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Sample records for annual dangerous waste

  1. Hanford Site annual dangerous waste report: Volume 1, Part 1, Generator dangerous waste report, dangerous waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

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

  2. Hanford Site annual dangerous waste report: Volume 1, Part 1, Generator dangerous waste report, dangerous waste

    International Nuclear Information System (INIS)

    1994-01-01

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

  3. Hanford Site annual dangerous waste report: Volume 1, Part 2, Generator dangerous waste report, dangerous waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

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

  4. Hanford Site annual dangerous waste report: Volume 1, Part 2, Generator dangerous waste report, dangerous waste

    International Nuclear Information System (INIS)

    1994-01-01

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

  5. Hanford Facility Annual Dangerous Waste Report Calendar Year 2002

    International Nuclear Information System (INIS)

    FR-EEMAN, D.A.

    2003-01-01

    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

  6. HANFORD FACILITY ANNUAL DANGEROUS WASTE REPORT CY2005

    Energy Technology Data Exchange (ETDEWEB)

    SKOLRUD, J.O.

    2006-02-15

    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 RCR4 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. An electronic 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, the report is also transmitted electronically to a web site maintained by the Washington State Department of Ecology.

  7. Hanford Site annual dangerous waste report: Volume 3, Part 2, Waste Management Facility report, dangerous waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1944-12-31

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    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.

  9. Hanford Site annual dangerous waste report: Volume 3, Part 1, Waste Management Facility report, dangerous waste

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    This report contains information on hazardous 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.

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

    International Nuclear Information System (INIS)

    1994-01-01

    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

  11. Hanford Site annual dangerous waste report: Volume 3, Part 1, Waste Management Facility report, dangerous waste

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains information on hazardous 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

  12. Hanford Site annual dangerous waste report, calendar year 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    This report is a compilation of data on the disposition of hazardous wastes generated on the Hanford Reservation. This information is on EPA requirement every two years. Wastes include: tank simulant waste; alkaline batteries; lead-based paints; organic solvents; light bulbs containing lead and/or mercury; monitoring well drilling wastes; soils contaminated with trace metals, halogenated organics, or other pollutants; Ni-Cd batteries; pesticides; waste oils and greases; wastes from the cleanup of fuel/gasoline spills; filters; metals; and other.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    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.

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

    International Nuclear Information System (INIS)

    1994-01-01

    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

  15. PFP dangerous waste training plan

    International Nuclear Information System (INIS)

    Khojandi, J.

    1996-01-01

    This document establishes the minimum training requirements for the Plutonium Finishing Plant (PFP) personnel who are responsible for management of dangerous waste. The training plan outlines training requirements for handling of solid dangerous waste during generator accumulation and liquid dangerous waste during treatment and storage operations. The implementation of this training plan will ensure the PFP facility compliance with the training plan requirements of Dangerous Waste Regulation. Chapter 173-303-330. Washington Administrative Code (WAC). The requirements for such compliance is described in Section 11.0 of WHC-CM-7-5 Environmental Compliance Manual

  16. 616 Nonradioactive Dangerous Waste Storage Facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-10-01

    The 616 Nonradioactive Dangerous Waste Storage Facility Dangerous Waste Permit Application consists of both a Part A and a Part B permit application. An explanation of the Part A revisions associated with this storage unit, including the Part A included with this document, is provided at the beginning of the Part A Section. The Part B consists of 15 chapters addressing the organization and content of the Part B Checklist prepared by the Washington State Department of Ecology (Ecology 1987). For ease of reference, the checklist section numbers, in brackets, follow chapter headings and subheadings. The 616 Nonradioactive Dangerous Waste Storage Facility Dangerous Waste Permit Application (Revision 0) was submitted to the Washington State Department of Ecology and the US Environmental Protection Agency on July 31, 1989. Revision 1, addressing Washington State Department of Ecology review comments made on Revision 0 dated November 21, 1989, and March 23, 1990, was submitted on June 22, 1990. This submittal, Revision 2, addresses Washington State Department of Ecology review comments made on Revision 1, dated June 22, 1990, August 30, 1990, December 18, 1990, and July 8, 1991

  17. Hanford facility dangerous waste permit application, 616 Nonradioactive Dangerous Waste Storage Facility. Revision 2A

    International Nuclear Information System (INIS)

    Bowman, R.C.

    1994-04-01

    This permit application for the 616 Nonradioactive Dangerous Waste Storage Facility consists for 15 chapters. Topics of discussion include the following: facility description and general provisions; waste characteristics; process information; personnel training; reporting and record keeping; and certification

  18. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1988-01-01

    This section briefly describes the Hanford Site, provides a general description of the site operations and administration, provides an overview of the contents of this Grout Treatment Facility (GTF) Permit Application, and gives a list of acronyms and abbreviations used in the document. The decision was made to use the checklist as a locator reference instead of using the checklist section numbers as paragraph section numbers because several different types of waste management units, some of which are not addressed in the checklists, are part of the GTF. The GTF is a waste management unit within the Hanford Site facility. In May 1988, permit application was filed that identified the GTF as an existing facility. The GTF mixes dry cementitious solids with liquid mixed wastes (containing both dangerous and radioactive constituents) produced by Hanford Site operations. In addition to the design and operating features of the GTF that are intended to meet the requirements of dangerous waste regulations, many additional design and operating features are necessary to comply with radioactive waste management practices. The GTF design features and practices are intended to keep operational exposure to radionuclides and dangerous substances ''as low as reasonably achievable'' (ALARA) and to provide a disposal system that protects the environment for at least 10,000 yr. In some instances, ALARA practices present difficulties when complying with requirements of dangerous waste regulations

  19. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1988-01-01

    This section briefly describes the Hanford Site, provides a general description of the site operations and administration, provides an overview of the contents of this Grout Treatment Facility (GTF) Permit Application, and gives a list of acronyms and abbreviations used in the document. The decision was made to use the checklist as a locator reference instead of using the checklist section numbers as paragraph section numbers because several different types of waste management units, some of which are not addressed in the checklists, are part of the GTF. The GTF is a waste management unit within the Hanford Site facility. In May 1988, a permit application was filed that identified the GTF as an existing facility. The GTF mixes dry cementitious solids with liquid mixed wastes (containing both dangerous and radioactive constitutents) produced by Hanford Site operations. In addition to the design and operating features of the GTF that are intended to meet the requirements of dangerous waste regulations, many additional design and operating features are necessary to comply with radioactive waste management practices. The GTF design features and practices are intended to keep operational exposure to radionuclides and dangerous substances ''as low as reasonably achievable'' (ALARA) and to provide a disposal system that protects the environment for at least 10,000 yr. In some instances, ALARA practices present difficulties when complying with requirements of dangerous waste regulations. This volume contains 2 Appendices covering engineering drawings and operating procedures

  20. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1988-01-01

    This section briefly describes the Hanford Site, provides a general description of the site operations and administration, provides an overview of the contents of this Grout Treatment Facility (GTF) Permit Application, and gives a list of acronyms and abbreviations used in the document. The decision was made to use the checklist as a locator reference instead of using the checklist section numbers as paragraph section numbers because several different types of waste management units, some of which are not addressed in the checklists, are part of the GTF. The GTF is a waste management unit within the Hanford Site facility. In May 1988, a permit application was filed that identified the GTF as an existing facility. The GTF mixes dry cementitious solids with liquid mixed wastes (containing both dangerous and radioactive constituents) produced by Hanford Site operations. In addition to the design and operating features of the GTF that are intended to meet the requirements of dangerous waste regulations, many additional design and operating features are necessary to comply with radioactive waste management practices. The GTF design features and practices are intended to keep operational exposure to radionuclides and dangerous substances ''as low as reasonably achievable'' (ALARA) and to provide a disposal system that protects the environment for at least 10,000 yr. In some instances, ALARA practices present difficulties when complying with requirements of dangerous waste regulations. This volume contains 2 appendices covering engineering drawings and operating procedures

  1. PUREX Storage Tunnels dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-12-01

    This report is part of a dangerous waste permit application for the storage of wastes from the Purex process at Hanford. Appendices are presented on the following: construction drawings; HSW-5638, specifications for disposal facility for failed equipment, Project CA-1513-A; HWS-8262, specification for Purex equipment disposal, Project CGC 964; storage tunnel checklist; classification of residual tank heels in Purex storage tunnels; emergency plan for Purex facility; training course descriptions; and the Purex storage tunnels engineering study

  2. Grout Treatment Facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1992-07-01

    The Grout Treatment Facility (GTF) is an existing treatment, storage, and/or disposal (TSD) unit located in the 200 East Area and the adjacent 600 Area of the Hanford Site. The GTF mixes dry cementitious solids with liquid mixed waste (containing both dangerous and radioactive constituents) produced by Hanford Site operations. The GTF consists of the following: The 241-AP-02D and 241-AP-04D waste pump pits and transfer piping; Dry Materials Facility (DMF); Grout Disposal Facility (GDF), consisting of the disposal vault and support and monitoring equipment; and Grout Processing Facility (GPF) and Westinghouse Hanford Company on the draft Hanford Facility Dangerous Waste Permit and may not be read to conflict with those comments. The Grout Treatment Facility Dangerous Waste Permit Application consists of both a Part A and a Part B permit application. An explanation of the Part A revisions associated with this TSD unit, including the current revision, is provided at the beginning of the Part A section. The Part B consists of 15 chapters addressing the organization and content of the Part B checklist prepared by the Washington State Department of Ecology (Ecology 1987). For ease of reference, the checklist section numbers, in brackets, follow chapter headings and subheadings

  3. Hanford facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-01-01

    This document, Set 2, the Hanford Facility Dangerous Waste Part B Permit Application, consists of 15 chapters that address the content of the Part B checklists prepared by the Washington State Department of Ecology (Ecology 1987) and the US Environmental Protection Agency (40 CFR 270), with additional information requirements mandated by the Hazardous and Solid Waste Amendments of 1984 and revisions of WAC 173-303. For ease of reference, the Washington State Department of Ecology checklist section numbers, in brackets, follow the chapter headings and subheadings. This permit application contains ''umbrella- type'' documentation with overall application to the Hanford Facility. This documentation is broad in nature and applies to all TSD units that have final status under the Hanford Facility Permit

  4. Hanford facility dangerous waste permit application

    Energy Technology Data Exchange (ETDEWEB)

    None

    1991-09-18

    This document, Set 2, the Hanford Facility Dangerous Waste Part B Permit Application, consists of 15 chapters that address the content of the Part B checklists prepared by the Washington State Department of Ecology (Ecology 1987) and the US Environmental Protection Agency (40 CFR 270), with additional information requirements mandated by the Hazardous and Solid Waste Amendments of 1984 and revisions of WAC 173-303. For ease of reference, the Washington State Department of Ecology checklist section numbers, in brackets, follow the chapter headings and subheadings. This permit application contains umbrella- type'' documentation with overall application to the Hanford Facility. This documentation is broad in nature and applies to all TSD units that have final status under the Hanford Facility Permit.

  5. Hanford Waste Vitrification Plant Dangerous Waste Permit Application

    International Nuclear Information System (INIS)

    1991-10-01

    The Hanford Facility currently stores mixed waste, resulting from various processing operations, in underground storage tanks. The Hanford Waste Vitrification Plant will be constructed and operated to process the high-activity fraction of mixed waste stored in these underground tanks. The Hanford Waste Vitrification Plant will solidify pretreated tank waste into a glass product that will be packaged for disposal in a national repository. This Vitrification Plant Dangerous Waste Permit Application, Revision 2, consists of both a Part A and a Part B permit application. An explanation of the Part A revisions, including Revision 4 submitted with this application, is provided at the beginning of the Part A section. The Part B consists of 15 chapters addressing the organization and content of the Part B Checklist prepared by the Washington State Department of Ecology (Ecology 1987)

  6. Tank waste remediation system dangerous waste training plan

    International Nuclear Information System (INIS)

    POHTO, R.E.

