sweden. SKB has conducted extensive R, D and D work with regard to constructing a spent fuel encapsulation plant and a deep repository in crystalline bedrock. This annual report treats all the different activities without going into technical details.

  3. Management of radioactive waste generated in nuclear medicine

    International Nuclear Information System (INIS)

    Nuclear medicine is a clinical specialty in which radioactive material is used in non-encapsulated form, for the diagnosis and treatment of patients. Nuclear medicine involves administering to a patient a radioactive substance, usually liquid, both diagnostic and therapeutic purposes. This process generates solid radioactive waste (syringes, vials, gloves) and liquid (mainly the patient's urine). (Author)

  4. Phase IV testing of monosodium titanate adsorption with radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Hobbs, D.T.

    1999-12-08

    Testing examined the extent and rate of strontium, plutonium, uranium, and neptunium removal from radioactive waste solutions at 4.5M and 7.5M in Na concentration by adsorption onto monosodium titanate (MST) at 0.2 g/L. Results indicate that the extents and rates of strontium, plutonium, and neptunium removal in radioactive waste solutions agree well with those previously measured using simulated waste solutions. Uranium removal in the 7.5M Na radioactive waste solution proved similar to that observed with simulated waste solutions. Uranium removal in the 4.5M Na radioactive waste solution proved lower than expected from previous simulant tests. The authors conclude that MST adsorption data obtained from simulated waste solutions provide reliable predictions for use in facility design and flowsheet modeling studies in the Salt Disposition Alternatives program.

  5. Controlled Containment, Radioactive Waste Management in the Netherlands

    Energy Technology Data Exchange (ETDEWEB)

    Codee, H.

    2002-02-26

    All radioactive waste produced in The Netherlands is managed by COVRA, the central organization for radioactive waste. The Netherlands forms a good example of a country with a small nuclear power program which will end in the near future. However, radioisotope production, nuclear research and other industrial activities will continue to produce radioactive waste. For the small volume, but broad spectrum of radioactive waste, including TENORM, The Netherlands has developed a management system based on the principles to isolate, to control and to monitor the waste. Long term storage is an essential element of the management system and forms a necessary step in the strategy of controlled containment that will ultimately result in final removal of the waste. Since the waste will remain retrievable for long time new technologies and new disposal options can be applied when available and feasible.

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

    International Nuclear Information System (INIS)

    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

  7. NEW CRITERIA FOR ASSIGNING WASTE CONTAINING TECH-NOGENIC RADIONUCLIDES TO THE RADIOACTIVE WASTE

    OpenAIRE

    I. K. Romanovich; M. I. Balonov; Barkovsky, A.N.

    2016-01-01

    The article contains detailed description of criteria for assigning of liquid and gaseous industrial waste containing technogenicradionuclides to the radioactive waste, presented in the new Basic Sanitary Rulesof Radiation Safety (OSPORB-99/2010). The analysisof shortcomings and discrepancies of the previously used in Russia system of criteria for assigning waste to the radioactive waste is given.

  8. NEW CRITERIA FOR ASSIGNING WASTE CONTAINING TECH-NOGENIC RADIONUCLIDES TO THE RADIOACTIVE WASTE

    Directory of Open Access Journals (Sweden)

    I. K. Romanovich

    2010-01-01

    Full Text Available The article contains detailed description of criteria for assigning of liquid and gaseous industrial waste containing technogenicradionuclides to the radioactive waste, presented in the new Basic Sanitary Rulesof Radiation Safety (OSPORB-99/2010. The analysisof shortcomings and discrepancies of the previously used in Russia system of criteria for assigning waste to the radioactive waste is given.

  9. Recent approach in treatment of liquid radioactive waste: membrane methods

    International Nuclear Information System (INIS)

    Full text: The fuel cycle produces different types of radioactive waste. Radioactive waste is also generated during production and application of radioisotopes, as well as during processing of raw materials containing naturally occurring radioactive isotopes. All those wastes have to be treated and conditioned before safe storage or disposal to protect the human health and natural environment. The management of radioactive waste has to be reached with reasonable cost by implementing appropriate technologies. The processing requirements depend on the level of radioactivity and chemical and physical properties of the waste streams. Various methods are used to treat aqueous radioactive wastes, including evaporation, chemical precipitation and ion exchange, as well as less developed solvent extraction, biotechnological processes and membrane methods. Although membrane processes are still considered as novel technologies in the field of radioactive waste treatment, many applications in nuclear centres and laboratories around the world are reported. At the Department of Nuclear Methods of Process Engineering, Institute of Nuclear Chemistry and Technology, for many years membrane techniques are studied and considered as a possible application in radioactive wastes processing field. After some years of research reverse osmosis was applied at Institute of Atomic Energy (Department of Radioactive Waste Treatment) processing the radioactive wastes from all of Poland. The 3-stage RO plant supplements the existing waste processing system based on evaporator giving the possibility of initial concentration of liquid waste or final polishing of the condensate after evaporation. Intensive studies on ultrafiltration (UF) enhanced by sorption on different sorbents or complexation with chelating polymers are carried on. The ceramic membranes made from alumina, titania and zirconia are used in experiments. Such membranes show high chemical, temperature and radiation resistance. They

  10. Measurement Technology on 200 Liters Barrels of Radioactive Waste

    Institute of Scientific and Technical Information of China (English)

    BAI; Lei; SHAO; Jie-wen; LIU; Da-ming; LIU; Hong-bin; CHENG; Yi-mei; HE; Li-xia; ZHU; Li-qun

    2012-01-01

    <正>The measurement device on 200 liters barrel of radioactive waste is designed following the rule of orderly measurement automatically, by using the technology of non-destructive to measure the mass of radioactive waste produced from fuel cycle. Device objects as shown in Fig. 1, which consists of the

  11. Radioactive waste management national policy and strategy in Cuba

    International Nuclear Information System (INIS)

    Due to the use of sources of ionizing radiation, radioactive wastes are generated which require an adequate management in conditions of radiological safety and protection during all phases; from their generation to their final disposal, for protecting human health and the environment, both currently and in the future, without imposing undue burden upon the next generations. Therefore there was a need for the establishment of a National Policy and Strategy with regard to the management of the radioactive wastes generated, in a way such that allows long term considerations in conception and vision, having as a reference; the legal framework in force in Cuba, the IAEA's recommendations, as well as the diagnosis and assessment of the current and future situation in Cuba. This work deals with key issues for the safe management of the radioactive wastes such as; objectives and goals, responsibilities and role of the organizations involved in the management, possible management options for each type of radioactive waste generated in the country, manpower and funding for an adequate management, control over the generation of the radioactive wastes, and the need for availability of a facility for their final disposal, among other issues. The Policy and Strategy for the management of radioactive wastes will serve as a basis for the users/facilities, that generate and manage radioactive wastes, to draft their own strategies, and for the achievement of a harmonized level of radioactive wastes in the country. Furthermore, they would contribute to enhance the National Environmental Strategy implemented in Cuba. (author)

  12. Technological progress in the management of radioactive waste

    International Nuclear Information System (INIS)

    The present report is the second part of a study which is aimed at evaluating the present situation and selecting the most interesting fields for research and development work on radioactive waste handling. It gives a detailed analysis on various techniques in the development stage or which can be envisaged in order to bring improvements in particular fields of radioactive waste handling and disposal

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

    Science.gov (United States)

    Dukert, Joseph M.

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

  14. Proceedings of the 1st workshop on radioactive waste treatment technologies, October 28, 1997 Taejon, Korea

    International Nuclear Information System (INIS)

    This proceedings describes the volume reduction of radioactive waste, the radioactive waste treatment technology, the decontamination and decommissioning, and the incineration and solidification of radioactive waste. Twenty two papers are submitted

  15. Proceedings of the 1st workshop on radioactive waste treatment technologies, October 28, 1997 Taejon, Korea

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    This proceedings describes the volume reduction of radioactive waste, the radioactive waste treatment technology, the decontamination and decommissioning, and the incineration and solidification of radioactive waste. Twenty two papers are submitted.

  16. Proceedings: a workshop on issue pertinent to the development of environmental protection criteria for radioactive wastes

    International Nuclear Information System (INIS)

    The results are presented from three working groups on approaches to radioactive waste management criteria development, risk considerations of radioactive waste management, and long-term implications of radioactive waste management

  17. Significance of radiation effects in solid radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Permar, P H; McDonell, W R

    1980-01-01

    Proposed NRC criteria for disposal of high-level nuclear waste require development of waste packages to contain radionuclide for at least 1000 years, and design of repositories to prevent radionuclide release at an annual rate greater than 1 part in 100,000 of the total activity. The high-level wastes that are now temporarily stored as aqueous salts, sludges, and calcines must be converted to high-integrity solid forms that resist deterioration from radiation and other effects of long-term storage. Spent fuel may be encapsulated for similar long-term storage. Candidate waste forms beside the spent fuel elements themselves, include borosilicate and related glasses, mineral-like crystalline ceramics, concrete formulations, and metal-matrix glass or ceramic composites. these waste forms will sustain damage produced by beta-gamma radiation up to 10/sup 12/ rads, by alpha radiation up to 10/sup 19/ particles/g, by internal helium generation greater than about 0.1 atom percent, and by the atom transmutations accompanying radioactive decay. Current data indicate that under these conditions the glass forms suffer only minor volume changes, stored energy deposition, and leachability effects. The crystalline ceramics appear susceptible to the potentially more severe alterations accompanying metamictization and natural analogs of candidate materials are being examined to establish their suitability as waste forms. Helium concentrations in the waste forms are generally below thresholds for severe damage in either glass or crystalline ceramics at low temperatures, but microstructural effects are not well characterized. Transmutation effects remain to be established.