    1999-01-01

    This document outlines the dangerous waste training program developed and implemented for all Treatment, Storage, and Disposal (TSD) Units operated by Lockheed Martin Hanford Corporation (LMHC) Tank Waste Remediation System (TWRS) in the Hanford 200 East, 200 West and 600 Areas and the <90 Day Accumulation Area at 209E. Operating TSD Units operated by TWRS are: the Double-Shell Tank (DST) System (including 204-AR Waste Transfer Building), the 600 Area Purgewater Storage and the Effluent Treatment Facility. TSD Units undergoing closure are: the Single-Shell Tank (SST) System, 207-A South Retention Basin, and the 216-B-63 Trench

  7. Liquid effluent retention facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-06-01

    This appendix to the Liquid Effluent Retention Facility Dangerous Waste Permit Application contains pumps, piping, leak detection systems, geomembranes, leachate collection systems, earthworks and floating cover systems

  8. The choice of locations for disposal of dangerous (radioactive) waste

    International Nuclear Information System (INIS)

    Hisschemoller, M.; Midden, C.J.H.; Stallen, P.J.; Rijksuniversiteit Leiden; Nederlandse Centrale Organisatie voor Toegepast Natuurwetenschappelijk Onderzoek, The Hague)

    1985-11-01

    In this report a managerial and psychological analysis, based on literature study and case analysis, is presented of various policy strategies which are or can be followed by governments in decisions about disposal of dangerous waste. Special attention is given to radioactive waste. (Auth.)

  9. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1992-07-01

    The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the low-level liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Hanford Site Maps, road evaluation for the grout treatment facility, Department of Ecology certificate of non-designation for centralia fly ash, double-shell tank waste compositional modeling, laboratory analysis reports for double-shell tank waste, stored in tanks 241-AN-103, 241-AN-106, and 241-AW-101, grout vault heat transfer results for M-106 grout formulation, test results for extraction procedure toxicity testing, test results for toxicity testing of double-shell tank grout, pilot-scale grout production test with a simulated low-level waste, characterization of simulated low-level waste grout produced in a pilot-scale test, description of the procedure for sampling nonaging waste storage tanks, description of laboratory procedures, grout campaign waste composition verification, variability in properties of grouted phosphate/sulfate N-reactor waste, engineering drawings, description of operating procedures, equipment list--transportable grout equipment, grout treatment facility--tank integrity assessment plan, long-term effects of waste solutions on concrete and reinforcing steel, vendor information, grout disposal facilities construction quality assurance plan, and flexible membrane liner/waste compatibility test results

  10. Double-shell tank system dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-06-01

    This Double-Shell Tank System Dangerous Waste Permit Application should be read in conjunction with the 242-A Evaporator Dangerous Waste Permit Application and the Liquid Effluent Retention Facility Dangerous Waste Permit Application, also submitted on June 28, 1991. Information contained in the Double-Shell Tank System permit application is referenced in the other two permit applications. The Double-Shell Tank System stores and treats mixed waste received from a variety of sources on the Hanford Site. The 242-A Evaporator treats liquid mixed waste received from the double-shell tanks. The 242-A Evaporator returns a mixed-waste slurry to the double-shell tanks and generates the dilute mixed-waste stream stored in the Liquid Effluent Retention Facility. This report contains information on the following topics: Facility Description and General Provisions; Waste Characteristics; Process Information; Groundwater Monitoring; Procedures to Prevent Hazards; Contingency Plan; Personnel Training; Exposure Information Report; Waste Minimization Plan; Closure and Postclosure Requirements; Reporting and Recordkeeping; other Relevant Laws; and Certification. 150 refs., 141 figs., 118 tabs

  11. Plutonium finishing plant dangerous waste training plan

    International Nuclear Information System (INIS)

    ENTROP, G.E.

    1999-01-01

    This training plan describes general requirements, worker categories, and provides course descriptions for operation of the Plutonium Finish Plant (PFP) waste generation facilities, permitted treatment, storage and disposal (TSD) units, and the 90-Day Accumulation Areas

  12. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1992-07-01

    The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Vault design, run-on/run-off control design, and asphalt compatibility with 90-degree celsius double-shell slurry feed

  13. Waste Encapsulation and Storage Facility (WESF) Dangerous Waste Training Plan (DWTP)

    International Nuclear Information System (INIS)

    SIMMONS, F.M.

    2000-01-01

    This Waste Encapsulation Storage Facility (WESF) Dangerous Waste Training Plan (DWTP) applies to personnel who perform work at, or in support of WESF. The plan, along with the names of personnel, may be given to a regulatory agency inspector upon request. General workers, subcontractors, or visiting personnel who have not been trained in the management of dangerous wastes must be accompanied by an individual who meets the requirements of this training plan. Dangerous waste management includes handling, treatment, storage, and/or disposal of dangerous and/or mixed waste. Dangerous waste management units covered by this plan include: less-than-90-day accumulation area(s); pool cells 1-8 and 12 storage units; and process cells A-G storage units. This training plan describes general requirements, worker categories, and provides course descriptions for operation of the WESF permitted miscellaneous storage units and the Less-than-90-Day Accumulation Areas

  14. Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-07-01

    This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization.

  15. Hanford facility dangerous waste permit application, 325 hazardous waste treatment units. Revision 1

    International Nuclear Information System (INIS)

    1997-07-01

    This report contains the Hanford Facility Dangerous Waste Permit Application for the 325 Hazardous Waste Treatment Units (325 HWTUs) which consist of the Shielded Analytical Laboratory, the 325 Building, and the 325 Collection/Loadout Station Tank. The 325 HWTUs receive, store, and treat dangerous waste generated by Hanford Facility programs. Routine dangerous and/or mixed waste treatment that will be conducted in the 325 HWTUs will include pH adjustment, ion exchange, carbon absorption, oxidation, reduction, waste concentration by evaporation, precipitation, filtration, solvent extraction, solids washing, phase separation, catalytic destruction, and solidification/stabilization

  16. Grout treatment facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1992-07-01

    The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of low-level radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Geologic data, hydrologic data, groundwater monitoring program, information, detection monitoring program, groundwater characterization drawings, building emergency plan--grout treatment facility, response action plan for grout treatment facility, Hanford Facility contingency plan, training course descriptions, overview of the Hanford Facility Grout Performance, assessment, bland use and zoning map, waste minimization plan, cover design engineering report, and clay liners (ADMIXTURES) in semiarid environments

  17. PUREX Storage Tunnels dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-12-01

    The PUREX Storage Tunnels are a mixed waste storage unit consisting of two underground railroad tunnels: Tunnel Number 1 designated 218-E-14 and Tunnel Number 2 designated 218-E-15. The two tunnels are connected by rail to the PUREX Plant and combine to provide storage space for 48 railroad cars (railcars). The PUREX Storage Tunnels provide a long-term storage location for equipment removed from the PUREX Plant. Transfers into the PUREX Storage Tunnels are made on an as-needed basis. Radioactively contaminated equipment is loaded on railcars and remotely transferred by rail into the PUREX Storage Tunnels. Railcars act as both a transport means and a storage platform for equipment placed into the tunnels. This report consists of part A and part B. Part A reports on amounts and locations of the mixed water. Part B permit application consists of the following: Facility Description and General Provisions; Waste Characteristics; Process Information; Groundwater Monitoring; Procedures to Prevent Hazards; Contingency Plan; Personnel Training; Exposure Information Report

  18. Hanford facility dangerous waste permit application, general information portion

    International Nuclear Information System (INIS)

    Hays, C.B.

    1998-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the U.S. Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needed by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in this report)

  19. Hanford facility dangerous waste permit application, general information portion

    Energy Technology Data Exchange (ETDEWEB)

    Hays, C.B.

    1998-05-19

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the U.S. Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needed by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in this report).

  20. Treatment and disposal techniques of dangerous municipal solid wastes

    International Nuclear Information System (INIS)

    Beone, G.; Carbone, A.I.; Zagaroli, M.

    1989-01-01

    This paper describes the qualitative and quantitative features of the different types of dangerous municipal solid wastes, according to Italian law. In the second part the impact on environment and man health is presented. This impact should be minimized by suitable controlled disposal techniques, which differ from other municipal waste treatments. Finally, the paper deals with the most appropriate systems for treatment and disposal of such kind of waste. Particularly, some research activities in the field of metal recovery from used batteries, sponsored by ENEA, and carrying out by private companies, are described. (author)

  1. Hanford facility dangerous waste permit application, 616 Nonradioactive dangerous waste storage facility

    Energy Technology Data Exchange (ETDEWEB)

    Price, S.M.

    1997-04-30

    This chapter provides information on the physical, chemical, and biological characteristics of the waste stored at the 616 NRDWSF. A waste analysis plan is included that describes the methodology used for determining waste types.

  2. Hanford facility dangerous waste permit application, 616 Nonradioactive dangerous waste storage facility

    International Nuclear Information System (INIS)

    Price, S.M.

    1997-01-01

    This chapter provides information on the physical, chemical, and biological characteristics of the waste stored at the 616 NRDWSF. A waste analysis plan is included that describes the methodology used for determining waste types

  3. River Protection Project (RPP) Dangerous Waste Training Plan

    International Nuclear Information System (INIS)

    POHTO, R.E.

    2000-01-01

    This supporting document contains the training plan for dangerous waste management at River Protection Project TSD Units. This document outlines the dangerous waste training program developed and implemented for all Treatment, Storage, and Disposal (TSD) Units operated by River Protection Project (RPP) in the Hanford 200 East, 200 West and 600 Areas and the <90 Day Accumulation Area at 209E. Operating TSD Units managed by RPP are: the Double-Shell Tank (DST) System, 204-AR Waste Unloading Facility, Grout, and the Single-Shell Tank (SST) System. The program is designed in compliance with the requirements of Washington Administrative Code (WAC) 173-303-330 and Title 40 Code of Federal Regulations (CFR) 265.16 for the development of a written dangerous waste training program and the Hanford Facility Permit. Training requirements were determined by an assessment of employee duties and responsibilities. The RPP training program is designed to prepare employees to operate and maintain the Tank Farms in a safe, effective, efficient, and environmentally sound manner. In addition to preparing employees to operate and maintain the Tank Farms under normal conditions, the training program ensures that employees are prepared to respond in a prompt and effective manner should abnormal or emergency conditions occur. Emergency response training is consistent with emergency responses outlined in the following Building Emergency Plans: HNF-IP-0263-TF and HNF-=IP-0263-209E

  4. Dangerous Waste Characteristics of Contact-Handled Transuranic Mixed Wastes from the Hanford Tanks

    Energy Technology Data Exchange (ETDEWEB)

    Tingey, Joel M.; Bryan, Garry H.; Deschane, Jaquetta R.

    2004-08-31

    This report summarizes existing analytical data from samples taken from the Hanford tanks designated as potentially containing transuranic mixed process wastes. Process knowledge of the wastes transferred to these tanks has been reviewed to determine whether the dangerous waste characteristics now assigned to all Hanford underground storage tanks are applicable to these particular wastes. Supplemental technologies are being examined to accelerate the Hanford tank waste cleanup mission and accomplish waste treatment safely and efficiently. To date, 11 Hanford waste tanks have been designated as potentially containing contact-handled (CH) transuranic mixed (TRUM) wastes. The CH-TRUM wastes are found in single-shell tanks B-201 through B-204, T-201 through T-204, T-104, T-110, and T-111. Methods and equipment to solidify and package the CH-TRUM wastes are part of the supplemental technologies being evaluated. The resulting packages and wastes must be acceptable for disposal at the Waste Isolation Pilot Plant (WIPP). The dangerous waste characteristics being considered include ignitability, corrosivity, reactivity, and toxicity arising from the presence of 2,4,5-trichlorophenol at levels above the dangerous waste threshold. The analytical data reviewed include concentrations of sulfur, sulfate, cyanide, 2,4,5-trichlorophenol, total organic carbon, and oxalate; the composition of the tank headspace, pH, and mercury. Differential scanning calorimetry results were used to determine the energetics of the wastes as a function of temperature.

  5. Hanford facility dangerous waste permit application, 242-A evaporator

    International Nuclear Information System (INIS)

    Engelmann, R.H.

    1997-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, 'operating' treatment, storage, and/or disposal units, such as the 242-A Evaporator (this document, DOE/RL-90-42)

  6. 224-T Transuranic Waste Storage and Assay Facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1992-01-01

    Westinghouse Hanford Company is a major contractor to the US Department of Energy Richland Field Office and serves as cooperator of the 224-T Transuranic Waste Storage and Assay Facility, the storage unit addressed in this permit application. At the time of submission of this portion of the Hanford Facility. Dangerous Waste Permit Application covering the 224-T Transuranic Waste Storage and Assay Facility, many issues identified in comments to the draft Hanford Facility Dangerous Waste Permit remain unresolved. This permit application reflects the positions taken by the US Department of Energy, Company on the draft Hanford Facility Dangerous Waste Permit and may not be read to conflict with those comments. The 224-T Transuranic Waste Storage and Assay Facility Dangerous Waste Permit Application (Revision 0) consists of both a Part A and Part B permit application. An explanation of the Part A revisions associated with this unit, including the Part A revision currently in effect, is provided at the beginning of the Part A section. The Part B consists of 15 chapters addressing the organization and content of the Part B Checklist prepared by the Washington State Department of Ecology (Ecology 1987). The 224-T Transuranic Waste Storage and Assay Facility Dangerous Waste Permit Application contains information current as of March 1, 1992

  7. Hanford facility dangerous waste permit application, general information portion. Revision 3

    International Nuclear Information System (INIS)

    Sonnichsen, J.C.