  18. The Dutch geologic radioactive waste disposal project

    International Nuclear Information System (INIS)

    The Final Report reviews the work on geologic disposal of radioactive waste performed in the Netherlands over the period 1 January 1978 to 31 December 1979. The attached four topical reports cover detailed subjects of this work. The radionuclide release consequences of an accidental flooding of the underground excavations during the operational period was studied by the institute for Atomic Sciences in Agriculture (Italy). The results of the quantitative examples made for different effective cross-sections of the permeable layer connecting the mine excavations with the boundary of the salt dome, are that under all circumstances the concentration of the waste nuclides in drinking water will remain well within the ICRP maximum permissible concentrations. Further analysis work was done on what minima can be achieved for both the maximum local rock salt temperatures at the disposal borehole walls and the maximum global rock salt temperatures halfway between a square of disposal boreholes. Different multi-layer disposal configurations were analysed and compared. A more detailed description is given of specific design and construction details of a waste repository such as the shaft sinking and construction, the disposal mine development, the mine ventilation and the different plugging and sealing procedures for both the disposal boreholes and the shafts. Thanks to the hospitality of the Gesellschaft fuer Strahlenforschung, an underground working area in the Asse mine became available for performing a dry drilling experiment, which resulted successfully in the drilling of a 300 m deep disposal borehole from a mine room at the -750 m level

  19. Ocean disposal of high level radioactive waste

    International Nuclear Information System (INIS)

    This study confirms, subject to limitations of current knowledge, the engineering feasibility of free fall penetrators for High Level Radioactive Waste disposal in deep ocean seabed sediments. Restricted sediment property information is presently the principal bar to an unqualified statement of feasibility. A 10m minimum embedment and a 500 year engineered barrier waste containment life are identified as appropriate basic penetrator design criteria at this stage. A range of designs are considered in which the length, weight and cross section of the penetrator are varied. Penetrators from 3m to 20m long and 2t to 100t in weight constructed of material types and thicknesses to give a 500 year containment life are evaluated. The report concludes that the greatest degree of confidence is associated with performance predictions for 75 to 200 mm thick soft iron and welded joints. A range of lengths and capacities from a 3m long single waste canister penetrator to a 20m long 12 canister design are identified as meriting further study. Estimated embedment depths for this range of penetrator designs lie between 12m and 90m. Alternative manufacture, transport and launch operations are assessed and recommendations are made. (author)

  20. Ocean disposal of heat generating radioactive waste

    International Nuclear Information System (INIS)

    A study of container designs for heat generating radioactive waste disposal in the deep ocean sediments is presented. The purpose of the container would be to isolate the waste from the environment for a period of 500 to 1000 years. The container designs proposed are based on the use of either corrosion allowance or corrosion resistant metals. Appropriate overpack wall thicknesses are suggested for each design using the results of corrosion studies and experiments but these are necessarily preliminary and data relevant to corrosion in deep ocean sediments remain sparse. It is concluded that the most promising design concept involves a thin titanium alloy overpack in which all internal void spaces are filled with lead or cement grout. In situ temperatures for the sediment adjacent to the emplaced 50 year cooled waste containers are calculated to reach about 260 deg C. The behaviour of the sediments at such a high temperature is not well understood and the possibility of 100 years interim storage is recommended for consideration to allow further cooling. Further corrosion data and sediment thermal studies would be required to fully confirm the engineering feasibility of these designs. (author)

  1. Incineration of Non-radioactive Simulated Waste

    International Nuclear Information System (INIS)

    An advanced controlled air incinerator has been investigated, developed and put into successful operation for both non radioactive simulated and other combustible solid wastes. Engineering efforts concentrated on providing an incinerator which emitted a clean, easily treatable off-gas and which produced minimum amounts of secondary waste. Feed material is fed by gravity into the gas reactor without shredding or other pretreatment. The temperature of the waste is gradually increased in a reduced oxygen atmosphere as the resulting products are introduced into the combustion chamber. Steady burning is thus accomplished under easily controlled excess air conditions with the off-gas then passing through a simple dry cleaning-up system. Experimental studies showed that, at lower temperature, CO2, and CH4 contents in gas reactor effluent increase by the increase of glowing bed temperature, while H2O, H2 and CO decrease . It was proved that, a burn-out efficiency (for ash residues) and a volume reduction factor appeared to be better than 95.5% and 98% respectively. Moreover, high temperature permits increased volumes of incinerated material and results in increased gasification products. It was also found that 8% by weight of ashes are separated by flue gas cleaning system as it has chemical and size uniformity. This high incineration efficiency has been obtained through automated control and optimization of process variables like temperature of the glowing bed and the oxygen feed rate to the gas reactor

  2. Management of low-level radioactive wastes around the world

    International Nuclear Information System (INIS)

    This paper reviews the status of various practices used throughout the world for managing low-level radioactive wastes. Most of the information in this review was obtained through the DOE-sponsored International Program Support Office (IPSO) activities at Pacific Northwest Laboratory (PNL) at Richland, Washington. The objective of IPSO is to collect, evaluate, and disseminate information on international waste management and nuclear fuel cycle activities. The center's sources of information vary widely and include the proceedings of international symposia, papers presented at technical society meetings, published topical reports, foreign trip reports, and the news media. Periodically, the information is published in topical reports. Much of the information contained in this report was presented at the Fifth Annual Participants' Information Meeting sponsored by DOE's Low-Level Waste Management Program Office at Denver, Colorado, in September of 1983. Subsequent to that presentation, the information has been updated, particularly with information provided by Dr. P. Colombo of Brookhaven National Laboratory who corresponded with low-level waste management specialists in many countries. The practices reviewed in this paper generally represent actual operations. However, major R and D activities, along with future plans, are also discussed. 98 refs., 6 tabls

  3. Management of low-level radioactive wastes around the world

    Energy Technology Data Exchange (ETDEWEB)

    Lakey, L.T.; Harmon, K.M.; Colombo, P.

    1985-04-01

    This paper reviews the status of various practices used throughout the world for managing low-level radioactive wastes. Most of the information in this review was obtained through the DOE-sponsored International Program Support Office (IPSO) activities at Pacific Northwest Laboratory (PNL) at Richland, Washington. The objective of IPSO is to collect, evaluate, and disseminate information on international waste management and nuclear fuel cycle activities. The center's sources of information vary widely and include the proceedings of international symposia, papers presented at technical society meetings, published topical reports, foreign trip reports, and the news media. Periodically, the information is published in topical reports. Much of the information contained in this report was presented at the Fifth Annual Participants' Information Meeting sponsored by DOE's Low-Level Waste Management Program Office at Denver, Colorado, in September of 1983. Subsequent to that presentation, the information has been updated, particularly with information provided by Dr. P. Colombo of Brookhaven National Laboratory who corresponded with low-level waste management specialists in many countries. The practices reviewed in this paper generally represent actual operations. However, major R and D activities, along with future plans, are also discussed. 98 refs., 6 tabls.

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

    International Nuclear Information System (INIS)

    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. Hospitalar radioactive waste of low activity, a daily practice

    Energy Technology Data Exchange (ETDEWEB)

    Rezio, M.T.; Vieira, M.R. [Instituto Portugues de Oncologia de Francisco Gentil - CROL, Lisboa (Portugal)

    2006-07-01

    Introduction According to the law we should have a specific area for storing and treating waste. That area should have special containers for temporary storage in order to assure the radioactive decay for all the radioactive waste, biological contaminated or non biological and in solid or liquid form. According with that law the limits established for discharge are: For solid waste, we must not discharge more than 370 MBq in a minimum volume of 0,1 m{sup 3} and is not allowed waste with activities higher than 3,7 kBq; For liquid waste discharges from the department to the public sewer, the average concentrations calculated taking into account the water flow of the sewer system that serves the installation, should be the following:The annual medium concentration must not exceed 3 times the reference concentration (C.R.) for that nuclide; The monthly medium concentration must not exceed 15 times the reference concentration (C.R.); The daily medium concentration must not exceed 60 times the reference concentration (C.R.); The reference concentration (C.R.), expressed in Bq.m{sup -3}, should be calculated taking into account the relevant incorporation per ingestion. The calculation of C.R. in liquid waste should have into account the following: For the general public the effective dose E achieved, per ingestion by an individual in the group of age g is determined according to the following formula(1):E= {sigma}{sub i} h(g){sub j,ing} X J{sub j,ing}, where h(g){sub j,ing} is the committed effective dose per unit-intake for the ingested radionuclide j (Sv/Bq) by an individual in the group of age g; J{sub j,ing} is the relevant intake via ingestion of the radionuclide j (Bq). The effective dose E achieved by an individual in the group of age g should not be higher than 0,1 mSv/year. If the average water volume ingested by an individual adult is 800 l, the value J{sub j,ing}, calculated by the formula (1) should be referred to 1000 l, in order to obtain the C.R., for the

  6. Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities

    International Nuclear Information System (INIS)

    One critical aspect of any denuclearization of the Democratic People's Republic of Korea (DPRK) involves dismantlement of its nuclear facilities and management of their associated radioactive wastes. The decommissioning problem for its two principal operational plutonium facilities at Yongbyun, the 5MWe nuclear reactor and the Radiochemical Laboratory reprocessing facility, alone present a formidable challenge. Dismantling those facilities will create radioactive waste in addition to existing inventories of spent fuel and reprocessing wastes. Negotiations with the DPRK, such as the Six Party Talks, need to appreciate the enormous scale of the radioactive waste management problem resulting from dismantlement. The two operating plutonium facilities, along with their legacy wastes, will result in anywhere from 50 to 100 metric tons of uranium spent fuel, as much as 500,000 liters of liquid high-level waste, as well as miscellaneous high-level waste sources from the Radiochemical Laboratory. A substantial quantity of intermediate-level waste will result from disposing 600 metric tons of graphite from the reactor, an undetermined quantity of chemical decladding liquid waste from reprocessing, and hundreds of tons of contaminated concrete and metal from facility dismantlement. Various facilities for dismantlement, decontamination, waste treatment and packaging, and storage will be needed. The shipment of spent fuel and liquid high level waste out of the DPRK is also likely to be required. Nuclear facility dismantlement and radioactive waste management in the DPRK are all the more difficult because of nuclear nonproliferation constraints, including the call by the United States for 'complete, verifiable and irreversible dismantlement,' or 'CVID.' It is desirable to accomplish dismantlement quickly, but many aspects of the radioactive waste management cannot be achieved without careful assessment, planning and preparation, sustained commitment, and long completion times

  7. Radioactive materials released from nuclear power plants. Annual report 1991, Volume 12

    Energy Technology Data Exchange (ETDEWEB)

    Tichler, J.; Doty, K.; Congemi, J. [Brookhaven National Lab., Upton, NY (United States)

    1994-05-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1991 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1991 release data are summarized in tabular form. Data Covering specific radionuclides are summarized.

  8. Radioactive materials released from nuclear power plants: Annual report, 1993. Volume 14

    Energy Technology Data Exchange (ETDEWEB)

    Tichler, J.; Doty, K.; Lucadamo, K. [Brookhaven National Lab., Upton, NY (United States)

    1995-12-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1993 have been compiled and reported. The summary data for the years 1974 through 1992 are included for comparison. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1993 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

  9. Radioactive materials released from nuclear power plants. Volume 13, Annual report 1992

    Energy Technology Data Exchange (ETDEWEB)

    Tichler, J.; Doty, K.; Lucadamo, K. [Brookhaven National Lab., Upton, NY (United States)

    1995-08-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1992 have been compiled and reported. The summary data for the years 1973 through 1991 are included for comparison. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1992 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

  10. Radioactive materials released from nuclear power plants. Volume 11: Annual report, 1990

    Energy Technology Data Exchange (ETDEWEB)

    Tichler, J.; Doty, K.; Congemi, J. [Brookhaven National Lab., Upton, NY (United States)

    1993-10-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1990 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1990 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

  11. Radioactive materials released from nuclear power plants. Annual report 1989: Volume 10

    Energy Technology Data Exchange (ETDEWEB)

    Tichler, J.; Norden, K.; Congemi, J. [Brookhaven National Lab., Upton, NY (United States)

    1992-09-01

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1989 have been compiled and reported. The summary data for the years 1970 through 1988 are included for comparison. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1989 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

  12. Radioactive materials released from nuclear power plants. Annual report 1981. Vol. 2

    International Nuclear Information System (INIS)

    Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1981 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1981 release data are summarized in tabular form. Data covering specific radionuclides are summarized

  13. Development of polymer concrete radioactive waste management containers

    International Nuclear Information System (INIS)