    1997-01-01

    For purposes of the Hanford facility dangerous waste permit application, the US Department of Energy's contractors are identified as ''co-operators'' and sign in that capacity (refer to Condition I.A.2. of the Dangerous Waste Portion of the Hanford Facility Resource Conservation and Recovery Act Permit). Any identification of these contractors as an ''operator'' elsewhere in the application is not meant to conflict with the contractors' designation as co-operators but rather is based on the contractors' contractual status with the U.S. Department of Energy, Richland Operations Office. The Dangerous Waste Portion of the initial Hanford Facility Resource Conservation and Recovery Act Permit, which incorporated five treatment, storage, and/or disposal units, was based on information submitted in the Hanford Facility Dangerous Waste Permit Application and in closure plan and closure/postclosure plan documentation. During 1995, the Dangerous Waste Portion was modified twice to incorporate another eight treatment, storage, and/or disposal units; during 1996, the Dangerous Waste Portion was modified once to incorporate another five treatment, storage, and/or disposal units. The permit modification process will be used at least annually to incorporate additional treatment, storage, and/or disposal units as permitting documentation for these units is finalized. The units to be included in annual modifications are specified in a schedule contained in the Dangerous Waste Portion of the Hanford Facility Resource Conservation and Recovery Act Permit. Treatment, storage, and/or disposal units will remain in interim status until incorporated into the Permit. The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (this document, DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to individual operating treatment, storage, and/or disposal units for which

  8. Hanford facility dangerous waste permit application, general information portion. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    Sonnichsen, J.C.

    1997-08-21

    For purposes of the Hanford facility dangerous waste permit application, the US Department of Energy`s contractors are identified as ``co-operators`` and sign in that capacity (refer to Condition I.A.2. of the Dangerous Waste Portion of the Hanford Facility Resource Conservation and Recovery Act Permit). Any identification of these contractors as an ``operator`` elsewhere in the application is not meant to conflict with the contractors` designation as co-operators but rather is based on the contractors` contractual status with the U.S. Department of Energy, Richland Operations Office. The Dangerous Waste Portion of the initial Hanford Facility Resource Conservation and Recovery Act Permit, which incorporated five treatment, storage, and/or disposal units, was based on information submitted in the Hanford Facility Dangerous Waste Permit Application and in closure plan and closure/postclosure plan documentation. During 1995, the Dangerous Waste Portion was modified twice to incorporate another eight treatment, storage, and/or disposal units; during 1996, the Dangerous Waste Portion was modified once to incorporate another five treatment, storage, and/or disposal units. The permit modification process will be used at least annually to incorporate additional treatment, storage, and/or disposal units as permitting documentation for these units is finalized. The units to be included in annual modifications are specified in a schedule contained in the Dangerous Waste Portion of the Hanford Facility Resource Conservation and Recovery Act Permit. Treatment, storage, and/or disposal units will remain in interim status until incorporated into the Permit. The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (this document, DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to individual operating treatment, storage, and/or disposal units for which

  9. Dangerous Waste Characteristics of Waste from Hanford Tank 241-S-109

    Energy Technology Data Exchange (ETDEWEB)

    Tingey, Joel M.; Bryan, Garry H.; Deschane, Jaquetta R.

    2004-11-05

    Existing analytical data from samples taken from Hanford Tank 241-S-109, along with process knowledge of the wastes transferred to this tank, are reviewed to determine whether dangerous waste characteristics currently assigned to all waste in Hanford underground storage tanks are applicable to this tank waste. Supplemental technologies are examined to accelerate the Hanford tank waste cleanup mission and to accomplish the waste treatment in a safer and more efficient manner. The goals of supplemental technologies are to reduce costs, conserve double-shell tank space, and meet the scheduled tank waste processing completion date of 2028.

  10. Low-Level Burial Grounds Dangerous Waste Permit Application

    International Nuclear Information System (INIS)

    1989-01-01

    The single dangerous waste permit identification number issued to the Hanford Site by the US Environmental Protection Agency and the Washington State Department of Ecology is US Environmental Protection Agency/State Identification Number WA 7890008967. This identification number encompasses a number of waste management units within the Hanford Site. Westinghouse Hanford Company is a major contractor to the US Department of Energy-Richland Operations Office and serves as co-operator of the Low-Level Burial Grounds, the waste management unit addressed by this permit application. The Low-Level Burial Grounds Dangerous Waste Permit Application consists of both a Part A and a Part B Permit Application. The original Part A, submitted in November 1985, identified landfills, retrievable storage units, and reserved areas. An explanation of subsequent Part A revisions is provided at the beginning of the Part A section. The Part B consists of 15 chapters addressing the organization and content of the Part B checklist prepared by the Washington State Department of Ecology

  11. Low-Level Burial Grounds Dangerous Waste Permit Application

    International Nuclear Information System (INIS)

    1989-01-01

    The single dangerous waste permit identification number issued to the Hanford Site by the US Environmental Protection Agency and the Washington State Department of Ecology is US Environmental Protection Agency/State Identification Number WA 7890008967. This identification number encompasses a number of waste management units within the Hanford Site. Westinghouse Hanford Company is a major contractor to the US Department of Energy-Richland Operations Office and serves as co-operator of the Low-Level Burial Grounds, the waste management unit addressed by this permit application. The Low-Level Burial Grounds Dangerous Waste Permit Application consists of both a Part A and a Part B Permit Application. The original Part A, submitted in November 1985, identified landfills, retrievable storage units, and reserved areas. An explanation of subsequent Part A revisions is provided at the beginning of the Part A section. Part B consists of 15 chapters addressing the organization and content of the Part B checklist prepared by the Washington State Department of Ecology

  12. Hanford Facility Dangerous Waste Permit Application, 222-S Laboratory Complex

    International Nuclear Information System (INIS)

    WILLIAMS, J.F.

    2000-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating treatment, storage, and/or disposal units, such as the 222-S Laboratory Complex (this document, DOE/RL-91-27). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needs defined by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the 222-S Laboratory Complex permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text. Information provided in this 222-S Laboratory Complex permit application documentation is current as of August 2000

  13. Hanford Facility dangerous waste permit application, general information

    International Nuclear Information System (INIS)

    1993-05-01

    The current Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (this document, number DOE/RL-91-28) and a treatment, storage, and/or disposal Unit-Specific Portion, which includes documentation for individual TSD units (e.g., document numbers DOE/RL-89-03 and DOE/RL-90-01). Both portions consist of a Part A division and a Part B division. The Part B division consists of 15 chapters that address the content of the Part B checklists prepared by the Washington State Department of Ecology (Ecology 1987) and the US Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information requirements mandated by the Hazardous and Solid Waste Amendments of 1984 and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology checklist section numbers, in brackets, follow the chapter headings and subheadings. Documentation contained in the General Information Portion (i.e., this document, number DOE/RL-91-28) is broader in nature and applies to all treatment, storage, and/or disposal units for which final status is sought. Because of its broad nature, the Part A division of the General Information Portion references the Hanford Facility Dangerous Waste Part A Permit Application (document number DOE/RL-88-21), a compilation of all Part A documentation for the Hanford Facility

  14. Decree 2211: Standards to control the generation and handling of dangerous wastes

    International Nuclear Information System (INIS)

    1992-01-01

    This Decree has for object to establish the conditions under which should be carried out the activities of generation and handling of dangerous waste, in order to prevent damages to health and to the atmosphere. It includes: definitions; a list of sources of waste; a list of constituent of dangerous waste; the characteristics of danger; a lists of maximum permissible concentrations in leachates, handling of dangerous waste, criterion for transport, monitoring form, storage areas, treatment and final disposition, storage, elimination, incineration, recycling, reuse and recovery, installation and operation of security backfilling, book of waste record, control of activities, obligations in charge of those who manage dangerous waste, and trans border movements of dangerous waste [es

  15. Hanford facility dangerous waste permit application, general information portion

    Energy Technology Data Exchange (ETDEWEB)

    Price, S.M., Westinghouse Hanford

    1996-07-29

    The `Hanford Facility Dangerous Waste Permit Application` is considered to be a single application organized into a General Information Portion (this document, DOE/RL-91-28) and a Unit- Specific Portion. The scope of the General Information Portion includes information that could be used to discuss operating units, units undergoing closure, or units being dispositioned through other options. Documentation included in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units. A checklist indicating where information is contained in the General Information Portion, in relation to the Washington State Department of Ecology guidance documentation, is located in the Contents Section. The intent of the General Information Portion is: (1) to provide an overview of the Hanford Facility; and (2) to assist in streamlining efforts associated with treatment, storage, and/or disposal unit-specific Part B permit application, preclosure work plan, closure work plan, closure plan, closure/postclosure plan, or postclosure permit application documentation development, and the `Hanford Facility Resource Conservation and Recovery Act Permit` modification process. Revision 2 of the General Information Portion of the `Hanford Facility Dangerous Waste Permit Application` contains information current as of May 1, 1996. This document is a complete submittal and supersedes Revision 1.

  16. Hanford facility dangerous waste permit application, PUREX storage tunnels

    International Nuclear Information System (INIS)

    Price, S.M.

    1997-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating treatment, storage, and/or disposal units, such as the PUREX Storage Tunnels (this document, DOE/RL-90-24). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the US Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needs defined by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. A checklist indicating where information is contained in the PUREX Storage Tunnels permit application documentation, in relation to the Washington State Department of Ecology guidance, is located in the Contents Section. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the PUREX Storage Tunnels permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text. Information provided in this PUREX Storage Tunnels permit application documentation is current as of April 1997

  17. Liquid effluent retention facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-06-01

    This permit application addresses the transfer and storage of a mixed-waste stream called 'process condensate' generated in the 242-A Evaporator. Process condensate is piped via 4,950 feet (1,509 meters) of double-wall pipe to any one of four 6.5-million gallon (24.6-million liter) double-lined basins; the double-wall pipe, basins, and ancillary equipment comprise the LERF. Eventually, the liquid will be piped directly to a new treatment system (covered under a separate Part B permit application) specifically designed to reduce the concentrations of dangerous constituents of the process condensate to acceptable levels for discharge. The LERF provides storage capacity for the process condensate during a period of projected shortage of double-shell tank (DST) volume at the Hanford Site. The DST waste is to be processed in the 242-A Evaporator, significantly reducing the volume of slurry returned to the DSTs for long-term storage for future treatment and/or disposal. Process condensate is a byproduct of this waste reduction process and is being stored temporarily in the LERF until the process condensate can be treated and disposed of as nonhazardous

  18. Management and hazardous waste characterization in Central for Isotop and Radiation Application based on potential dangers

    International Nuclear Information System (INIS)

    Niken Hayudanti Anggarini; Megi Stefanus; Prihatiningsih

    2014-01-01

    Separating and storing hazardous waste have been done based on the physical, chemical, and based on potential dangers due to safety hazardous waste temporary storage warehouse. From the results of data collection in 2014 found that the most dominant hazardous waste is organic liquid waste which reaches 61 %, followed by inorganic liquid waste 33 % while organic solid waste and inorganic solid waste has a small portion. When viewed from potential danger, flammable liquid waste has the greatest volume percentage it is 47 % and is followed by a corrosive liquid waste 26 %, while the liquid waste that has not been identified is quite large, which is 9 %. From the highest hazard potential data, hazardous waste storage warehouse is required to have good air circulation and waste storage shelf protected from direct solar heat. Cooperation of lab workers and researchers are also indispensable in providing identification of each waste generated to facilitate the subsequent waste management. (author)

  19. Low-level burial grounds dangerous waste permit application

    International Nuclear Information System (INIS)

    1990-07-01

    This document is submitted to request an exemption for Trench 94 from dangerous waste landfill liner and leachate collection and removal system (hereinafter referred to as liner/leachate system) requirements. This exemption request is based on an evaluation which demonstrates that burial in Trench 94 of cathodically protected submarine reactor compartments (SRC), which contain lead and polychlorinated biphenyls (PCB) as hazardous constituents, is as effective as disposal in a landfill having a liner/leachate system. This demonstration also considers the effectiveness of burial in Trench 94 in terms of preventing long-term migration of contaminants to groundwater or surface water. Modeling results indicate that release of contaminants to the groundwater or surface water will not occur until after long periods of time and that even after reaching the groundwater, contaminants will not be in excess of current regulatory limits, such as drinking water standards. Chapter 1.0 provides introductory information concerning this request, including the scope of the exemption request and relevant background information. The five subsequent chapters provide information needed to support the exemption request. Chapter 2.0 discusses the regulatory basis for the exemption request and presents performance objectives related to regulatory requirements. Chapter 3.0 provides a description of the site and its operation. Chapter 4.0 describes the wastes subject to this exemption request Chapter 5.0 discusses the performance of the disposal site with respect to performance objectives. Finally, Chapter 6.0 presents the actual request for exemption from requirements for a liner/leachate system. 30 refs., 13 figs., 6 tabs

  20. Low-level burial grounds dangerous waste permit application design documents

    International Nuclear Information System (INIS)

    1990-08-01

    This document serves a supplement to the already existing ''Low-Level Burial Ground Dangerous Waste Permit Application Design Documents.'' This paper contains information regarding drawings, construction specifications, and liner/leachate compatibility test plans

  1. Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    The 200 Area Effluent Treatment Facility Dangerous Waste Permit Application documentation consists of both Part A and a Part B permit application documentation. An explanation of the Part A revisions associated with this treatment and storage unit, including the current revision, is provided at the beginning of the Part A section. Once the initial Hanford Facility Dangerous Waste Permit is issued, the following process will be used. As final, certified treatment, storage, and/or disposal unit-specific documents are developed, and completeness notifications are made by the US Environmental Protection Agency and the Washington State Department of Ecology, additional unit-specific permit conditions will be incorporated into the Hanford Facility Dangerous Waste Permit through the permit modification process. All treatment, storage, and/or disposal units that are included in the Hanford Facility Dangerous Waste Permit Application will operate under interim status until final status conditions for these units are incorporated into the Hanford Facility Dangerous Waste Permit. The Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility contains information current as of May 1, 1993.

  2. Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility

    International Nuclear Information System (INIS)

    1993-08-01

    The 200 Area Effluent Treatment Facility Dangerous Waste Permit Application documentation consists of both Part A and a Part B permit application documentation. An explanation of the Part A revisions associated with this treatment and storage unit, including the current revision, is provided at the beginning of the Part A section. Once the initial Hanford Facility Dangerous Waste Permit is issued, the following process will be used. As final, certified treatment, storage, and/or disposal unit-specific documents are developed, and completeness notifications are made by the US Environmental Protection Agency and the Washington State Department of Ecology, additional unit-specific permit conditions will be incorporated into the Hanford Facility Dangerous Waste Permit through the permit modification process. All treatment, storage, and/or disposal units that are included in the Hanford Facility Dangerous Waste Permit Application will operate under interim status until final status conditions for these units are incorporated into the Hanford Facility Dangerous Waste Permit. The Hanford Facility Dangerous Waste Permit Application, 200 Area Effluent Treatment Facility contains information current as of May 1, 1993

  3. Annual Waste Minimization Summary Report

    International Nuclear Information System (INIS)

    Haworth, D.M.

    2011-01-01

    This report summarizes the waste minimization efforts undertaken by National Security TechnoIogies, LLC, for the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during calendar year 2010. The NNSA/NSO Pollution Prevention Program establishes a process to reduce the volume and toxicity of waste generated by NNSA/NSO activities and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment.

  4. Hazardous waste. Annual report, 1984

    International Nuclear Information System (INIS)

    1985-01-01

    Activities in the Hazardous Waste Program area in 1984 ranged from preparing management and long-range plans to arranging training seminars. Past and present generation of hazardous wastes were the key concerns. This report provides a summary of the significant events which took place in 1984. 6 tabs

  5. Hanford Central Waste Complex: Waste Receiving and Processing Facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-10-01

    The Hanford Central Waste Complex is an existing and planned series of treatment, and/or disposal (TSD) unites that will centralize the management of solid waste operations at a single location on the Hanford Facility. The Complex includes two units: the WRAP Facility and the Radioactive Mixed Wastes Storage Facility (RMW Storage Facility). This Part B permit application addresses the WRAP Facility. The Facility will be a treatment and storage unit that will provide the capability to examine, sample, characterize, treat, repackage, store, and certify radioactive and/or mixed waste. Waste treated and stored will include both radioactive and/or mixed waste received from onsite and offsite sources. Certification will be designed to ensure and demonstrate compliance with waste acceptance criteria set forth by onsite disposal units and/or offsite facilities that subsequently are to receive waste from the WRAP Facility. This permit application discusses the following: facility description and general provisions; waste characterization; process information; groundwater monitoring; procedures to prevent hazards; contingency plant; personnel training; exposure information report; waste minimization plan; closure and postclosure requirements; reporting and recordkeeping; other relevant laws; certification

  6. 300 Area dangerous waste tank management system: Compliance plan approach. Final report

    International Nuclear Information System (INIS)

    1996-03-01

    In its Dec. 5, 1989 letter to DOE-Richland (DOE-RL) Operations, the Washington State Dept. of Ecology requested that DOE-RL prepare ''a plant evaluating alternatives for storage and/or treatment of hazardous waste in the 300 Area...''. This document, prepared in response to that letter, presents the proposed approach to compliance of the 300 Area with the federal Resource Conservation and Recovery Act and Washington State's Chapter 173-303 WAC, Dangerous Waste Regulations. It also contains 10 appendices which were developed as bases for preparing the compliance plan approach. It refers to the Radioactive Liquid Waste System facilities and to the radioactive mixed waste

  7. 300 Area dangerous waste tank management system: Compliance plan approach. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    In its Dec. 5, 1989 letter to DOE-Richland (DOE-RL) Operations, the Washington State Dept. of Ecology requested that DOE-RL prepare ``a plant evaluating alternatives for storage and/or treatment of hazardous waste in the 300 Area...``. This document, prepared in response to that letter, presents the proposed approach to compliance of the 300 Area with the federal Resource Conservation and Recovery Act and Washington State`s Chapter 173-303 WAC, Dangerous Waste Regulations. It also contains 10 appendices which were developed as bases for preparing the compliance plan approach. It refers to the Radioactive Liquid Waste System facilities and to the radioactive mixed waste.

  8. Nonradioactive Dangerous Waste Landfill sampling and analysis plan and data quality objectives process summary report

    International Nuclear Information System (INIS)

    Smith, R.C.

    1997-08-01

    This sampling and analysis plan defines the sampling and analytical activities and associated procedures that will be used to support the Nonradioactive Dangerous Waste Landfill soil-gas investigation. This SAP consists of three sections: this introduction, the field sampling plan, and the quality assurance project plan. The field sampling plan defines the sampling and analytical methodologies to be performed

  9. Earthquakes: no danger for deep underground nuclear waste repositories

    International Nuclear Information System (INIS)

    2010-03-01

    On the Earth, the continental plates are steadily moving. Principally at the plate boundaries such shifts produce stresses which are released in form of earthquakes. The highest the built-up energy, the more violent will be the shaking. Earthquakes accompany mankind from very ancient times on and they disturb the population. Till now nobody is able to predict where and when they will take place. But on the Earth there are regions where, due to their geological situation, the occurrence of earthquakes is more probable than elsewhere. The impact of a very strong earthquake on the structures at the Earth surface depends on several factors. Besides the ground structure, the density of buildings, construction style and materials used play an important role. Construction-related technical measures can improve the safety of buildings and, together with a correct behaviour of the people concerned, save many lives. Earthquakes are well known in Switzerland. Here, the stresses are due to the collision of the African and European continental plates that created the Alps. The impact of earthquake is more limited in the underground than at the Earth surface. There is no danger for deep underground repositories

  10. Waste dumps in local communities in developing countries and hidden danger to health.

    Science.gov (United States)

    Anetor, Gloria O

    2016-07-01

    The rapid industrialisation and urbanisation fuelled by a fast-growing population has led to the generation of a huge amount of waste in most communities in developing countries. The hidden disorders and health dangers in waste dumps are often ignored. The waste generated in local communities is usually of a mixed type consisting of domestic waste and waste from small-scale industrial activities. Among these wastes are toxic metals, lead (Pb), cadmium (Cd), arsenic (As), mercury (Hg), halogenated organic compounds, plastics, remnants of paints that are themselves mixtures of hazardous substances, hydrocarbons and petroleum product-contaminated devices. Therefore, there is the urgent need to create an awareness of the harmful health effect of toxic wastes in developing countries, especially Nigeria. This is a review aimed at creating awareness on the hidden dangers of waste dumps to health in local communities in developing countries. Many publications in standard outlets use the following keywords: cancer, chemical toxicity, modern environmental health hazards, waste management and waste speciation in PubMed, ISI, Toxbase environmental digest, related base journals, and some standard textbooks, as well as the observation of the researcher between 1959 and 2014. Studies revealed the preponderance of toxic chemicals such as Pb, Cd, As and Hg in dump sites that have the risk of entering food chain and groundwater supplies, and these can give rise to endemic malnutrition and may also increase susceptibility to mutagenic substances, thereby increasing the incidence of cancer in developing countries. Industrialisation and urbanisation have brought about a change in the waste that is generated in contemporary communities in developing countries. Therefore, there is the need to embrace speciation and sound management of waste, probably including bioremediation. The populations in the local communities need regulatory agencies who are health educators as positive change

  11. Nonradioactive Dangerous Waste Landfill supplemental information to the Hanford Facility Contingency Plan (DOE/RL-93-75)

    International Nuclear Information System (INIS)

    Ingle, S.J.

    1996-05-01

    This document is a unit-specific contingency plan for the Nonradioactive Dangerous Waste Landfill and is intended to be used as a supplement to DOE/RL-93-75, 'Hanford Facility Contingency Plan.' This unit-specific plan is to be used to demonstrate compliance with the contingency plan requirements of the Washington Administrative Code, Chapter 173-303 for certain Resource, Conservation and Recovery Act of 1976 waste management units. The Nonradioactive Dangerous Waste Landfill (located approximately 3.5 miles southeast of the 200 East Area at the Hanford Site) was used for disposal of nonradioactive dangerous waste from January 1975 to May 1985. Currently, there are no dangerous waste streams disposed in the Nonradioactive Dangerous Waste Landfill. Dangerous waste management activities are no longer required at the landfill. The landfill does not present a significant hazard to adjacent units, personnel, or the environment. It is unlikely that incidents presenting hazards to public health or the environment would occur at the Nonradioactive Dangerous Waste Landfill

  12. Hanford facility dangerous waste permit application, 616 Nonradioactive Dangerous Waste Storage Facility. Revision 2, Chapter 3.0, Waste characteristics supplemental information; Volume 1

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains supplemental information concerning waste characteristics for numerous nonradioactive waste materials. Uniform hazardous waste manifests are included for routine as well as nonroutine waste streams. The manifests contain the following information: waste disposal analysis; general instructions; waste destination; and transportation representatives

  13. Hanford facility dangerous waste permit application, 616 Nonradioactive Dangerous Waste Storage Facility. Revision 2, Chapter 3.0, Waste characteristics supplemental information; Volume 2

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains supplemental information concerning waste characteristics for numerous nonradioactive waste materials. Uniform hazardous waste manifests are included for routine as well as nonroutine waste streams. The manifests contain the following information: waste disposal analysis; general instructions; waste destination; and transportation representatives

  14. Hanford facility dangerous waste permit application, 616 Nonradioactive Dangerous Waste Storage Facility. Revision 2, Chapter 3.0, Waste characteristics supplemental information; Volume 3

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains supplemental information concerning waste characteristics for numerous nonradioactive waste materials. Uniform hazardous waste manifests are included for routine as well as nonroutine waste streams. The manifests contain the following information: waste disposal analysis; general instructions; waste destination; and transportation representatives

  15. 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.

  16. Annual radioactive waste tank inspection program -- 1993

    International Nuclear Information System (INIS)

    McNatt, F.G. Sr.

    1994-05-01

    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

  17. Guidelines for the disposal of dangerous and toxic wastes so as to minimize or prevent environmental and water pollution

    CSIR Research Space (South Africa)

    Rudd, RT

    1978-01-01

    Full Text Available Modern society is producing ever increasing quantities of dangerous and/or toxic wastes, which require safe and effective disposal if they are not to pose a threat to our water supplies or the environment in general....

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

    International Nuclear Information System (INIS)

    1990-01-01

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

  19. 616 Nonradioactive Dangerous Waste Storage Facility -- Essential/support drawing list. Revision 2

    International Nuclear Information System (INIS)

    Busching, K.R.

    1994-01-01

    This document identifies the essential and supporting engineering drawings for the 616 Nonradioactive Dangerous Waste Storage Facility. The purpose of the documents is to describe the criteria used to identify and the plan for updating and maintaining their accuracy. Drawings are designated as essential if they relate to safety systems, environmental monitoring systems, effluents, and facility HVAC, electrical, and plumbing systems. Support drawings are those which are frequently used or describe a greater level of detail for equipment, components, or systems shown on essential drawings. A listing of drawings identified as essential or support is provided in Table A

  20. 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.