    A high-integrity radioactive waste container has been developed to immobilize the spent resin wastes from nuclear power plants, protect possible future, inadvertent intruders from damaging radiation. The polymer concrete container is designed to ensure safe and reliable disposal of the radioactive waste for a minimum period of 300 years. A built-in vent system for each container will permit the release of gas. An experimental evaluation of the mechanical, chemical, and biological tests of the container was carried out. The tests showed that the polymer concrete container is adequate for safe disposal of the radioactive wastes. (author)

  14. Development of polymer concrete radioactive waste management containers

    Energy Technology Data Exchange (ETDEWEB)

    Chung, H.; Lee, M. S.; Ahn, D. H.; Won, H. J.; Kang, H. S.; Lee, H. S.; Lim, S.P.; Kim, Y. E.; Lee, B. O.; Lee, K. P.; Min, B. Y.; Lee, J.K.; Jang, W. S.; Sim, W. B.; Lee, J. C.; Park, M. J.; Choi, Y. J.; Shin, H. E.; Park, H. Y.; Kim, C. Y

    1999-11-01

    A high-integrity radioactive waste container has been developed to immobilize the spent resin wastes from nuclear power plants, protect possible future, inadvertent intruders from damaging radiation. The polymer concrete container is designed to ensure safe and reliable disposal of the radioactive waste for a minimum period of 300 years. A built-in vent system for each container will permit the release of gas. An experimental evaluation of the mechanical, chemical, and biological tests of the container was carried out. The tests showed that the polymer concrete container is adequate for safe disposal of the radioactive wastes. (author)

  15. Fixation of radioactive waste by HHP method

    International Nuclear Information System (INIS)

    Simulated high-level radioactive waste was fixed into a silica matrix and tritiated water was fixed into glass powder matrix by a hydrothermal hot-pressing (HHP) method. The simulated HLW and the silica matrix were mixed with NaOH solution and then solidified. When the starting powder was solidified at 350degC, and 66 MPa for 6 h by the use of 10N NaOH solution, the solid body with high compressive strength was produced. From the result by modified MCC-1 leach test, the leach rate of Cs and Sr from solid body was much lower than a concrete form but slightly higher than a glass form. Tritiated water was solidified with only glass powder. The amount of tritiated water fixed by HHP was almost the same as fixed by the ordinary cement solidifying procedure. The compressive strength of the body was higher than that of the cement body. (author)

  16. Slovac Republic repository of radioactive waste

    Directory of Open Access Journals (Sweden)

    M. Bartko

    2014-01-01

    Full Text Available The Slovac Republic Repository of Radioactive Waste (radwaste in place Mochovce presents a multi-barrier repository of the surface type designed as an ultimate storage of treated solid and fixed, low-and very low-level radwaste generated during the operation and decommissioning of the nuclear power plants, in research institutes, laboratories and hospitals in the Slovak Republic. The isolation of the radwaste and retardation of the radionuclides are provided by the barrier system of the repository. To assess the complete system and parts of one of the most important barriers – the multi-barrier ultimate shielding of the repository – the model of the ultimate shielding of the repository was designed. The monitoring results of the model “ in situ“ will be applicable for projecting the ultimate shielding of the repository.

  17. Ocean disposal of heat generating radioactive waste

    International Nuclear Information System (INIS)

    The feasibility of safe ocean disposal options for heat-generating radioactive waste relies on the existence of suitable disposal sites. This review considers the status of the development of site selection criteria and the results of the study area investigations carried out under various national and international research programmes. In particular, the usefulness of the results obtained is related to the data needed for environmental and emplacement modelling. Preliminary investigations have identified fifteen potential deep ocean study areas in the North Atlantic. From these Great Meteor East (GME), Southern Nares Abyssal Plan (SNAP) and Kings Trough Flank (KTF) were selected for further investigation. The review includes appraisals of regional geology, geophysical studies, sedimentology, geotechnical studies, geochemical studies and oceanography. (author)

  18. Management of radioactive waste in Kazakhstan: Problems and solutions

    International Nuclear Information System (INIS)

    The paper studies the history of the accumulation and research of distribution of radioactive waste in Kazakhstan. Currently, on the territory of Kazakhstan, a large volume (up to 240 million tons) of radioactive waste has accumulated. These wastes have various origins ranging from nuclear explosions waste up to those formed under uranium mining and milling. The main wastes are those formed under uranium extraction. In addition, an important part of wastes is that formed under the mining of non-uranium ores including radioactive mineralization (coal, base metals and rare earths, etc), as well as under oil extraction. The aggregate volume of such wastes is 98% of the total. Currently, the management of radioactive wastes in Kazakhstan is becoming more active. Use of the in-situ leaching method instead of uranium mining is very important for the uranium industry of Kazakhstan. This method allows to decrease radioactive waste formation under uranium extraction and to reduce the environmental impact of the uranium industry. At the same time, it is necessary for Kazakhstan to resolve a large variety of questions concerning radioactive waste problems. (author)

  19. Where are the radioactive wastes in France? 2006 geographic inventory of radioactive wastes

    International Nuclear Information System (INIS)

    This document presents, by region, the localization of existing radioactive wastes in France at the date of December 31, 2004. In addition to the geographic situation, this inventory is presented by site and by category of waste producer or owner. The collection of these data is based on the free declaration made by waste owners or producers. The gathered information has been reformatted and homogenized and is reported in a synthetic way in the form of tables and files. Thus, 899 sites have been indexed, among which 159 are presented in the form of a detailed file. For each region, a table details the registered sites by category of producer/owner and the location of the main ones is reported on a regional map. The registered waste producers are radionuclide users belonging to 4 specific domains: medical, research, industry and national defense. The corresponding wastes are in general modest both in quantity and activity. The sites polluted by radioactive substances are also mentioned, even if they are already decontaminated or not. (J.S.)

  20. The disposal of radioactive waste on land

    Energy Technology Data Exchange (ETDEWEB)

    None

    1957-09-01

    A committee of geologists and geophysicists was established by the National Academy of Sciences-National Research Council at the request of the Atomic Energy Commission to consider the possibilities of disposing of high level radioactive wastes in quantity within the continental limits of the United States. The group was charged with assembling the existing geologic information pertinent to disposal, delineating the unanswered problems associated with the disposal schemes proposed, and point out areas of research and development meriting first attention; the committee is to serve as continuing adviser on the geological and geophysical aspects of disposal and the research and development program. The Committee with the cooperation of the Johns Hopkins University organized a conference at Princeton in September 1955. After the Princeton Conference members of the committee inspected disposal installations and made individual studies. Two years consideration of the disposal problems leads to-certain general conclusions. Wastes may be disposed of safely at many sites in the United States but, conversely, there are many large areas in which it is unlikely that disposal sites can be found, for example, the Atlantic Seaboard. Disposal in cavities mined in salt beds and salt domes is suggested as the possibility promising the most practical immediate solution of the problem. In the future the injection of large volumes of dilute liquid waste into porous rock strata at depths in excess of 5,000 feet may become feasible but means of rendering, the waste solutions compatible with the mineral and fluid components of the rock must first be developed. The main difficulties, to the injection method recognized at present are to prevent clogging of pore space as the solutions are pumped into the rock and the prediction or control of the rate and direction of movement.

  1. Engineered barriers for radioactive waste confinement

    Directory of Open Access Journals (Sweden)

    Fernández, R.

    2011-09-01

    Full Text Available Nuclear power plants generate long-lived radioactive waste of high toxicity. The security assessment of repositories destined to definitive confinement of radioactive waste has been studied for several decades. Deep geological repositories are technically feasible and begin to be built by some pioneer countries. The scientific evaluation of interactions between the different engineered barriers is studied by laboratory experiments, natural analogues and modeling studies. The three methods are able to represent and validate the main geochemical processes that take place in the near field. This paper reviews the scientific and technical basis of the concept of geological disposal, with particular focus on the methods of study applied to the evaluation of geochemical stability of the bentonite barrier.

    Las centrales nucleares generan residuos radiactivos de elevada peligrosidad y permanencia en el tiempo. La evaluación de la seguridad de repositorios destinados al alojamiento definitivo de estos residuos lleva estudiándose desde hace varias décadas. El almacenamiento geológico es técnicamente factible y empieza ya a desarrollarse en países pioneros. La evaluación científica de las interacciones entre las distintas barreras de ingeniería se estudia mediante ensayos de laboratorio, análisis de análogos naturales y modelos teóricos. Las tres vías de estudio son capaces de representar y validar los principales procesos geoquímicos que tienen lugar en el campo cercano al repositorio. Este artículo revisa los fundamentos científicos y técnicos del concepto de almacenamiento geológico detallando, en particular, los métodos de estudio aplicados a la evaluación de la estabilidad geoquímica de la barrera de bentonita.

  2. Low and medium level radioactive waste disposal in France

    Energy Technology Data Exchange (ETDEWEB)

    Potier, J.M.

    1994-12-31

    ANDRA, as the national radioactive waste management agency of France, was created in 1979 as part of the French Atomic Energy, Commission and is responsible for radioactive waste disposal. Legislation passed on December 30, 1991 gave ANDRA greater autonomy and responsibility for radioactive waste management by making it a Public Service Company separate from the CEA and by placing it under the supervisory authority of the Ministries of Industry, of the Environment and of Research. The legislation specifically delegates the following responsibilities to ANDRA: (1) establishment of specifications for radioactive waste solidification and disposal; (2) design, siting and construction of new waste disposal facilities; (3) disposal facility operations; and (4) participation in research on, and design and construction of, isolation systems for long lived waste.

  3. European experience with asphalt packaging of radioactive wastes

    International Nuclear Information System (INIS)

    In Europe, the use of asphalt is synonymous with volume reduction of low and medium level radioactive waste. It started at Marcoule, France in the early 1960's and soon was adopted by Karlsruhe in West Germany, Eurochemic in Belgium, and in other countries. The use of an asphalt (or bitumen) binder, or immobilizing agent, in the VRS (Volume Reduction and Solidification) process proved to be beneficial in many ways. At Karlsruhe, for example, the VRS asphalt system replaced a cement system (non-volume reducing) and resulted in two drums of solidified waste versus ten with cement. This process reduced the transportation problem considerably. Asphalt is an inert, waterproof material and provides significantly improved package integrity under all conditions of on-site storage, transportation, and burial. The asphalt VRS system provides considerable cost savings, particularly for the recurring items such as binder, containers, transportation, and burial. These annual savings may approach $500,000 annually for a 1000 MWe nuclear plant. End product advantages include higher resistance to leaching and other environmental impacts, as well as less internal corrosion of the drums

  4. Management of radioactive wastes from non-power applications - Sharing the experience. Proceedings

    International Nuclear Information System (INIS)