  1. 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.

  2. Annual report of waste generation and pollution prevention progress 1999

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-09-01

    This Annual Report summarizes and highlights waste generation, waste reduction, pollution prevention accomplishments, and cost avoidance for 44 U.S. Department of Energy reporting sites for Calendar Year 1999. This section summarizes Calendar Year 1999 Complex-wide waste generation and pollution prevention accomplishments.

  3. Plutonium Finishing Plant Treatment and Storage Unit Dangerous Waste Training Plan

    International Nuclear Information System (INIS)

    ENTROP, G.E.

    2000-01-01

    The training program for personnel performing waste management duties pertaining to the Plutonium Finishing Plant (PFP) Treatment and Storage Unit is governed by the general requirements established in the Plutonium Finishing Plant Dangerous Waste Training Plan (PFP DWTP). The PFP Treatment and Storage Unit DWTP presented below incorporates all of the components of the PFP DWTP by reference. The discussion presented in this document identifies aspects of the training program specific to the PFP Treatment and Storage Unit. The training program includes specifications for personnel instruction through both classroom and on-the-job training. Training is developed specific to waste management duties. Hanford Facility personnel directly involved with the PFP Treatment and Storage Unit will receive training to container management practices, spill response, and emergency response. These will include, for example, training in the cementation process and training pertaining to applicable elements of WAC 173-303-330(1)(d). Applicable elements from WAC 173-303-330(1)(d) for the PFP Treatment and Storage Unit include: procedures for inspecting, repairing, and replacing facility emergency and monitoring equipment; communications and alarm systems; response to fires or explosions; and shutdown of operations

  4. Dangers associated with civil nuclear power programmes: weaponization and nuclear waste.

    Science.gov (United States)

    Boulton, Frank

    2015-07-24

    The number of nuclear power plants in the world rose exponentially to 420 by 1990 and peaked at 438 in 2002; but by 2014, as closed plants were not replaced, there were just 388. In spite of using more renewable energy, the world still relies on fossil fuels, but some countries plan to develop new nuclear programmes. Spent nuclear fuel, one of the most dangerous and toxic materials known, can be reprocessed into fresh fuel or into weapons-grade materials, and generates large amounts of highly active waste. This article reviews available literature on government and industry websites and from independent analysts on world energy production, the aspirations of the 'new nuclear build' programmes in China and the UK, and the difficulties in keeping the environment safe over an immense timescale while minimizing adverse health impacts and production of greenhouse gases, and preventing weaponization by non-nuclear-weapons states acquiring civil nuclear technology.

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

    International Nuclear Information System (INIS)

    1997-02-01

    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

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

    International Nuclear Information System (INIS)

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

    1987-09-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    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.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1987-09-01

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

  9. Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    Coenenberg, J.G.

    1997-08-15

    The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, `operating` treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating

  10. Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility

    International Nuclear Information System (INIS)

    Coenenberg, J.G.

    1997-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, 'operating' treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating

  11. Sandia National Laboratories, California Waste Management Program annual report.

    Energy Technology Data Exchange (ETDEWEB)

    Brynildson, Mark E.

    2010-02-01

    The annual program report provides detailed information about all aspects of the Sandia National Laboratories, California (SNL/CA) Waste Management Program. It functions as supporting documentation to the SNL/CA Environmental Management System Program Manual. This annual program report describes the activities undertaken during the past year, and activities planned in future years to implement the Waste Management (WM) Program, one of six programs that supports environmental management at SNL/CA.

  12. Annual report 1999. Department of wastes disposal and storage

    International Nuclear Information System (INIS)

    2000-01-01

    This annual report presents the organization, the personnel, the collaborations, the scientific researches and the publications of the Department of wastes disposal and storage of the CEA. A thematic presentation of the research and development programs is provided bringing information on the liquid effluents processing, the materials and solid wastes processing, the wastes conditioning, the characterization, the storage, the radionuclides chemistry and migration, the dismantling and the environment. (A.L.B.)

  13. Quality of Life at Work: A study conducted in an organization of waste collection not dangerous

    Directory of Open Access Journals (Sweden)

    Grasiele Cabral Pereira

    2018-04-01

    Full Text Available Incluir o resumo em inglês. This article aims to elaborate a diagnosis of a not dangerous waste collection organization, that seeks to analyze which factors determine the quality of life of the employees of the organization. Nadler and Lawler (1983 affirm that Quality of Life at Work is a way of thinking about individuals, work and the company itself. This research is characterized as exploratory, descriptive and quantitative with the use of statistics and application of a questionnaire aiming to identify the Quality of Life at Work of this specific company. The questionnaire applied was created through the interpretation and analysis of the eight dimensions of QWL presented by Walton (1973. As for the population, an intentional sample was used, comprising the employees of the administrative sector. As for the analysis carried out from the graphs, it was verified that the organization provides a good quality of life to its employees, since just a small percentages of respondents did not agree in part or did not agree with some of the affirmative questions obtained.

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

    International Nuclear Information System (INIS)

    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

  15. Mercury separation from mixed wastes. Annual report

    International Nuclear Information System (INIS)

    Taylor, P.A.; Klasson, K.T.; Corder, S.L.; Carlson, T.R.; McCandless, K.R.

    1995-11-01

    This is an assessment of new sorbents for removing Hg from wastes at US DOE sites. Four aqueous wastes were used for the laboratory tests: a simulant of a high-salt, acidic waste currently stored at INEL, a simulant of a high-salt, alkaline waste stored at Savannah River (SRS), a dilute LiOH solution stored at Y-12, and a low-salt, neutral groundwater generated at Y-12. Eight adsorbents covering a wide range of cost and capability were tested. Screening tests identified the most promising adsorbents, and column tests were performed using at least two adsorbents for each waste stream. No one adsorbent is effective in all of these waste streams. Based on loading capacity and compatibility, the most effect adsorbents to date are SuperLig 618 for the INEL tank waste simulant, Mersorb and Ionac SR-3 for the SRS tank waste simulant, Durasil 70 and Ionac SR-3 for the LiOH solution, and Ionac SR-3, followed by Ionac SR-4 and Mersorb, for the Y-12 groundwater

  16. 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.

  17. 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.

  18. 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.

  19. Annual report of tank waste treatability

    Energy Technology Data Exchange (ETDEWEB)

    Lane, A.G. [Los Alamos Technical Associates, Inc., NM (United States); Kirkbride, R.A. [Westinghouse Hanford Co., Richland, WA (United States)

    1993-09-01

    This report has been prepared as part of the Hanford Federal Facility Agreement and Consent Order* (Tri-Party Agreement) and constitutes completion of Tri-Party Agreement milestone M-04-00D for fiscal year 1993. This report provides a summary of treatment activities for newly generated waste, existing double-shell tank waste, and existing single-shell tank waste, as well as a summary of grout disposal feasibility, glass disposal feasibility, alternate methods for disposal, and safety issues which may impact the treatment and disposal of existing defense nuclear wastes. This report is an update of the 1992 report and is intended to provide traceability for the documentation by statusing the studies, activities, and issues which occurred in these areas listed above over the period of March 1, 1992, through February 28, 1993. Therefore, ongoing studies, activities, and issues which were documented in the previous (1992) report are addressed in this (1993) report.

  20. 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.

  1. Annual report of tank waste treatability

    Energy Technology Data Exchange (ETDEWEB)

    Giese, K.A.

    1991-09-01

    This report has been prepared as part of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) and constitutes completion of Tri-Party Agreement Milestone M-04-00 for fiscal year 1991. This report provides a summary of treatment activities for newly generated waste, existing double-shell tank waste, and existing single-shell tank waste, as well as a summary of grout disposal feasibility, glass disposal feasibility, alternate methods of disposal, and safety issues which may impact the treatment and disposal of existing defense nuclear wastes. This report is an update of the 1990 report and is intended to provide traceability for the documentation of the areas listed above by statusing the studies, activities, and issues which occurred in these areas over the period of March 1, 1990, through February 28, 1991. Therefore, ongoing studies, activities, and issues which were documented in the previous (1990) report are addressed in this subsequent (1991) report. 40 refs., 4 figs., 3 tabs.

  2. Annual radioactive waste tank inspection program - 1991

    International Nuclear Information System (INIS)

    McNatt, F.G.

    1992-01-01

    Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1991 to evaluate these vessels and evaluations based on data accrued by inspections made since the tanks were constructed are the subject of this report

  3. Eighteenth annual report of: The Radioactive Waste Management Advisory Committee

    International Nuclear Information System (INIS)

    1998-07-01

    This annual report reviews the RWMAC's work programme and progress made in 1997-1998; discusses operational and administrative matters including financial management and policy review; and presents the 1998 RWMAC work programme. Particular chapters are devoted to the management of intermediate and high level radioactive waste and spent fuel; the Dounreay Nuclear Establishment; the radioactive waste discharge authorisations. The document presents the RWMAC's review of the Ministry of Defence's radioactive waste management practices. A separate chapter is devoted to the study of radioactive waste management practices in Spain. Annexes to the report include terms of reference and membership of the Radioactive Waste Management Advisory Committee; RWMAC financial statement; declaration and register of member's interests; the RWMAC's 1998 work programme; the RWMAC's response to the Government on Proposals for the control and remediation of radioactively contaminated land

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

    International Nuclear Information System (INIS)

    1990-12-01

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

  5. Nuclear waste treatment program: Annual report for FY 1987

    Energy Technology Data Exchange (ETDEWEB)

    Brouns, R.A.; Powell, J.A. (comps.)

    1988-09-01

    Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment designs, and trouble-shooting assistance, as required to treat existing wastes. This annual report describes progress during FY 1987 towards meeting these two objectives. 24 refs., 59 figs., 24 tabs.

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-12-01

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

  7. Annual report 2000. Department of wastes disposal and storage

    International Nuclear Information System (INIS)

    2001-01-01

    This annual report presents the missions, the organization, the researches progress, the events, the publications and the personnel formation of the Department of wastes disposal and storage in the year 2000, one of the CEA fuel cycle Direction. (A.L.B.)

  8. 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.

  9. Hanford facility dangerous waste Part A, Form 3 and Part B permit application documentation, Central Waste Complex (WA7890008967)(TSD: TS-2-4)

    Energy Technology Data Exchange (ETDEWEB)

    Saueressig, D.G.

    1998-05-20

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating, treatment, storage, and/or disposal units, such as the Central Waste Complex (this document, DOE/RL-91-17). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the U.S. Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needed by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. A checklist indicating where information is contained in the Central Waste Complex permit application documentation, in relation to the Washington State Department of Ecology guidance, is located in the Contents section. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the Central Waste Complex permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text. Information provided in this Central Waste Complex permit application documentation is current as of May 1998.

  10. Hanford facility dangerous waste Part A, Form 3, and Part B permit application documentation for the Central Waste Complex (WA7890008967) (TSD: TS-2-4)

    International Nuclear Information System (INIS)

    Saueressig, D.G.

    1998-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, operating, treatment, storage, and/or disposal units, such as the Central Waste Complex (this document, DOE/RL-91-17). Both the General Information and Unit-Specific portions of the Hanford Facility Dangerous Waste Permit Application address the content of the Part B permit application guidance prepared by the Washington State Department of Ecology (Ecology 1996) and the U.S. Environmental Protection Agency (40 Code of Federal Regulations 270), with additional information needed by the Hazardous and Solid Waste Amendments and revisions of Washington Administrative Code 173-303. For ease of reference, the Washington State Department of Ecology alpha-numeric section identifiers from the permit application guidance documentation (Ecology 1996) follow, in brackets, the chapter headings and subheadings. A checklist indicating where information is contained in the Central Waste Complex permit application documentation, in relation to the Washington State Department of Ecology guidance, is located in the Contents section. Documentation contained in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units (e.g., the glossary provided in the General Information Portion). Wherever appropriate, the Central Waste Complex permit application documentation makes cross-reference to the General Information Portion, rather than duplicating text. Information provided in this Central Waste Complex permit application documentation is current as of May 1998

  11. Annual report of waste generation and pollution prevention progress, 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    This Report summarizes the waste generation and pollution prevention activities of the major operational sites in the Department of Energy (DOE). We are witnessing progress in waste reduction from routine operations that are the focus of Department-wide reduction goals set by the Secretary on May 3,1996. The goals require that by the end of 1999, we reduce, recycle, reuse, and otherwise avoid waste generation to achieve a 50 percent reduction over 1993 levels. This Report provides the first measure of our progress in waste reduction and recycling against our 1993 waste generation baseline. While we see progress in reducing waste from our normal operations, we must begin to focus attention on waste generated by cleanup and facilities stabilization activities that are the major functions of the Office of Environmental Management. Reducing the generation of waste is one of the seven principles that I have established for the Office of Environmental Management Ten Year Plan. As part of our vision to complete a major portion of the environmental cleanup at DOE sites over the next ten years, we must utilize the potential of the pollution prevention program to reduce the cost of our cleanup program. We have included the Secretarial goals as part of the performance measures for the Ten Year Plan, and we are committed to implementing pollution prevention ideas. Through the efforts of both Federal and contractor employees, our pollution prevention program has reduced waste and the cost of our operations. I applaud their efforts and look forward to reporting further waste reduction progress in the next annual update of this Report.

  12. Annual report of waste generation and pollution prevention progress, 1994

    International Nuclear Information System (INIS)

    1996-09-01

    This Report summarizes the waste generation and pollution prevention activities of the major operational sites in the Department of Energy (DOE). We are witnessing progress in waste reduction from routine operations that are the focus of Department-wide reduction goals set by the Secretary on May 3,1996. The goals require that by the end of 1999, we reduce, recycle, reuse, and otherwise avoid waste generation to achieve a 50 percent reduction over 1993 levels. This Report provides the first measure of our progress in waste reduction and recycling against our 1993 waste generation baseline. While we see progress in reducing waste from our normal operations, we must begin to focus attention on waste generated by cleanup and facilities stabilization activities that are the major functions of the Office of Environmental Management. Reducing the generation of waste is one of the seven principles that I have established for the Office of Environmental Management Ten Year Plan. As part of our vision to complete a major portion of the environmental cleanup at DOE sites over the next ten years, we must utilize the potential of the pollution prevention program to reduce the cost of our cleanup program. We have included the Secretarial goals as part of the performance measures for the Ten Year Plan, and we are committed to implementing pollution prevention ideas. Through the efforts of both Federal and contractor employees, our pollution prevention program has reduced waste and the cost of our operations. I applaud their efforts and look forward to reporting further waste reduction progress in the next annual update of this Report

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

    International Nuclear Information System (INIS)

    1985-05-01

    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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-12-01

    This sixth Annual Report to Congress by the Office of Civilian Radioactive Waste Management (OCRWM) describes activities and expenditures of the Office during fiscal year 1988. An epilogue chapter reports significant events from the end of the fiscal year on September 30, 1988 through March 1989. The Nuclear Waste Policy Amendments Act (NWPA) of 1987 made significant changes to the NWPA relating to repository siting and monitored retrievable storage and added new provisions for the establishment of several institutional entities with which OCRWM will interact. Therefore, a dominant theme throughout this report is the implementation of the policy focus and specific provisions of the Amendments Act. 50 refs., 8 figs., 4 tabs.

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

    International Nuclear Information System (INIS)

    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

  16. 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.

  17. Method for contamination control and barrier apparatus with filter for containing waste materials that include dangerous particulate matter

    Science.gov (United States)

    Pinson, Paul A.

    1998-01-01

    A container for hazardous waste materials that includes air or other gas carrying dangerous particulate matter has incorporated in barrier material, preferably in the form of a flexible sheet, one or more filters for the dangerous particulate matter sealably attached to such barrier material. The filter is preferably a HEPA type filter and is preferably chemically bonded to the barrier materials. The filter or filters are preferably flexibly bonded to the barrier material marginally and peripherally of the filter or marginally and peripherally of air or other gas outlet openings in the barrier material, which may be a plastic bag. The filter may be provided with a backing panel of barrier material having an opening or openings for the passage of air or other gas into the filter or filters. Such backing panel is bonded marginally and peripherally thereof to the barrier material or to both it and the filter or filters. A coupling or couplings for deflating and inflating the container may be incorporated. Confining a hazardous waste material in such a container, rapidly deflating the container and disposing of the container, constitutes one aspect of the method of the invention. The chemical bonding procedure for producing the container constitutes another aspect of the method of the invention.

  18. Dangerous waste incineration and its impact on air quality. Case study: the incinerator SC Mondeco SRL Suceava

    Directory of Open Access Journals (Sweden)

    Dumitru MIHĂILĂ

    2015-03-01

    Full Text Available Dangerous waste, such as oil residues, pesticides, lacquers, stains, glues, organic solvents, hospital and food industry residues represent a major risk for all components of the environment (water, air, earth, soil, flora, fauna, people as well. Consequently, their incineration with high-performance burning installations lessens the impact on the environment, especially on the air quality, and it gives the possibility to recuperate the warmth of the incineration. This research presents a representative technique of incineration of dangerous waste at S.C. Mondeco S.R.L. Suceava, which runs according to the European standards, located in the industrial zone of Suceava, on the Suceava river valley Suceava. Also it is analysed the impact of this unit on the quality of nearby air. Moreover, not only the concentrations of gases and powders during the action of the incineration process (paramaters that are continuously monitored by highly methods are analysed, but also here are described the dispersions of those pollutants in the air, taking into account the characteristics of the source and the meteorological parametres that are in the riverbed. 

  19. Low-Level Burial Grounds Dangerous Waste Permit Application design documents

    International Nuclear Information System (INIS)

    1990-01-01

    This document presents the Functional Design Criteria for trenches to be constructed to receive solid radioactive mixed waste (RMW) from on and offsite generators. The new RMW disposal facilities are considered modifications to or lateral expansion of the existing low-level waste burial grounds. The new facilities upgrade the existing disposal practice for RMW to the minimum technology requirements of the Resource Conservation and Recovery Act. The proposed locations for the two facilities are: 218-E-10 for drag-off-waste packages and, 218-W-4C for non drag-off waste packages

  20. Hanford facility dangerous waste permit application, low-level burial grounds

    International Nuclear Information System (INIS)

    Engelmann, R.H.

    1997-01-01

    The Hanford Facility Dangerous Plaste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, 'operating' treatment, storage, and/or disposal units, such as the Low-Level Burial Grounds (this document, DOE/RL-88-20)

  1. Hanford facility dangerous waste permit application, low-level burial grounds

    Energy Technology Data Exchange (ETDEWEB)

    Engelmann, R.H.

    1997-08-12

    The Hanford Facility Dangerous Plaste Permit Application is considered to be a single application organized into a General Information Portion (document number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the Unit-Specific Portion is limited to Part B permit application documentation submitted for individual, `operating` treatment, storage, and/or disposal units, such as the Low-Level Burial Grounds (this document, DOE/RL-88-20).

  2. Nuclear Waste Fund fee adequacy: an assessment. Second annual report

    International Nuclear Information System (INIS)

    1984-07-01

    This is the second report of an annual series that evaluates whether the revenues collected from the waste disposal fees established under Section 302 of the Nuclear Waste Policy Act of 1982 (Public Law 97-425) are sufficient to offset the federal government's costs for the disposal of commercially generated spent nuclear fuel (SNF) and high-level radioactive waste. Nuclear wastes produced from defense activities are not considered in this report. The principal findings of this year's analysis are: The current 1.0 mill per kilowatt-hour (kWh) fee is projected to produce revenues sufficient to offset total system life cycle costs associated with the cases specified later in the report, assuming that the average annual rate of inflation does not exceed 2 to 3%. Higher average annual rates of inflation, or unanticipated real cost growth, would cause cumulative program costs to approach and then surpass cumulative revenues generated from the current 1.0 mill per kWh fee. Based on an analysis of different inflation rates and program cost growth projections discussed herein, indexing of the fee to correct for inflation would not need to begin until 1985, at the earliest, or perhaps as late as the year 2000. There is substantial uncertainty about both the program cost and revenue projections. However, more reliable data are expected to become available in the late 1980s as the program evolves from its present conceptual design phase to the engineering phase. Hence, any recommendation to raise the 1.0 mill per kWh fee before that time should be measured against the uncertainties that attend the present program. 4 references, 4 tables

  3. Basalt Waste Isolation Project. Annual report, fiscal year 1980

    Energy Technology Data Exchange (ETDEWEB)

    1980-11-01

    During this fiscal year the information available in the fields of geology and hydrology of the Columbia Plateau was consolidated and two reports were issued summarizing this information. In addition, the information on engineered barriers was consolidated and a report summarizing the research to date on waste package development and design of borehole seals was prepared. The waste package studies, when combined with the hydrologic integration, revealed that even under extreme disruptive conditions, a repository in basalt with appropriately designed waste packages can serve as an excellent barrier for containment of radionuclides for the long periods of time required for waste isolation. On July 1, 1980, the first two heater tests at the Near-Surface Test Facility were started and have been successfully operated to this date. The papers on the Near-Surface Test Facility section of this report present the results of the equipment installed and the preliminary results of the testing. In October 1979, the US Department of Energy selected the joint venture of Kaiser Engineers/Parsons Brinckerhoff Quade and Douglas, Inc., to be the architect-engineer to produce a conceptual design of a repository in basalt. During the year, this design has progressed and concept selection has now been completed. This annual report presents a summary of the highlights of the work completed during fiscal year 1980. It is intended to supplement and summarize the nearly 200 papers and reports that have been distributed to date as a part of the Basalt Waste Isolation Project studies.

  4. [Office of Civilian Radioactive Waste Management] 1992 annual capacity report

    International Nuclear Information System (INIS)

    1993-03-01

    The Standard Contract for Disposal of Spent Nuclear Radioactive Waste (10 CFR Part 961) requires the Department of Energy (DOE) to issue an Annual Capacity Report (ACR) for planning purposes. This report is the fifth in the series published by DOE. In March 1993, DOE published the 1992 Acceptance Priority Ranking (APR) that established the order in which DOE will allocate projected acceptance capacity. As required by the Standard Contract, the acceptance priority ranking is based on the date the spent nuclear fuel (SNF) was permanently discharged, with the owners of the oldest SNF, on an industry-wide basis, given thehighest priority. The 1992 ACR applies the projected waste acceptance rates in Table 2.1 to the 1992 APR, resulting in individual allocations for the owners and generators of the SNF. These allocations art, listed in detail in the Appendix, and summarized in Table 3.1. The projected waste acceptance rates for SNF presented in Table 2.1 assume a site for a Monitored Retrievable Storage (MRS) facility will tic obtained; the facility will initiate operations in 1998; and the statutory linkages between the MRS facility and the repository set forth in the Nuclear Waste Policy Act of 1982, as amended (NWPA), will be modified. During the first ten years following projected commencement of Civilian Radioactive Waste Management System (CRWMS) operation, the total quantity of SNF that could be accepted is projected to be 8200 metric tons of uranium (MTU). This is consistent with the storage capacity licensing conditions imposed on an MRS facility by the NWPA. The annual acceptance rates provide an approximation of the system throughput and are subject to change as the program progresses

  5. Office of Civilian Radioactive Waste Management annual capacity report

    International Nuclear Information System (INIS)

    1990-12-01

    The Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (10 CRF 961) requires the Department of Energy (DOE) to issue and Annual Capacity Report (ACR) for planning purposes. This report is currently scheduled to be the last in the series of ACRs to be published by DOE. The Standard Disposal Contract states that beginning in April 1991, DOE will publish the first annual Acceptance Priority Ranking report which will formally set forth the acceptance queue in which Purchasers will receive priority for allocation of the Waste Management System (WMS) acceptance capacity. This 1990 issue of the ACR utilizes two projected WMS waste acceptance schedules as the bases for allocation of acceptance capacity to the Purchasers for a 10-year period following the projected commencement of facility operations. The acceptance schedules were selected to be representative of upper and lower boundaries for a WMS which includes a Monitored Retrievable Storage (MRS) facility capable of receiving and storing SNF starting in 1998. 6 refs., 4 tabs

  6. Comparative overview of dangers, protective measures and risks for the final disposal of radioactive wastes

    International Nuclear Information System (INIS)

    1981-10-01

    The purpose of this report is to present an overview of the anticipated risks of geological disposal of radioactive wastes and to compare these to 'conventional' risks, which voluntarily or involuntarily are associated with human activities and have accompanied mankind for long times. Radioactive wastes which result from the generation of electricity by commercial nuclear reactors as well as those originating from research, industrial and medical applications necessitate prolonged isolation from the biosphere to their long-lived, although decaying, toxicity. Chapter 2 of this report contains a survey of the nature and extent of the potential hazard of radioactive waste, drawing attention to the fact that the toxicity of radionuclides is comparable to that of nonradioactive chemical compounds. The possibility of adverse effects on the public cannot be ruled out for either kind of waste. Current plans aim at the safe and effective disposal of radioactive wastes in deep and stable geological formations which should serve as hosts for engineered final repositories. For a final repository to be suitable, the site chosen should be free from circulating groundwater or the free movement of the groundwater must be strongly restricted. In order to prevent radioactive substances migrating away from the final repository in which they have been placed, it is planned to utilise natural and man-made barriers which function largely independently from each other. Thorough knowledge of the properties of man-made barriers, is as important as knowledge of the natural barriers, which are determined by the geology and hydrogeology of the site of the final repository. This principle of protection is known as a 'multiple-barrier concept' and is considered capable of providing safe disposal of radioactive wastes

  7. Logistic Problem Connected with Removing Asbestos as Dangerous Waste from Terrains of Country Communes

    Science.gov (United States)

    Parkitny, Waldemar; Wojcik, Weronika; Generowicz, Agnieszka

    2017-12-01

    Asbestos is a common term referring to certain mineral groups having the form of fibers with a length to fibre diameter of at least 100: 1. The specific properties of asbestos - flammability, mechanical strength and thermal and flexibility - meant that asbestos has been widely used in various types of industrial technologies. It is classified as hazardous waste and therefore requires special methods for collection, export and disposal. The article proposes a model of logistics exports of asbestos from selected villages, in order to guarantee the shortest route, while maintaining the ecological safety and the rules of transportation of hazardous waste.