    Radioactive materials are used extensively in the industrial, medical, agricultural, research and education sectors owing to the favourable properties of some specific radionuclides, their commercial availability and their reasonable cost. The annual consumption of these materials is growing, both in developing and in developed countries, resulting in generation of radioactive waste of different forms and natures. Thus the growing number of radionuclide applications is mirrored by increasing demands for efficient management of the associated radioactive waste. Management of the waste requires special techniques, trained personnel and an appropriate regulatory framework, all of which should be fully available in the countries where such materials are used. The growing number of nuclear applications underscores the increasing importance of the associated handling, processing, storage and disposal of the radioactive waste generated. A specific issue is the decommissioning of old facilities, since their original design in some cases may not correspond to modern safety requirements or are due to inadequate functional capabilities. A wide variety of technical options have been developed and are available for processing of radioactive waste generated both by the nuclear power industry and by different nuclear applications. The selection of an appropriate technology for waste processing depends mainly on the characteristics of the waste, the scale of waste production and the requirements for the final waste forms. The types, volumes and characteristics of the wastes generated from nuclear applications vary considerably, such that in many cases different approaches are needed for the whole system of treatment, conditioning and storage of these wastes. The primary objective of the conference was to provide an opportunity for experts in this field to meet and exchange information, and to discuss experience, specific practices and technical solutions used in the management of

  5. Low-level radioactive waste in the northeast: disposal volume projections

    International Nuclear Information System (INIS)

    The northeastern states, with support of the Coalition of Northeastern Governors (CONEG), are developing compact(s) for the disposal and management of low-level radioactive waste (LLRW) generated in the eleven northeastern states (Connecticut, Delaware, Maine, Maryland, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island, and Vermont). The Technical Subcommittee has made a projection of future low-level radioactive waste to the year 2000 based on existing waste volume data and anticipated growth in the Northeast states. Aware of the difficulties involved with any long range projection - unforeseen events can drastically change projections based on current assumptions - the Technical Subcommittee believes that waste volume projections should be reviewed annually as updated information becomes available. The Technical Subcommittee made the following findings based upon a conservative projection methodology: volumes of low-level waste produced annually in the eleven states individually and collectively are expected to grow continually through the year 2000 with the rate of increase varying by state; by the year 2000, the Northeast is projected to generate 58,000 m3 of low-level waste annually, about 1.9 times the current average; and based on current estimates, 47% of the total projected waste volume in the year 2000 will be produced by nuclear power plants, compared to the current average of 54%. Non-reactor wastes will equal 53% of the total in the year 2000 compared to the current 46%

  6. Analysis through indicators of the management of radioactive waste in a radioactive facility; Analisis por medio de indicadores de la gestion de desechos radiactivos en una instalacion radiactiva

    Energy Technology Data Exchange (ETDEWEB)

    Amador Balbona, Zayda; Argudin Bocourt, William, E-mail: zabalbona@centis.edu.cu [Centro de Isotopos (CENTIS), Mayabeque (Cuba)

    2013-07-01

    The evaluation of the management of radioactive waste in the center of isotopes of the Republic of Cuba is the objective of this work. To do so, all the operations of the management system are evaluated through indicators used by this radioactive facility over a decade ago. Available information is processed from 1996 until 2012. The major waste generators are identified through the indicator of annual generation of each working group by local and by worker and it were analyzed the available store radioactive inventory, the relationship between the variation of annual technological waste volume of waste and the annual total manipulated activity, the relationship generation-declassification and the percent of liquid effluents managed as waste. Indicators of unconditional clearance, as well as the of the gaseous and liquid discharges are presented. It is concluded, with all these indicators, that it is possible to determine where are the causes of the behavior in the generation of radioactive waste if it is an increase of manipulated activity int the places of work or of worker, or improper application of the procedures of collection. It is controlled not only management, but also determines in which aspects can work to achieve the objective of minimizing the formation of these wastes, to be able to reduce the production costs. National shedding environmental regulations are met and the results are acceptable)

  7. Ocean disposal of heat generating radioactive waste

    International Nuclear Information System (INIS)

    The detailed radiological assessment of any proposed operations for the disposal of heat-generating radioactive waste in deep ocean sediments would require data describing expected embedment depths and spacing of the waste. In this study a theoretical model which predicts penetrator trajectories from launch through to rest in the sediment has been produced and has been used to generate data for environmental models. The trajectory model has been used to study the effects of small imperfections and launch parameters on the motion of a reference penetrator through water and sediment. The model predicts that the horizontal displacements of the penetrators' final resting places in the sediment from their launch positions at the ocean surface could be limited to less than 15m by twisting their tail fins uniformly by just one degree to induce spinning. The reference penetrator is predicted to achieve satisfactory embedment depth for all the cases considered including allowance for the effect of curved penetration paths in the seabed. However, the ability of the model to represent highly non-linear sediment penetration paths is demonstrated. Distribution histograms of seabed impact points relative to specific release points are presented. The area of seabed required is calculated. (author)

  8. Ocean disposal of heat generating radioactive waste

    International Nuclear Information System (INIS)

    This report is based on an emplacement techniques review prepared for the Department of the Environment in February 1983, which appeared as Chapter III of the Nuclear Energy Agency, Seabed Working Group's Status Report. The original document (DOE/RW/83.032) has been amended to take account of the results of field trials carried out in March 1983 and to better reflect current UK Government policy on ocean disposal of HGW. In particular Figure 7 has been redrawn using more realistic drag factors for the calculation of the terminal velocity in water. This report reviews the work conducted by the SWG member countries into the different techniques of emplacing heat generating radioactive waste into the deep ocean sediments. It covers the waste handling from the port facilities to final emplacement in the seabed and verification of the integrity of the canister isolation system. The two techniques which are currently being considered in detail are drilled emplacement and the free fall penetrator. The feasibility study work in progress for both techniques as well as the mathematical and physical modelling work for embedment depth and hole closure behind the penetrator are reviewed. (author)

  9. Device for the transport of radioactive waste

    International Nuclear Information System (INIS)

    The containers are transported purely by machine inside the loading cell of a cavern system and can be used for further overload transport after emptying and locking out of the loading cell. After unloading from the transport vehicle, the container passes through a radiation protection gate into the loading cell, where it is transported via rollers to a crane, whose rotating arm is provided with a pneumatically driven spindle screwdriver, which undoes all the screws on the container lid. After removing the lid, the electrically operated grab of a second rotating crane lifts the drum with the radioactive waste from the container and deposits them on rollers, from which they pass to a transport vessel, which transports the waste to the final storage position. The lid is then screwed back on to the empty container, the container is placed on some scales and is only transported through a window out of the loading cell if its weight agrees with the given tare weight. (HP)

  10. Chapter No.6. Radioactive waste (RAW)

    International Nuclear Information System (INIS)

    UJD SR supervises all phases of radioactive waste management at nuclear installations and final phases of institutional radioactive waste management. Total concentrates generation and minimisation trends during recent period (for NPP V1, NPP V2 Bohunice and NPP Mochovce) as well as increasing of their conditioning are presented. So nearly 8000 m3 of concentrates were stored at the end of year 2001, representing 75.5% of storage capacity at Bohunice site. Total amount of solid waste stored at VVER NPPs reached 3500 m3 at December 2001. The solid waste storage capacity of NPP V1 Bohunice is spent. NPP A1 Bohunice with a heterogeneous reactor using natural uranium, moderated by heavy water and cooled by CO2 had been in operation for 4 years. It was finally shut down in February 1977 after an accident (INES level 4). Main activities in 2001 were focused on an increasing of radwaste management safety by the waste solidification or storage improvement, especially in the case of inorganic spent fuel coolant. The total solid radwaste inventory in 2001 (including filters) represents cca 700 m3 of soft and pre-pressed not sorted waste, 700 m3 of sorted waste, more then 1 000 t of scrap and next 260 m3 of scrap in drums. The total volume of contaminated soils and concrete is more than 7200 m3. The volume of solid radwaste depends on the extent of dismantling works and following treatment, conditioning and disposal. The total volume is also increased by products of bituminization and cementation facilities in drums stored before conditioning at NPP A1 Bohunice site. The facilities focused only on treatment of radwaste from NPP A1 decommissioning are operated by the same operator as a part of this decommissioned nuclear installation. Experimental and research treatment plants are operated by VUJE. A facility for the treatment and conditioning of operational liquid radwaste from NPP Mochovce is under preparation and a start of construction is foreseen in 2004. The nuclear

  11. The Future: Innovative Technologies for Radioactive Waste Processing and Disposal

    International Nuclear Information System (INIS)

    Safe, proliferation resistant and economically efficient nuclear fuel cycles that minimize waste generation and environmental impacts are key to sustainable nuclear energy. Innovative approaches and technologies could significantly reduce the radiotoxicity, or the hazard posed by radioactive substances to humans, as well as the waste generated. Decreasing the waste volume, the heat load and the duration that the waste needs to be isolated from the biosphere will greatly simplify waste disposal concepts

  12. Application to transfer radioactive waste to the Nevada Test Site

    International Nuclear Information System (INIS)

    All waste described in this application has been, and will be, generated by LANL in support of the nuclear weapons test program at the NTS. All waste originates on the NTS. DOE Order 5820.2A states that low-level radioactive waste shall be disposed of at the site where it is generated, when practical. Since the waste is produced at the NTS, it is cost effective for LANL to dispose of the waste at the NTS

  13. BN-350 decommissioning problems of radioactive waste management

    International Nuclear Information System (INIS)

    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

  14. Assessing radioactive concentrates and waste vapor condensate in solidifying radioactive wastes by bituminization

    International Nuclear Information System (INIS)

    A brief overview is presented of chemical and radiochemical methods used in the world for the analysis of the concentrate of liquid radioactive wastes from nuclear power plants destined for bituminization. Most methods are also suitable for an analysis of the condensate of waste vapors produced in bituminization. The methods of analysis of the radioactive concentrate from the V-1 nuclear power plant in Jaslovske Bohunice and of the waste vapors condensate were developed and tested in practice. Gross gamma activity was measured using a well-type Na(Tl) scintillation detector, the content of radionuclides was determined using semiconductor Ge(Li) spectrometry. The concentration of boric acid in the concentrate was determined by titration with mannite; in the condensate, using spectrophotometry with curcumine. The content of nitrates in both the concentrate and the condensate was determined spectrophotometrically using salicylic acid, the content of nitrites was determined by spectrophotometry using sulfanilic acid and α-naphthylamine. Carbonates and chlorides were determined by titration, sodium and potassium by flame photometry. The content of organic acids was measured by gravimetry of extracted methyl esters, the content of surfactants by spectrophotometry. Infrared spectrophotometry was used in determining hydrocarbons in the waste vapor condensate. The measured value range and the measurement errors are shown for each method. (A.K.)

  15. Radioactive waste management and the nuclear renaissance

    International Nuclear Information System (INIS)

    Full text: Full text: For many years, nuclear supporters have been talking of a possible nuclear power renaissance. Today there are definite signs that this is finally beginning to happen. New plants are being built or planned in China, Japan, Korea, Finland, France and even the USA. Phase-out policies are being rethought in countries like Sweden, Belgium and Germany. Countries like Vietnam, Indonesia, the Baltic States and even Australia are choosing or debating initiating a nuclear programme. Support for these nuclear power developments may be strongly influenced by the progress of waste management programmes, especially final disposal. Conversely, the growing realisation of the potential global benefits of nuclear power may well lead to increased support, effort and funding for initiatives to ensure that all nations have access to safe and secure waste management facilities. This implies that large nuclear programmes must make progress with implementation of treatment, storage and disposal facilities for all of their radioactive wastes. For small nuclear programmes (and for countries with nuclear applications other than power generation) such facilities are also necessary. For economic and other reasons, these small programmes may not be able to implement all of the required national facilities. Multinational cooperation is needed. This can be realised by large countries providing back-end services such as reprocessing and disposal, or by small countries forming regional or international partnerships to implement shared facilities for storage and/or disposal. This paper will trace through the past decades the mutual interactions between programmes in nuclear power and in waste management. The relevant issues of concern for both include radiological safety, environmental impacts and, most topically, non-proliferation and security. Debates on these issues have strongly affected national efforts to implement power plants and repositories, and also influenced the

  16. Low-level radioactive waste regulation: Science, politics and fear

    International Nuclear Information System (INIS)

    An inevitable consequence of the use of radioactive materials is the generation of radioactive wastes and the public policy debate over how they will be managed. In 1980, Congress shifted responsibility for the disposal of low-level radioactive wastes from the federal government to the states. This act represented a sharp departure from more than 30 years of virtually absolute federal control over radioactive materials. Though this plan had the enthusiastic support of the states in 1980, it now appears to have been at best a chimera. Radioactive waste management has become an increasingly complicated and controversial issue for society in recent years. This book discusses only low-level wastes, however, because Congress decided for political reasons to treat them differently than high-level wastes. The book is based in part on three symposia sponsored by the division of Chemistry and the Law of the American Chemical Society. Each chapter is derived in full or in part from presentations made at these meetings, and includes: (1) Low-level radioactive wastes in the nuclear power industry; (2) Low-level radiation cancer risk assessment and government regulation to protect public health; and (3) Low-level radioactive waste: can new disposal sites be found

  17. Preparation and leaching of radioactive INEL waste forms

    International Nuclear Information System (INIS)

    Appreciable quantities of radioactive waste are in storage at the Idaho National Engineering Laboratory (INEL). Plans are being made to convert this waste into durable solid forms for final disposal in a geological repository. Part of the inventory consists of low- and intermediate-level fission, activation, and decay products and transuranic (TRU) wastes, either stored retrievably or buried at the INEL Radioactive Waste Management area. One of the TRU wastes is a sludge from the Department of Energy Rocky Flats Plant, currently stored retrievably in 55-gallon drums. Immobilizing the TRU sludge is the primary concern of the work reported here

  18. The role of performance assessment in radioactive waste disposal

    International Nuclear Information System (INIS)

    Performance assessment has many applications in the field of radioactive waste management, none more important than demonstrating the suitability of a particular repository system for waste disposal. The role of performance assessment in radioactive waste disposal is discussed with reference to assessments performed in civilian waste management programmes. The process is, however, relevant, and may be applied directly to the disposal of defence-related wastes. When used in an open and transparent manner, performance assessment is a powerful methodology not only for convincing the authorities of the safety of a disposal concept, but also for gaining the wider acceptance of the general public for repository siting. 26 refs

  19. Removal of organics from radioactive waste. V. 2

    International Nuclear Information System (INIS)

    This report reviews the available literature concerning the removal of organic substances from radioactive waste streams. A substantial portion of low level wastes generated in the various parts of the nuclear fuel cycle, nuclear laboratories and other places where radionuclides are used for research, industrial medical and defense related activities is organic (paper, wood, plastics, rubber etc.) and combustible. These combustible wastes can be processed by incineration. Incineration converts combustible wastes into radioactive ashes and residues that are non-flammable, chemically inert and more homogenous than the initial waste. (author)

  20. Programs of recovery of radioactive wastes from the trenches and land decontamination of the radioactive waste storage center

    International Nuclear Information System (INIS)

    In this report there are the decontamination program of the land of the Radioactive Waste Storage Center, the Program of Recovery of the radioactive waste of the trenches, the recovery of polluted bar with cobalt 60, the recovery of minerals and tailings of uranium and of earth with minerals and tailings of uranium, the recovery of worn out sealed sources and the waste recovery with the accustomed corresponding actions are presented. (Author)

  1. Determination of toxic organic constituents in radioactive waste

    International Nuclear Information System (INIS)

    With regard to the commissioning of the Konrad repository for radioactive waste with negligible heat development and with regard to the legal prohibition of storage of mixed wastes, there is a great interest in a technique allowing toxic organic waste to be detected in radioactive wastes in solidified cement. No real radioactive wastes were used for the examinations but model substances which also were solidified with cement. A part of these specimens was irradiated by a 4.2x105 Gy gamma dose in order to examine the influence of the radioactive radiation. The specimens were comminuted after hardening. In the irradiated specimens, the headspace of the containers was examined by means of gas chromatography-thermal conductivity detector before the containers were opened in order to remove the specimens for comminuting. The organic substances were isolated from the cement by extraction or steam distillation extraction. The extracts obtained were examined by means of gas chromatography-mass spectrometry. (orig./EF)

  2. About the Application of 'D' Values to Radioactive Waste

    International Nuclear Information System (INIS)

    A system for categorizing radioactive sources and quantities of radioactive materials aimed at specifying generic security levels has been developed during the last years. The minimum activity of a given radionuclide that is considered 'dangerous' (i.e. the 'D value' of such radionuclide) is derived from a set of well-defined scenarios, but the low activity concentration of radioactive waste, particularly of very low level waste (VLLW), low level waste (LLW) and intermediate level waste (ILW), makes inappropriate the direct application of the D Values. Taking into account the quantitative definition of a 'dangerous source' and the role of the activity concentration, a quantitative approach for the determination of the level of security applicable to the case of radioactive waste is proposed. (authors)

  3. Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility

    Energy Technology Data Exchange (ETDEWEB)

    Gates, R.; Glukhov, A.; Markowski, F.

    1996-06-01

    This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quantity and total activity of radioactive waste in the 30-km Zone and the Sarcophagus from the Chernobyl accident. Processing options are described that may ultimately be used in the long-term disposal of selected 30-km Zone and Sarcophagus wastes. A detailed report on the issues concerning the construction of a Ukrainian Central Radioactive Waste Processing Facility (CRWPF) from the Ukrainian Scientific Research and Design institute for Industrial Technology was obtained and incorporated into this report. This report outlines various processing options, their associated costs and construction schedules, which can be applied to solving the operating and decommissioning radioactive waste management problems in Ukraine. The costs and schedules are best estimates based upon the most current US industry practice and vendor information. This report focuses primarily on the handling and processing of what is defined in the US as low-level radioactive wastes.

  4. Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility

    International Nuclear Information System (INIS)

    This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quantity and total activity of radioactive waste in the 30-km Zone and the Sarcophagus from the Chernobyl accident. Processing options are described that may ultimately be used in the long-term disposal of selected 30-km Zone and Sarcophagus wastes. A detailed report on the issues concerning the construction of a Ukrainian Central Radioactive Waste Processing Facility (CRWPF) from the Ukrainian Scientific Research and Design institute for Industrial Technology was obtained and incorporated into this report. This report outlines various processing options, their associated costs and construction schedules, which can be applied to solving the operating and decommissioning radioactive waste management problems in Ukraine. The costs and schedules are best estimates based upon the most current US industry practice and vendor information. This report focuses primarily on the handling and processing of what is defined in the US as low-level radioactive wastes

  5. Can the same principles be used for the management of radioactive and non-radioactive waste?

    International Nuclear Information System (INIS)

    Non-radioactive waste has a much more complex composition than radioactive waste and appears in much larger quantities. The two types of waste have, however, some properties in common when it comes to their longterm impact on health and the environment. The occurrence in both of substances that may exist for generations and may cause cancer provides one example. Both types of waste also always occur together. It is therefore proposed that the same basic principles could be applied for the management of radioactive and non-radioactive waste. By doing so one may increase the efficiency of policy development, research and practical management. This is particurlarly importand for the very costly restoration of old disposal sites which have earlier been poorly managed. (author)

  6. Assessment of public perception of radioactive waste management in Korea.

    Energy Technology Data Exchange (ETDEWEB)

    Trone, Janis R.; Cho, SeongKyung (Myongji University, Korea); Whang, Jooho (Kyung Hee University, Korea); Lee, Moo Yul

    2011-11-01

    The essential characteristics of the issue of radioactive waste management can be conceptualized as complex, with a variety of facets and uncertainty. These characteristics tend to cause people to perceive the issue of radioactive waste management as a 'risk'. This study was initiated in response to a desire to understand the perceptions of risk that the Korean public holds towards radioactive waste and the relevant policies and policy-making processes. The study further attempts to identify the factors influencing risk perceptions and the relationships between risk perception and social acceptance.

  7. Design and operation of evaporators for radioactive wastes

    International Nuclear Information System (INIS)

    A manual dealing with the application of evaporators to the treatment of liquid radioactive wastes. This book is the second of three commissioned by the IAEA on the three on the three principal techniques for concentrating radioactive wastes, namely chemical precipitation, evaporation and ion-exchange. Informations on different types of evaporators and related equipment and their operational procedures are given in this document. It also gives different means of disposal of evaporator condensates and concentrates and a rough estimate of costs of radioactive waste evaporator plant and its operation. 58 refs, 43 figs, 5 tabs

  8. Policies and Strategies for Radioactive Waste Management (Russian Edition)

    International Nuclear Information System (INIS)

    To assure the safe, technically optimal and cost effective management of spent fuel and radioactive waste, appropriate policies and strategies are required. This publication clarifies the differences between a policy and a strategy, and provides principal advice to Member States on the typical composition, mutual links and the process of compilation of such documents. It also offers options for and indicates approaches to the management of spent fuel and radioactive waste, thus enabling an effective spent fuel and radioactive waste management infrastructure to be developed.

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

    International Nuclear Information System (INIS)

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

  10. Observations and impressions on the nature of radioactive waste management problems

    International Nuclear Information System (INIS)

    The observations and impressions of the NRC Task Group on the goals of radioactive waste management fall into five basic categories: (1) Perceptions of the waste management problem; (2) hazards of radioactive wastes; (3) methodology for assessing radioactive waste management; (4) decision processes in waste management; and (5) problems of implementing a waste management system. Each category is discussed

  11. USDOE activities in low-level radioactive waste treatment

    International Nuclear Information System (INIS)

    This paper describes current research, development and demonstration (R, D and D) programs sponsored by the US Department of Energy in the area of low-level radioactive waste treatment. The US Department of Energy Low-Level Radioactive Waste Management Program is directed toward a coordinated program covering the period from low-level radioactive waste generation through the decommissioning of the disposal site. This paper addresses the treatment portion of the program. The development efforts include: mechanical methods for metal and compactible waste volume reduction; incineration of trash or other combustibles through the use of controlled air, cyclone, or molten glass furnaces; ultrafiltration, reverse osmosis, biological or chemical destruction of nitrates; adsorption treatment of low-concentration aqueous waste streams; combustion of organic liquids; and smelting of metal wastes to reduce their volume and conserve our natural resources. (author)

  12. Low-level radioactive waste disposal in the United States

    International Nuclear Information System (INIS)

    Two national systems comprise the low-level radioactive waste management system in the United States of America. The U.S. Nuclear Regulatory Commission regulates low-level radioactive waste produced in the public sector (commercial waste), and the U.S. Department of Energy manages low-level radioactive waste produced by government-sponsored programs. The primary distinction between the two national systems is the source of regulatory control. This paper discusses two issues critical to the success of each system: the site selection process used by the commercial low-level waste disposal system, and the evaluation process used to determine configuration of the DOE waste management system. The two national systems take different approaches to reach the same goals, which are increased social responsibility, protection of public health and safety, and protection of the environment

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

    International Nuclear Information System (INIS)

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

  14. Defense Waste Processing Facility Radioactive Operations - Year Two

    Energy Technology Data Exchange (ETDEWEB)

    Occhipinti, J.E.; Carter, J.T.; Edwards, R.E.; Beck, R.S.; Iverson, D.C.