  8. Waste Isolation Pilot Plant Annual Site Enviromental Report for 2008

    Energy Technology Data Exchange (ETDEWEB)

    Washington Regulatory and Enviromnetal Services

    2009-09-21

    The purpose of the Waste Isolation Pilot Plant Annual Site Environmental Report for 2008 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to characterize site environmental management performance; summarize environmental occurrences and responses reported during the calendar year; confirm compliance with environmental standards and requirements; highlight significant facility programs and efforts; and describe how compliance and environmental improvement is accomplished through the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the Waste Isolation Pilot Plant (WIPP). DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit (HWFP) Number NM4890139088-TSDF (treatment, storage, and disposal facility) further requires that the ASER be provided to the New Mexico Environment Department (NMED). The WIPP mission is to safely dispose of transuranic (TRU) radioactive waste generated by the production of nuclear weapons and other activities related to the national defense of the United States. In 2008, 5,265 cubic meters (m3) of TRU waste were disposed of at the WIPP facility, including 5,216 m3 of contact-handled (CH) TRU waste and 49 m3 of remote-handled (RH) TRU waste. From the first

  9. Waste Isolation Pilot Plant Annual Site Enviromental Report for 2008

    International Nuclear Information System (INIS)

    2009-01-01

    The purpose of the Waste Isolation Pilot Plant Annual Site Environmental Report for 2008 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to characterize site environmental management performance; summarize environmental occurrences and responses reported during the calendar year; confirm compliance with environmental standards and requirements; highlight significant facility programs and efforts; and describe how compliance and environmental improvement is accomplished through the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the Waste Isolation Pilot Plant (WIPP). DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit (HWFP) Number NM4890139088-TSDF (treatment, storage, and disposal facility) further requires that the ASER be provided to the New Mexico Environment Department (NMED). The WIPP mission is to safely dispose of transuranic (TRU) radioactive waste generated by the production of nuclear weapons and other activities related to the national defense of the United States. In 2008, 5,265 cubic meters (m3) of TRU waste were disposed of at the WIPP facility, including 5,216 m3 of contact-handled (CH) TRU waste and 49 m3 of remote-handled (RH) TRU waste. From the first

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

    International Nuclear Information System (INIS)

    1988-08-01

    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

  11. Office of Civilian Radioactive Waste Management annual capacity report

    International Nuclear Information System (INIS)

    1991-12-01

    The Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (10 CFR Part 961) requires the Department of Energy (DOE) to issue an Annual Capacity Report (ACR) for planning purposes. This report is the fourth in the series published by DOE. In December 1991, the Department published the 1991 Acceptance Priority Ranking (APR) that established the order in which the Department will allocate acceptance capacity. As required by the Standard Contract, the priority ranking for acceptance capacity is based on the date the spent nuclear fuel (SNF) was permanently discharged, with the owners of the oldest SNF, on an industry-wide basis, given the highest priority. The 1991 ACR applies the waste acceptance rates in the 1991 APR, resulting in individual Purchaser allocations. These allocations are listed and summarized. The projected waste acceptance rates for SNF presented assume: a site for a Monitored Retrievable Storage (MRS) facility will be obtained and the facility will be obtained and the facility will initiate operations in 1998; and the statutory schedule linkages between the MRS facility and the repository set forth in the Nuclear Waste Policy of 1982, as amended (NWPA) will be modified

  12. Waste Isolation Pilot Plant Annual Site Environmental Report for 2012

    Energy Technology Data Exchange (ETDEWEB)

    None

    2013-09-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2012 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: Characterize site environmental management performance; Summarize environmental occurrences and responses reported during the calendar year; Confirm compliance with environmental standards and requirements; Highlight significant environmental accomplishments, including progress toward the DOE Environmental Sustainability Goals made through implementation of the WIPP Environmental Management System (EMS).

  13. Transport of dangereous waste on the route to the pilot facility in Grenoble. Risk analysis. Final report

    International Nuclear Information System (INIS)

    Brenot, J.; Despres, A.; Degrange, J.P.; Hubert, Ph.; Pages, P.

    1988-12-01

    This document presents the results of a study performed by CEPN for INRETS upon request of the Department of Dangerous substances of the Ministry of Transport and department of Isere. The objective is risk analysis related to transport of dangerous substances on the part of road known as 'pilot route', which crosses the city and the valley of Isere at Point de Claix. First estimation of traffic was done based on counting the traffic especially done for the purpose of the study and data concerning economic activity of the region. Annual traffic amounts to 30 to 50 000 vehicles transporting dangerous substances along this route. Contrary to the usual data in France, petroleum products amount to at least half of the traffic, the second half are toxic liquids and corrosion agents. Liquid hydrocarbons (70 veh/day), other inflammable products (20 veh/day), GPLs (10 veh/day) and caustic soda (30 veh/day) are transported according to this study. Traffic has been estimated for other products like chlorine (0.5 veh/day), ammonia (1 veh/day) or gaseous hydrochloric acid (1 veh/day), which are less frequent but more dangerous. Before estimating the risk, it was necessary to identify the possible impacts. It is evident that human health (death or injuries) is the objective, factors less defined than environmental damage or economic losses. Level of analysis was then very different dependent on the cases: quantification taken for mortality, approach semi-quantificative for pollution effects, and identification of economic impacts. This difference is explained by the fact that for the first case complete methodology exists for many years, and for the latter two cases it is still necessary to formulate appropriate methodologies. In the frame of this analysis, it was shown that it is difficult to establish precise hierarchy of protection options. On one hand, study included a methodology aspect for taking into account pollution impacts, and on the other hand it is necessary to

  14. Law 16.867 International Agreement approve the Basilea amendment about the control of the transborder movement of the dangerous wastes and elimination

    International Nuclear Information System (INIS)

    1997-01-01

    Approve you the Amendment to the Agreement of Basile on the Control of the Transborder Movements of the Dangerous Waste and their Elimination, adopted by the Conference of the Parts, in their Third Meeting, taken place in Geneva-Switzerland - of the 18 at the 22 of September of 1995 [es

  15. Office of Civilian Radioactive Waste Management: Annual capacity report

    International Nuclear Information System (INIS)

    1987-06-01

    The system configuration used as the basis for this report is defined in the Mission Plan Amendment. It includes a Monitored Retrievable Storage (MRS) facility as an integral system component. During the first 10 years of WMS operation, the total quantity of spent fuel that could be accepted is 18,600 metric tons uranium (MTU). By starting WMS operations in 1998, the MRS facility could accept 6000 MTU of spent fuel by the time repository operations are projected to begin in 2003. The allocation of acceptance right is currently based on the projected annual capacity of the waste management system to receive SNF and the age of permanently discharged spent fuel. The allocations are based on the oldest fuel having the highest priority. Section 1.0 provides a discussion of the requirement for the (ACR) and the role the ACR will play in DOE's interaction with the Purchasers in implementing the provisions of the Standard Disposal Contract. The currently projected annual acceptance capacity to be allocated is discussed and presented in Section 2.0. Section 3.0 discusses the procedure and basis for allocation of this capacity (acceptance rights). Allocation will be based on the chronological listing of spent fuel assemblies and equivalent MTU. Some of the contingencies which may have an impact on Contract implementation and system operation considerations which could affect the projected annual capacity and its allocation are identified in Section 4.0. 4 refs., 11 tabs

  16. RCRA Permit for a Hazardous Waste Management Facility, Permit Number NEV HW0101, Annual Summary/Waste Minimization Report

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, Patrick [NSTec

    2014-02-14

    This report summarizes the EPA identification number of each generator from which the Permittee received a waste stream, a description and quantity of each waste stream in tons and cubic feet received at the facility, the method of treatment, storage, and/or disposal for each waste stream, a description of the waste minimization efforts undertaken, a description of the changes in volume and toxicity of waste actually received, any unusual occurrences, and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101.

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

    International Nuclear Information System (INIS)

    1986-03-01

    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

  18. Waste Isolation Pilot Plant Annual Site Environmental Report for 2016

    Energy Technology Data Exchange (ETDEWEB)

    Ward, Anderson [Carlsbad Field Office (CBFO), NM (United States); Basabilvazo, George T. [Carlsbad Field Office (CBFO), NM (United States)

    2017-09-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2016 (ASER) is to provide the information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC) maintain and preserve the environmental resources at the WIPP facility. DOE Order 231.1B; DOE Order 436.1, Departmental Sustainability; and DOE Order 458.1, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1B, which requires DOE facilities to submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer.

  19. Waste Isolation Pilot Plant Annual Site Environmental Report for 2010

    Energy Technology Data Exchange (ETDEWEB)

    None

    2011-09-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2010 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: (1) Characterize site environmental management performance. (2) Summarize environmental occurrences and responses reported during the calendar year. (3) Confirm compliance with environmental standards and requirements. (4) Highlight significant environmental accomplishments, including progress toward the DOE Environmental Sustainability Goals made through implementation of the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the WIPP. DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit Number NM4890139088-TSDF (Permit) further requires that the ASER be provided to the New Mexico Environment Department (NMED).

  20. Waste Isolation Pilot Plant Annual Site Environmental Report for 2010

    International Nuclear Information System (INIS)

    2011-01-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2010 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1A, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: (1) Characterize site environmental management performance. (2) Summarize environmental occurrences and responses reported during the calendar year. (3) Confirm compliance with environmental standards and requirements. (4) Highlight significant environmental accomplishments, including progress toward the DOE Environmental Sustainability Goals made through implementation of the WIPP Environmental Management System (EMS). The DOE Carlsbad Field Office (CBFO) and the management and operating contractor (MOC), Washington TRU Solutions LLC (WTS), maintain and preserve the environmental resources at the WIPP. DOE Order 231.1A; DOE Order 450.1A, Environmental Protection Program; and DOE Order 5400.5, Radiation Protection of the Public and the Environment, require that the affected environment at and near DOE facilities be monitored to ensure the safety and health of the public and workers, and preservation of the environment. This report was prepared in accordance with DOE Order 231.1A, which requires that DOE facilities submit an ASER to the DOE Headquarters Chief Health, Safety, and Security Officer. The WIPP Hazardous Waste Facility Permit Number NM4890139088-TSDF (Permit) further requires that the ASER be provided to the New Mexico Environment Department (NMED).

  1. Liquid and Gaseous Waste Operations Department annual operating report CY 1996

    International Nuclear Information System (INIS)

    Maddox, J.J.; Scott, C.B.

    1997-03-01

    This annual report summarizes operating activities dealing with the process waste system, the liquid low-level waste system, and the gaseous waste system. It also describes upgrade activities dealing with the process and liquid low-level waste systems, the cathodic protection system, a stack ventilation system, and configuration control. Maintenance activities are described dealing with nonradiological wastewater treatment plant, process waste treatment plant and collection system, liquid low-level waste system, and gaseous waste system. Miscellaneous activities include training, audits/reviews/tours, and environmental restoration support

  2. 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.

  3. Sandia National Laboratories California Waste Management Program Annual Report April 2011

    Energy Technology Data Exchange (ETDEWEB)

    Brynildson, Mark E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2011-04-01

    The annual program report provides detailed information about all aspects of the Sandia National Laboratories, California (SNL/CA) Waste Management Program. It functions as supporting documentation to the SNL/CA Environmental Management System Program Manual. This annual program report describes the activities undertaken during the past year, and activities planned in future years to implement the Waste Management (WM) Program, one of six programs that supports environmental management at SNL/CA.