    1998-03-01

    The Savannah River Site`s Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation`s first high-level radioactive waste vitrification facility. This waste (130 million liters) which has been stored in carbon steel underground tanks and is now being pretreated, melted into a highly durable borosilicate glass and poured into stainless steel canisters for eventual disposal in a geologic repository. Following a ten-year construction period and nearly three-year nonradioactive test program, the DWPF began radioactive operations in March 1996. The first nine months of radioactive operations have been reported previously. As with any complex technical facility, difficulties were encountered during the transition to radioactive operations. Results of the second year of radioactive operations are presented in this paper. The discussion includes: feed preparation and glass melting, resolution of the melter pouring issues, improvements in processing attainment and throughput, and planned improvements in laboratory attainment and throughput.

  15. Spent fuel and radioactive waste inventories, projections, and characteristics

    International Nuclear Information System (INIS)

    Current inventories and characteristics of commercial spent fuels and both commercial and US Department of Energy (DOE) radioactive wastes were compiled through December 31, 1983, based on the most reliable information available from government sources and the open literature, technical reports, and direct contacts. Future waste and spent fuel to be generated over the next 37 years and characteristics of these materials are also presented, consistent with the latest DOE/Energy Information Administration (EIA) or projection of US commercial nuclear power growth and expected defense-related and private industrial and institutional activities. Materials considered, on a chapter-by-chapter basis, are: spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, airborne waste, 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. 48 figures, 107 tables

  16. Annual report of waste generation and pollution prevention progress 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-09-01

    This seventh Annual Report presents and analyzes DOE Complex-wide waste generation and pollution prevention activities at 45 reporting sites from 1993 through 1998. This section summarizes Calendar Year 1998 Complex-wide waste generation and pollution prevention accomplishments. More detailed information follows this section in the body of the Report. In May 1996, the Secretary of Energy established a 50 percent Complex-Wide Waste Reduction Goal (relative to the 1993 baseline) for routine operations radioactive, mixed, and hazardous waste generation, to be achieved by December31, 1999. DOE has achieved its Complex-Wide Waste Reduction Goals for routine operations based upon a comparison of 1998 waste generation to the 1993 baseline. Excluding sanitary waste, routine operations waste generation decreased 67 percent overall from 1993 to 1998. However, for the first time since 1994, the total amount of materials recycled by the Complex decreased from 109,600 metric tons in 1997 to 92,800 metric tons in 1998. This decrease is attributed to the fact that in 1997, several large ''one-time only'' recycling projects were conducted throughout the Complex. In order to demonstrate commitment to DOE's Complex-wide recycling goal, it is important for sites to identify all potential large-scale recycling/reuse opportunities.

  17. Geological disposal of heat generating radioactive waste

    International Nuclear Information System (INIS)

    A study has been made of the requirements and design features for containers to isolate vitrified heat generating radioactive waste from the environment for a period of 500 to 1000 years. The requirements for handling, storing and transporting containers have been identified following a study of disposal operations, and the pressures and temperatures which may possibly be experienced in clay, granite and salt formations have been estimated. A range of possible container designs have been proposed to satisfy the requirements of each of the disposal environments. Alternative design concepts in corrosion resistant or corrosion allowance material have been suggested. Potentially suitable container shell materials have been selected following a review of corrosion studies and although metals have not been specified in detail, titanium alloys and low carbon steels are thought to be appropriate for corrosion resistant and corrosion allowance designs respectively. Performance requirements for container filler materials have been identified and candidate materials assessed. A preliminary container stress analysis has shown the importance of thermal modelling and that if lead is used as a filler it dominates the stress response of the container. Possible methods of manufacturing disposal containers have been assessed and found to be generally feasible. (author)

  18. Packaging and transport of low and intermediate level radioactive waste

    International Nuclear Information System (INIS)

    The paper presents an overview of Nirex proposals for the packaging and transport of low and intermediate-level radioactive waste, as well as the regulatory requirements which must be met in such operations. (author)

  19. Legal framework of radioactive waste management in Indonesia

    International Nuclear Information System (INIS)

    The nuclear programme and the related legal framework in Indonesia is outlined. The provisions and principles concerning the management of radioactive waste are described. Furthermore, aspects of liability for nuclear damage and public involvement are addressed. (author)

  20. Technical career opportunities in high-level radioactive waste management

    International Nuclear Information System (INIS)

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

  1. Radioactive Waste Management in Non-Nuclear Countries - 13070

    Energy Technology Data Exchange (ETDEWEB)

    Kubelka, Dragan; Trifunovic, Dejan [SORNS, Frankopanska 11, HR-10000 Zagreb (Croatia)

    2013-07-01

    This paper challenges internationally accepted concepts of dissemination of responsibilities between all stakeholders involved in national radioactive waste management infrastructure in the countries without nuclear power program. Mainly it concerns countries classified as class A and potentially B countries according to International Atomic Energy Agency. It will be shown that in such countries long term sustainability of national radioactive waste management infrastructure is very sensitive issue that can be addressed by involving regulatory body in more active way in the infrastructure. In that way countries can mitigate possible consequences on the very sensitive open market of radioactive waste management services, comprised mainly of radioactive waste generators, operators of end-life management facilities and regulatory body. (authors)

  2. Public service of radioactive waste management for small producers

    International Nuclear Information System (INIS)

    By Governmental decree of May 1999, the Agency for radwaste management (ARAO) was authorized as a state public service for managing radioactive waste from small producers. By this decree the ARAO also became the operator of the Central Interim Storage intended for radioactive waste from industry, medicine and research, located in Brinje near Ljubljana. In this paper the current situation will be presented, together with plans for improving public service and the necessary refurbishment and modernization of the storage facility. Execution of the proposed measures, modifications and a modernization will ensure proper and safe storing of all radioactive waste from small producers produced in Slovenia, thus fulfilling the requirements for full operation of the public service of radioactive waste management.(author)

  3. Redesign and modernization of radioactive waste administration systems in Ukraine

    Energy Technology Data Exchange (ETDEWEB)

    Nieder-Westermann, Gerald H.; Walther, Thorsten; Krone, Juergen [DBE Technology GmbH, Peine (Germany)

    2016-06-15

    The European Commission (EC) has undertaken a series of projects to render assistance to Ukraine in modernizing and redesigning the Ukrainian approach to the administration, management and ultimately disposal of all forms of radioactive waste, including waste associated with the Chornobyl accident as well as waste generated as part of the Ukrainian energy infrastructure and from industrial and medical applications. One of the most recently completed projects focused on modernizing Ukraine's management and administrative systems responsible for the disposal of radioactive waste.

  4. Radioactive waste and nuclear power: a personal perspective

    International Nuclear Information System (INIS)

    An overview is given of all major sources of radioactive materials in this country, including spent fuel, high-level waste, TRU waste, low-level waste, mill tailings, remedial action programs, decontamination and decommissioning, and airborne waste. These materials are characterized in terms of location, volume, age, radioactivity, thermal power, physical properties, and chemical properties. The role of nuclear power in an oxidized and oxidizing world is discussed in terms of environmental benefits and the conservation of our limited supply of chemically reduced matter; i.e., material that can be oxidized or burned

  5. Glasses and ceramics for immobilisation of radioactive wastes for disposal

    International Nuclear Information System (INIS)

    The U.K. Research Programme on Radioactive Waste Management includes the development of processes for the conversion of high level liquid reprocessing wastes from thermal and fast reactors to borosilicate glasses. The properties of these glasses and their behaviour under storage and disposal conditions have been examined. Methods for immobilising activity from other wastes by conversion to glass or ceramic forms is described. The U.K. philosophy of final solutions to waste management and disposal is presented. (author)

  6. Development of characterization protocol for mixed liquid radioactive waste classification

    Energy Technology Data Exchange (ETDEWEB)

    Zakaria, Norasalwa, E-mail: norasalwa@nuclearmalaysia.gov.my [Waste Technology Development Centre, Malaysian Nuclear Agency, 43000 Kajang, Selangor (Malaysia); Wafa, Syed Asraf [Radioisotop Technology and Innovation, Malaysian Nuclear Agency, 43000 Kajang, Selangor (Malaysia); Wo, Yii Mei [Radiochemistry and Environment, Malaysian Nuclear Agency, 43000 Kajang, Selangor (Malaysia); Mahat, Sarimah [Material Technology Group, Malaysian Nuclear Agency, 43000 Kajang, Selangor (Malaysia)

    2015-04-29

    Mixed liquid organic waste generated from health-care and research activities containing tritium, carbon-14, and other radionuclides posed specific challenges in its management. Often, these wastes become legacy waste in many nuclear facilities and being considered as ‘problematic’ waste. One of the most important recommendations made by IAEA is to perform multistage processes aiming at declassification of the waste. At this moment, approximately 3000 bottles of mixed liquid waste, with estimated volume of 6000 litres are currently stored at the National Radioactive Waste Management Centre, Malaysia and some have been stored for more than 25 years. The aim of this study is to develop a characterization protocol towards reclassification of these wastes. The characterization protocol entails waste identification, waste screening and segregation, and analytical radionuclides profiling using various analytical procedures including gross alpha/ gross beta, gamma spectrometry, and LSC method. The results obtained from the characterization protocol are used to establish criteria for speedy classification of the waste.

  7. State-of-the-art report on low-level radioactive waste treatment

    International Nuclear Information System (INIS)

    An attempt is made to identify the main sources of low-level radioactive wastes that are generated in the United States. To place the waste problem in perspective, rough estimates are given of the annual amounts of each generic type of waste that is generated. Most of the wet solid wastes arise from the cleanup of gaseous and liquid radioactive streams prior to discharge or recycle. The treatment of the process streams and the secondary wet solid wastes thus generated is described for each type of government or fuel cycle installation. Similarly, the institutional wet wastes are also described. The dry wastes from all sources have smilar physical and chemical characteristics in that they can be classified as compactible, noncompactible, combustible, noncombustible, or combinations thereof. The various treatment options for concentrated or solid wet wastes and for dry wastes are discussed. Among the dry-waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting, and shredding. Organic materials can usually be incinerated or, in some cases, biodegraded. The filter sludges, spent resins, incinerator ashes, and concentrated liquids are usually solidified in cement, urea-formaldehyde, or unsaturated polyester resins prior to burial. Asphalt has not yet been used as a solidificaton agent in the United States, but it probably will be used in the near future. The treatment of radioactive medical and bioresearch wastes is described, but the waste from radiochenmical, pharmaceutical, and other industries is not well defined at the present time. Recovery of waste metals and treatment of hazardous contaminated wastes are discussed briefly. Some areas appearing to need more research, development, and demonstration are specifically pointed out

  8. State-of-the-art report on low-level radioactive waste treatment

    Energy Technology Data Exchange (ETDEWEB)

    Kibbey, A.H.; Godbee, H.W.

    1980-09-01

    An attempt is made to identify the main sources of low-level radioactive wastes that are generated in the United States. To place the waste problem in perspective, rough estimates are given of the annual amounts of each generic type of waste that is generated. Most of the wet solid wastes arise from the cleanup of gaseous and liquid radioactive streams prior to discharge or recycle. The treatment of the process streams and the secondary wet solid wastes thus generated is described for each type of government or fuel cycle installation. Similarly, the institutional wet wastes are also described. The dry wastes from all sources have smilar physical and chemical characteristics in that they can be classified as compactible, noncompactible, combustible, noncombustible, or combinations thereof. The various treatment options for concentrated or solid wet wastes and for dry wastes are discussed. Among the dry-waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting, and shredding. Organic materials can usually be incinerated or, in some cases, biodegraded. The filter sludges, spent resins, incinerator ashes, and concentrated liquids are usually solidified in cement, urea-formaldehyde, or unsaturated polyester resins prior to burial. Asphalt has not yet been used as a solidificaton agent in the United States, but it probably will be used in the near future. The treatment of radioactive medical and bioresearch wastes is described, but the waste from radiochenmical, pharmaceutical, and other industries is not well defined at the present time. Recovery of waste metals and treatment of hazardous contaminated wastes are discussed briefly. Some areas appearing to need more research, development, and demonstration are specifically pointed out.

  9. Summary report on the 1985 United Kingdom radioactive waste inventory

    International Nuclear Information System (INIS)

    Stocks of radioactive waste in the United Kingdom which have arisen, or are projected to arise, from commercial nuclear power reactors and fuel cycle facilities, research, medical and industrial uses of radioactive nuclides are given in the form of summary tables. Projected future arisings from operation and decommissioning of facilities and notional nuclear power generation programmes to 2030 are also given. (author)

  10. Incineration facilities for treatment of radioactive wastes: a review

    Energy Technology Data Exchange (ETDEWEB)

    Perkins, B.L.

    1976-02-01

    A description is given of incinerator installations in the US and in foreign countries. Included are descriptions of inactive incinerators, incinerator facilities currently in operation, and incinerator installations under construction. Special features of each installation and operational problems of each facility are emphasized. Problems in the incineration of radioactive waste are discussed in relation to the composition of the waste and the amount and type of radioactive contaminant.

  11. Safety in long term radioactive waste management : insight and oversight

    OpenAIRE

    Schröder, Jantine; Rossignol, Nicolas; Van Oudheusden, Michiel

    2016-01-01

    Abstract: High-level, long-lived radioactive waste remains hazardous for periods that go well beyond our human conception of time (many thousands of years). Because active safety measures are considered unreliable, unjustifiable and simply impossible over such long time spans, experts worldwide recommend geological disposal as the preferred strategy for long-term radioactive waste management, to a large extent due to its promise of delivering 'passive safety'. Passive safety refers to the rep...

  12. Radioactive waste management: a summary of state laws and administration. National Low-Level Radioactive Waste Management Program. Revision 6

    International Nuclear Information System (INIS)

    This is the sixth update of ''Radioactive Waste Management: A Summary of State Laws and Administration.'' It completely replaces the fifth update (15 September 1984). The updated report covers low-level radioactive waste compacts, and the administration, the legislature and the laws related to radioactive waste management in each of the fifty states. The report is organized by low-level waste compact regions. Each section begins with a description of the low-level waste compact, followed by reports on each state within the region. There are also sections for states which have made plans to dispose of waste independently of a compact, and for those states which have not yet declared their intentions. The report on each compact is divided into four sections: Cover Page, Chair Organization, State Delegations, and Compact

  13. An overview of radioactive waste disposal procedures of a nuclear medicine department.

    Science.gov (United States)

    Ravichandran, R; Binukumar, J P; Sreeram, Rajan; Arunkumar, L S

    2011-04-01

    Radioactive wastes from hospitals form one of the various types of urban wastes, which are managed in developed countries in a safe and organized way. In countries where growth of nuclear medicine services are envisaged, implementations of existing regulatory policies and guidelines in hospitals in terms of handling of radioactive materials used in the treatment of patients need a good model. To address this issue, a brief description of the methods is presented. A designed prototype waste storage trolley is found to be of great help in decaying the I-131 solid wastes from wards before releasing to waste treatment plant of the city. Two delay tanks with collection time of about 2 months and delay time of 2 months alternately result in 6 releases of urine toilet effluents to the sewage treatment plant (STP) of the hospital annually. Samples of effluents collected at releasing time documented radioactive releases of I-131 much below recommended levels of bi-monthly release. External counting of samples showed good statistical correlation with calculated values. An overview of safe procedures for radioactive waste disposal is presented. PMID:21731225

  14. An overview of radioactive waste disposal procedures of a nuclear medicine department

    Directory of Open Access Journals (Sweden)

    R Ravichandran

    2011-01-01

    Full Text Available Radioactive wastes from hospitals form one of the various types of urban wastes, which are managed in developed countries in a safe and organized way. In countries where growth of nuclear medicine services are envisaged, implementations of existing regulatory policies and guidelines in hospitals in terms of handling of radioactive materials used in the treatment of patients need a good model. To address this issue, a brief description of the methods is presented. A designed prototype waste storage trolley is found to be of great help in decaying the I-131 solid wastes from wards before releasing to waste treatment plant of the city. Two delay tanks with collection time of about 2 months and delay time of 2 months alternately result in 6 releases of urine toilet effluents to the sewage treatment plant (STP of the hospital annually. Samples of effluents collected at releasing time documented radioactive releases of I-131 much below recommended levels of bi-monthly release. External counting of samples showed good statistical correlation with calculated values. An overview of safe procedures for radioactive waste disposal is presented.

  15. An overview of radioactive waste disposal procedures of a nuclear medicine department.

    Science.gov (United States)

    Ravichandran, R; Binukumar, J P; Sreeram, Rajan; Arunkumar, L S

    2011-04-01

    Radioactive wastes from hospitals form one of the various types of urban wastes, which are managed in developed countries in a safe and organized way. In countries where growth of nuclear medicine services are envisaged, implementations of existing regulatory policies and guidelines in hospitals in terms of handling of radioactive materials used in the treatment of patients need a good model. To address this issue, a brief description of the methods is presented. A designed prototype waste storage trolley is found to be of great help in decaying the I-131 solid wastes from wards before releasing to waste treatment plant of the city. Two delay tanks with collection time of about 2 months and delay time of 2 months alternately result in 6 releases of urine toilet effluents to the sewage treatment plant (STP) of the hospital annually. Samples of effluents collected at releasing time documented radioactive releases of I-131 much below recommended levels of bi-monthly release. External counting of samples showed good statistical correlation with calculated values. An overview of safe procedures for radioactive waste disposal is presented.

  16. Management of nontritium radioactive wastes from fusion power plants

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-09-01

    This report identifies nontritium radioactive waste sources for current conceptual fusion reactor designs. Quantities and compositions of the radwaste are estimated for the tokamaks of the University of Wisconsin (UWMAK-I), the Princeton Plasma Physics Laboratory (PPPL), and the Oak Ridge National Laboratory (ORNL); the Reference Theta Pinch Reactor of the Los Alamos Scientific Laboratory (LASL); and the Minimum Activation Blanket of the Brookhaven National Laboratory (BNL). Disposal of large amounts of radioactive waste appears necessary for fusion reactors. Although the curie (Ci) level of the wastes is comparable to that of fission products in fission reactors, the isotopes are less hazardous, and have shorter half-lives. Therefore radioactivity from fusion power production should pose a smaller risk than radioactivity from fission reactors. Radioactive waste sources identified for the five reference plants are summarized. Specific radwaste treatments or systems had to be assumed to estimate these waste quantities. Future fusion power plant conceptual designs should include radwaste treatment system designs so that assumed designs do not have to be used to assess the environmental effects of the radioactive waste.

  17. Radioactive Liquid Waste Treatment Facility: Environmental Information Document

    Energy Technology Data Exchange (ETDEWEB)

    Haagenstad, H.T.; Gonzales, G.; Suazo, I.L. [Los Alamos National Lab., NM (United States)

    1993-11-01

    At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R&D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R&D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action.

  18. Radioactive Liquid Waste Treatment Facility: Environmental Information Document

    International Nuclear Information System (INIS)

    At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R ampersand D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R ampersand D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action

  19. Treatment and storage of radioactive wastes at Institute for Energy Technology, Kjeller, Norway and a short survey of non-radioactive hazardous wastes in Norway

    International Nuclear Information System (INIS)

    The treatment and storage of low-level and intermediate-level radioactive wastes in Norway is described. A survey of non-radioactive hazardous wastes and planned processing methods for their treatment in Norway is given. It seems that processing methods developed for radioactive wastes to a greater extent could be adopted to hazardous wastes, and that an increased interdisciplinary waste cooperation could be a positive contribution to the solution of the hazardous waste problems

  20. Radioactive waste management of the nuclear medicine services

    International Nuclear Information System (INIS)

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

  1. Present status of research and development of radioactive waste treatment (1). Present status of concept, business, research and development of radioactive waste treatment in Japan

    International Nuclear Information System (INIS)

    The concept of radioactive waste treatment and research and development for its commercialization in Japan is explained. The relation between the kinds of radioactive wastes and production sites, the treatment methods depending on the kind and level of radioactive waste, low level radioactive waste treatment method, the basic concept, selection of sites, and barrier functions of high level radioactive waste facility are stated. Outline of fundamental technology development system of radioactive treatment in Japan, development of investigation and evaluation technology of site properties, design and execution of treatment facility, and the future treatment technologies are stated. (S.Y.)

  2. Projection to 2035 for the radioactive wastes of low and intermediate level in Mexico

    International Nuclear Information System (INIS)

    It is necessary to establish in few years a definitive warehouse for the radioactive waste of low and intermediate level, generated in the country and to satisfy the necessities of their confinement in the next ones 50 to 80 years. Therefore, it is required to be considered those volumes produced annually, those stored at the present and those estimated to medium and long term. The results of the simulation of 4 cases are presented, considering the operation from the 2 nuclear power reactors to 40 and 60 years, the use of the technology of current treatment and the use of super compaction of solids, as well as the importance in the taking of decision of the methodology for the dismantlement of each reactor to the finish of their useful life. At the moment the Nuclear Power Plant of Laguna Verde, produces an average of 250 m3/year of radioactive waste of low and intermediate level, constituted by solid dry wastes, humid solids and liquids. In the last 3 years, the power plant has reached an effectiveness of re utilization of effluents of 95%. On the other hand, in Mexico the non energetic applications of the radioisotopes, produce annually of the order of 20 m3/year of solid wastes, 280 m3/year of liquid wastes and 300 worn out radioactive sources. (Author)

  3. New York State low-level radioactive waste status report for 1998

    International Nuclear Information System (INIS)

    This report summarizes data on low-level radioactive waste (LLRW) generated in New York State: it is based on reports from generators that must be filed annually with the New York State Energy Research and Development Authority (NYSERDA) and on data from the US Department of Energy (US DOE). The New York State Low-Level Radioactive Waste Management Act (State Act) requires LLRW generators in the State to submit annual reports detailing the classes and quantities of waste generated. This is the 13th year generators have been required to submit these reports to NYSERDA. The data are summarized in a series of tables and figures. There are four sections in the report. Section 1 covers volume, activity, and other characteristics of waste shipped for disposal in 1998. Activity is the measure of a material's radioactivity, or the number of radiation-emitting events occurring each second. Section 2 summarizes volume, activity, and other characteristics of waste held for storage as of December 31, 1998. Section 3 shows historical LLRW generation and includes generators' projections for the next five years. Section 4 provides a list, by county, of all facilities from which 1998 LLRW reports were received. 2 figs., 23 tabs

  4. New York State Low-Level Radioactive Waste Status Report for 1992

    Energy Technology Data Exchange (ETDEWEB)

    Attridge, T.; Rapaport, S.; Yang, Qian

    1993-06-01

    This report summarizes data on low-level radioactive waste (LLRW) generation in New York State for calendar year 1992. It is based on reports from generators that must be filed annually with the New York State Energy Research and Development Authority (Energy Authority) and on data from the US Department of Energy. The New York State Low-Level Radioactive Waste Management Act (State Act) requires LLRW generators in the State to submit annual reports detailing the classes and quantities of waste generated. This is the seventh year generators have been required to submit reports on their waste to the Energy Authority. The data are summarized in a series of tables and figures. There are three sections in the report. Section 1 covers volume, radioactivity and other characteristics of waste generated in 1992. Section 2 shows historical LLRW generation over the years and includes generators` projections for the next five years. Section 3 provides a list of all facilities for which 1992 LLRW reports were received.

  5. New York State low-level radioactive waste status report for 1998

    Energy Technology Data Exchange (ETDEWEB)

    Voelk, H.

    1999-06-01

    This report summarizes data on low-level radioactive waste (LLRW) generated in New York State: it is based on reports from generators that must be filed annually with the New York State Energy Research and Development Authority (NYSERDA) and on data from the US Department of Energy (US DOE). The New York State Low-Level Radioactive Waste Management Act (State Act) requires LLRW generators in the State to submit annual reports detailing the classes and quantities of waste generated. This is the 13th year generators have been required to submit these reports to NYSERDA. The data are summarized in a series of tables and figures. There are four sections in the report. Section 1 covers volume, activity, and other characteristics of waste shipped for disposal in 1998. Activity is the measure of a material`s radioactivity, or the number of radiation-emitting events occurring each second. Section 2 summarizes volume, activity, and other characteristics of waste held for storage as of December 31, 1998. Section 3 shows historical LLRW generation and includes generators` projections for the next five years. Section 4 provides a list, by county, of all facilities from which 1998 LLRW reports were received. 2 figs., 23 tabs.

  6. Qualification test of packages for transporting radioactive materials and wastes

    International Nuclear Information System (INIS)

    Since 1979 the Waste Treatment Division of Nuclear Tecnology Development Center has been developed and tested packagings for transporting radioactive materials and wastes. The Division has designed facilities for testing Type A packages in accordance with the adopted regulations. The Division has tested several packages for universities, research centers, industries, INB, FURNAS, etc. (author)

  7. State agencies for the collection of radioactive waste

    International Nuclear Information System (INIS)

    In the Federal Republic of Germany the establishment of state agencies for the collection of radioactive wastes is embodied in Section 9a, para. 3 of the Atomic Energy Act. They concentrate on collecting radioactive wastes resulting from the application of radionuclides in industry, research, and medicine. The Atomic Energy Act expressly permits to assign the operation of the agencies to third parties. For the eleven states of the Federal Republic of Germany there exist eight waste collecting agencies. They accept the radioactive wastes according to their regulations of use. The wastes are partly collected by their collecting services and, if necessary, conditioned for ultimate storage. Until the end of 1978 the wastes were continuously transferred to the experimental ultimate storage facility Asse. Only wastes producing radioactive gases or vapors, like e.g. radium and tritium, were not accepted for storage in the pit structures for reasons of radiation protection, and therefore remained with the collecting agencies. After the license for storage in Asse expired, great difficulties have arisen. The various state collecting agencies today are offering storage capacities only for limited periods of time, generally not more than for two years in total. Moreover, the acceptance of waste being confined to the territory of the corresponding state, the state collecting agencies have to be extended with respect to storage capacity as well as processing facilities. (orig.)

  8. New materials for the containment of radioactive wastes

    International Nuclear Information System (INIS)

    Asbestos-cement is a new material that can be used in the containment or storage of radioactive waste, because it can act as intermediate storage for high activity waste dispersed in this material or else be used in the shape of definitive storage containers

  9. 'WISP' a simple radioactive waste management computer program

    International Nuclear Information System (INIS)

    The report describes the radioactive waste management program WISP. WISP was developed for rapid comparative assessment of different nuclear scenarios and fuel reprocessing strategies. It provides tables and graphs of low, intermediate and high level waste volumes from reactor operation, fuel reprocessing and station decommissioning (excluding Stage 3). (author)

  10. Future strategic directions for radioactive waste management programmes

    International Nuclear Information System (INIS)

    The NEA Radioactive Waste Management Committee (RWMC) has identified six strategic areas as priorities for work in the coming years. These strategic areas, listed in this paper, are described in a NEA publication (Strategic Areas in Waste Management: the viewpoint and work orientations of the NEA RWMC

  11. Radioactive waste management practices with KWU-boiling water reactors

    International Nuclear Information System (INIS)

    A Kraftwerk Union boiling water reactor is used to demonstrate the reactor auxiliary systems which are applied to minimize the radioactive discharge. Based on the most important design criteria the philosophy and function of the various systems for handling the off-gas, ventilation air, waste water and concentrated waste are described. (orig.)

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

    International Nuclear Information System (INIS)

    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

  13. ICPP radioactive liquid and calcine waste technologies evaluation. Interim report

    Energy Technology Data Exchange (ETDEWEB)

    Murphy, J.A.; Pincock, L.F.; Christiansen, I.N.

    1994-06-01

    The Department of Energy (DOE) has received spent nuclear fuel (SNF) at the Idaho Chemical Processing Plant (ICPP) for interim storage since 1951 and reprocessing since 1953. Until recently, the major activity of the ICPP has been the reprocessing of SNF to recover fissile uranium; however, changing world events have raised questions concerning the need to recover and recycle this material. In April 1992, DOE chose to discontinue reprocessing SNF for uranium recovery and shifted its focus toward the management and disposition of radioactive wastes accumulated through reprocessing activities. Currently, 1.8 million gallons of radioactive liquid wastes (1.5 million gallons of radioactive sodium-bearing liquid wastes and 0.3 million gallons of high-level liquid waste) and 3,800 cubic meters (m{sup 3}) of calcine waste are in inventory at the ICPP. Legal drivers and agreements exist obligating the INEL to develop, demonstrate, and implement technologies for safe and environmentally sound treatment and interim storage of radioactive liquid and calcine waste. Candidate treatment processes and waste forms are being evaluated using the Technology Evaluation and Analysis Methodology (TEAM) Model. This process allows decision makers to (1) identify optimum radioactive waste treatment and disposal form alternatives; (2) assess tradeoffs between various optimization criteria; (3) identify uncertainties in performance parameters; and (4) focus development efforts on options that best satisfy stakeholder concerns. The Systems Analysis technology evaluation presented in this document supports the DOE in selecting the most effective radioactive liquid and calcine waste management plan to implement in compliance with established regulations, court orders, and agreements.

  14. CAN WE CONSIDER WASTES GENERATED DURING RADIOIMMUNOASSAYS AS A RADIOACTIVE WASTE?

    Directory of Open Access Journals (Sweden)

    V. V. Shapilov

    2010-01-01

    Full Text Available The work presents issues of the radiation protection provision for the management of radioactive waste produced by the radioimmunological analysis with the use of 125I marker, calculated and experimental data on radioactive waste specific activities are analyzed.

  15. High level radioactive waste (HLW) disposal a global challenge

    CERN Document Server

    PUSCH, R; NAKANO, M

    2011-01-01

    High Level Radioactive Waste (HLW) Disposal, A Global Challenge presents the most recent information on proposed methods of disposal for the most dangerous radioactive waste and for assessing their function from short- and long-term perspectives. It discusses new aspects of the disposal of such waste, especially HLW.The book is unique in the literature in making it clear that, due to tectonics and long-term changes in rock structure, rock can serve only as a ""mechanical support to the chemical apparatus"" and that effective containment of hazardous elements can only be managed by properly des

  16. Proceedings of the 1983 civilian radioactive waste management information meeting

    International Nuclear Information System (INIS)

    This proceedings document from the 1983 Civilian Radioactive Waste Management Information Meeting serves to highlight developments since the passage of the Nuclear Policy Act of 1982 and reviews program activities necessary to provide for the permanent disposal and storage of commercially generated high-level radioactive waste. Presentations included in this program cover topics concerning interim spent fuel, monitored retrievable storage, geologic repository deployment as well as management of the Nuclear Waste Fund. Individual papers were abstracted for inclusion in the Energy Data Base

  17. Treatment of low-level radioactive waste using Volcanic ash

    International Nuclear Information System (INIS)

    The effective application of volcanic ash, an indigenous adsorptive material abundant in the Mt. Pinatubo area, in the removal of radioiodine from radioactive waste streams was demonstrated. Factors such as availability, low cost and comparative retention capacity with respect to activated charcoal make volcanic ash an attractive alternative in the conditioning of radioactive waste containing radioiodine. Chemical precipitation was employed in the treatment of low level aqueous waste containing 137Cs. It was shown that there exists an optimum concentration of ferric ion that promotes maximum precipitation of caesium. It was further demonstrated that complete removal of caesium can be achieved with the addition of nickel hexacyanoferrate. (author). 5 refs, 3 figs

  18. RATA to take care of Radioactive Waste Management

    International Nuclear Information System (INIS)

    After the Law of the Republic of Lithuania was passed on Radioactive Waste (RW) Management on 20 May 1999, much more attention has been given to the disposal of this kind of waste in our country and especially to the Ignalina NPP, the facility that produces most of it. The Ministry of Economy set up the Radioactive Waste Management Agency (RATA) on 20 July 2001. Its task is to take care of the final disposal of RW in the Republic of Lithuania. Structure, description of the activities and plans for future of RATA is presented

  19. Problem of the NPP liquid radioactive wastes processing and disposal

    International Nuclear Information System (INIS)

    Modern methods of NPP radioactive waste processing and disposal are briefly presented, bituminization with the following disposal in the clayey soil in particular. Soviet installations of liquid waste bituminization and results of proving ground preservation of bituminic blocks are briefly described. These results indicate a possibility of bituminic material disposal with specific activity of 1 Ci/l directly in the soil without waterproofing. High safety and effectivity of waste bituminization is shown in comparison with preservation variant of liquid radioactive concentrates in capacities

  20. Spanish high level radioactive waste management system issues

    International Nuclear Information System (INIS)

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