  4. Sandia National Laboratories California Waste Management Program Annual Report February 2008.

    Energy Technology Data Exchange (ETDEWEB)

    Brynildson, Mark E.

    2008-02-01

    The annual program report provides detailed information about all aspects of the Sandia National Laboratories, California (SNL/CA) Waste Management Program. It functions as supporting documentation to the SNL/CA Environmental Management System Program Manual. This annual program report describes the activities undertaken during the past year, and activities planned in future years to implement the Waste Management (WM) Program, one of six programs that supports environmental management at SNL/CA.

  5. Sandia National Laboratories, California Waste Management Program annual report : February 2009.

    Energy Technology Data Exchange (ETDEWEB)

    Brynildson, Mark E.

    2009-02-01

    The annual program report provides detailed information about all aspects of the Sandia National Laboratories, California (SNL/CA) Waste Management Program. It functions as supporting documentation to the SNL/CA Environmental Management System rogram Manual. This annual program report describes the activities undertaken during the past year, and activities planned in future years to implement the Waste Management (WM) Program, one of six programs that supports environmental management at SNL/CA.

  6. Institute for Nuclear Waste Disposal. Annual Report 2009

    International Nuclear Information System (INIS)

    Geckeis, H.; Stumpf, T.

    2010-01-01

    On October 01, 2009, the Karlsruhe Institute of Technology (KIT) was founded by a merger of Forschungszentrum Karlsruhe and Universitaet Karlsruhe (TH). KIT bundles the missions of both precursory institutions: a university of the state of Baden- Wuerttemberg with teaching and research tasks and a large-scale research institution of the Helmholtz Association conducting program-oriented provident research on behalf of the Federal Republic of Germany. Within these missions, KIT is operating along the three strategic fields of action, research, teaching, and innovation. With about 8000 employees and an annual budget of about EUR 700 million, KIT is one of the largest research and teaching institutions worldwide. It has the potential to assume a top position worldwide in selected fields of research. The objective: KIT will become an institution of excellent research and scientific education, as well as a prominent location of academic life, life-long learning, comprehensive advanced training, unrestricted exchange of know-how and sustainable innovation culture. The largest organizational units of KIT are the KIT Centers. They focus on problems of fundamental importance to the existence and further development of our society or on key issues of basic science. KIT Centers are characterized by the uniqueness of their scientific approach, their strategic objective and mission and by a long-term perspective. The Institut fuer Nukleare Entsorgung, INE, (Institute for Nuclear Waste Disposal) belongs to the KIT Energy Center. The KIT Energy Center comprises some 40 institutes of the Universitaet Karlsruhe (TH) and 18 large institutes of the Forschungszentrum Karlsruhe with, at present, a total of approx. 1100 staff members. The participating institutes and research groups are the operating research units. An interdisciplinary KIT School of Energy establishes ideal framework conditions for teaching. For external partners from industry, the KIT Center develops solutions in

  7. Effect of quantity and composition of waste on the prediction of annual methane potential from landfills.

    Science.gov (United States)

    Cho, Han Sang; Moon, Hee Sun; Kim, Jae Young

    2012-04-01

    A study was conducted to investigate the effect of waste composition change on the methane production in landfills. An empirical equation for the methane potential of the mixed waste is derived based on the methane potential values of individual waste components and the compositional ratio of waste components. A correction factor was introduced in the equation and was determined from the BMP and lysimeter tests. The equation and LandGEM were applied for a full size landfill and the annual methane potential was estimated. Results showed that the changes in quantity of waste affected the annual methane potential from the landfill more than the changes of waste composition. Copyright © 2012 Elsevier Ltd. All rights reserved.

  8. Waste form development program. Annual report, October 1982-September 1983

    International Nuclear Information System (INIS)

    Colombo, P.; Kalb, P.D.; Fuhrmann, M.

    1983-09-01

    This report provides a summary of the work conducted for the Waste Form Development/Test Program at Brookhaven National Laboratory in FY 1983 under the sponsorship of the US Department of Energy's Low-Level Waste Management Program. The primary focus of this work is the investigation of new solidification agents which will provide improved immobilization of low-level radioactive wastes in an efficient, cost-effective manner. A working set of preliminary waste form evaluation criteria which could impact upon the movement of radionuclides in the disposal environment was developed. The selection of potential solidification agents for further investigation is described. Two thermoplastic materials, low-density polyethylene and a modified sulfur cement were chosen as primary candidates for further study. Three waste types were selected for solidification process development and waste form property evaluation studies which represent both new volume reduction wastes (dried evaporator concentrates and incinerator ash) and current problem wastes (ion exchange resins). Preliminary process development scoping studies were conducted to verify the compatibility of selected solidification agents and waste types and the potential for improved solidification. Waste loadings of 60 wt % Na 2 SO 4 , 25 wt % H 3 BO 3 , 25 wt % incinerator ash and 50 wt % dry ion exchange resin were achieved using low density polyethylene as a matrix material. Samples incorporating 65 wt % Na 2 SO 4 , 40 wt % H 3 BO 3 , 20 wt % incinerator ash and 40 wt % dry ion exchange resin were successfully solidified in modified sulfur cement. Additional improvements are expected for both matrix materials as process parameters are optimized. Several preliminary property evaluation studies were performed to provide the basis for an initial assessment of waste form acceptability. These included a two-week water immersion test and compressive load testing

  9. Special waste form lysimeters-arid. Annual report, 1985

    International Nuclear Information System (INIS)

    Walter, M.B.; Graham, M.J.

    1985-09-01

    The Special Waste Form Lysimeters-Arid program was initiated to determine typical source terms generated by commercial solidified low-level nuclear waste in an arid climate. Waste-form leaching tests are being conducted at a field facility at the Hanford site near Richland, Washington. A similar program is being conducted at a humid site. The field facility consists of 10 lysimeters placed around a central instrument caisson. The waste samples from boiling water and pressurized water reactors were emplaced in 1984, and the lysimeters are being monitored for movement of contaminants and water. Solidifying agents being tested include vinyl ester-styrene, bitumen, and cement. Laboratory leaching and geochemical modeling studies are being conducted to predict expected leach rates at the field site and to aid field-data interpretation. Small samples of the solidified waste forms were made for use in the laboratory leaching studies that include standard leach tests and leaching of solidified waste forms in soil columns. Complete chemical and radionuclide analyses are being conducted on the solid and liquid portions of the wastes. 2 refs

  10. DANGEROUS EXERCISES

    OpenAIRE

    Hassan Daneshmandi

    2011-01-01

    Research has shown that many exercises are contraindicated and may do more harm thanbenefits. Many of the warm-up exercises we practiced each day have now found to be dangerous.While different levels of athletics do have different levels of stretching; it is necessary to knowwhat the dangerous exercises are and how to use safer alternatives. Certain exercises are toorisky and should not be performed at all. Exercises must be performed in certain ways and ifperformed incorrectly can cause inju...

  11. Annual Waste Minimization Summary Report, Calendar Year 2008

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2009-02-01

    This report summarizes the waste minimization efforts undertaken by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during calendar year 2008.

  12. Hazardous Waste Remedial Actions Program annual progress report, FY 1990

    Energy Technology Data Exchange (ETDEWEB)

    1990-12-01

    The Hazardous Waste Remedial Actions Programs (HAZWRAP), a unit of Martin Marietta Energy Systems, Inc., supports the Department of Energy (DOE) Oak Ridge Operations Office in broadly environmental areas, especially those relating to waste management and environmental restoration. HAZWRAP comprises six program areas, which are supported by central administrative and technical organizations. Existing programs deal with airborne hazardous substances, pollution prevention, remedial actions planning, environmental restoration, technology development, and information and data systems. HAZWRAP's mission to develop, promote, and apply-cost-effective hazardous waste management and environmental technologies to help solve national problems and concerns. HAZWRAP seeks to serve as integrator for hazardous waste and materials management across the federal government. It applies the unique combination of research and development (R D) capabilities, technologies, management expertise, and facilities in the Energy Systems complex to address problems of national importance. 24 figs., 10 tabs.

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

    International Nuclear Information System (INIS)

    1987-04-01

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

  14. Annual Waste Minimization Summary Report, Calendar Year 2008

    International Nuclear Information System (INIS)

    2009-01-01

    This report summarizes the waste minimization efforts undertaken by National Security Technologies, LLC (NSTec), for the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during calendar year 2008. This report was developed in accordance with the requirements of the Nevada Test Site (NTS) Resource Conservation and Recovery Act (RCRA) Permit (No. NEV HW0021), and as clarified in a letter dated April 21, 1995, from Paul Liebendorfer of the Nevada Division of Environmental Protection to Donald Elle of the U.S. Department of Energy, Nevada Operations Office. The NNSA/NSO Pollution Prevention (P2) Program establishes a process to reduce the volume and toxicity of waste generated by NNSA/NSO activities and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment. The following information provides an overview of the P2 Program, major P2 accomplishments during the reporting year, a comparison of the current year waste generation to prior years, and a description of efforts undertaken during the year to reduce the volume and toxicity of waste generated by the NNSA/NSO

  15. Annual Waste Minimization Summary Report, Calendar Year 2009

    International Nuclear Information System (INIS)

    2010-01-01

    This report summarizes the waste minimization efforts undertaken by National Security Technologies, LLC, for the U. S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during calendar year 2009. This report was developed in accordance with the requirements of the Nevada Test Site Resource Conservation and Recovery Act Permit (No. NEV HW0021), and as clarified in a letter dated April 21, 1995, from Paul Liebendorfer of the Nevada Division of Environmental Protection to Donald Elle of the U.S. Department of Energy, Nevada Operations Office. The NNSA/NSO Pollution Prevention (P2) Program establishes a process to reduce the volume and toxicity of waste generated by NNSA/NSO activities and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment. The following information provides an overview of the P2 Program, major P2 accomplishments during the reporting year, a comparison of the current year waste generation to prior years, and a description of efforts undertaken during the year to reduce the volume and toxicity of waste generated by NNSA/NSO.

  16. Waste package environment studies. FY 1984 annual report

    International Nuclear Information System (INIS)

    Pederson, L.R.; Gray, W.J.; Hodges, F.N.; McVay, G.L.; Moore, D.A.; Rai, D.; Schramke, J.A.

    1986-03-01

    Tests were conducted by Pacific Northwest Laboratory in FY 1984 to examine the influence of heat and radiation on the chemical environment of a high-level nuclear waste package in a repository in salt and to determine the solubility of key radionuclides in site-specific brines. These tests are part of an ongoing effort by the Waste Package Program, whose objective is to help develop a data base on package components and system interactions necessary to qualify a nuclear waste package for geologic disposal. Specifically, tests performed in FY 1984 involved alpha and gamma radiolysis of brines, americium solubility in brines, the influence of heat and radiation on rock salt, and the influence of temperature on brine chemistry

  17. Annual report of waste generation and pollution prevention progress 2000 [USDOE] [9th edition

    International Nuclear Information System (INIS)

    None

    2001-01-01

    This ninth edition of the Annual Report of Waste Generation and Pollution Prevention Progress highlights waste reduction, pollution prevention accomplishments, and cost savings/avoidance for the U.S. Department of Energy (DOE) Pollution Prevention Program for Fiscal Year 2000. This edition marks the first time that progress toward meeting the 2005 Pollution Prevention Goals, issued by the Secretary of Energy in November 1999, is being reported. In addition, the Annual Report has a new format, and now contains information on a fiscal year basis, which is consistent with other DOE reports

  18. Annual report of waste generation and pollution prevention progress 2000 [USDOE] [9th edition

    Energy Technology Data Exchange (ETDEWEB)

    None

    2001-06-01

    This ninth edition of the Annual Report of Waste Generation and Pollution Prevention Progress highlights waste reduction, pollution prevention accomplishments, and cost savings/avoidance for the U.S. Department of Energy (DOE) Pollution Prevention Program for Fiscal Year 2000. This edition marks the first time that progress toward meeting the 2005 Pollution Prevention Goals, issued by the Secretary of Energy in November 1999, is being reported. In addition, the Annual Report has a new format, and now contains information on a fiscal year basis, which is consistent with other DOE reports.

  19. Fourth annual report of the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

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

    1982-12-01

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

  20. Second annual report of the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Boulton, J.

    1980-12-01

    This report, the second of a series of annual reports, reviews in general terms the progress which has been achieved in the research and development program for the safe, permanent disposal of Canada's nuclear fuel wastes. The report summarizes activities over the past year, in the areas of public interaction, used fuel storage and transportation, immobilization of used fuel and fuel reprocessing wastes, research and development associated with deep underground disposal, and environmental and safety assessment. (auth)

  1. Third annual report of the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

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

    1981-12-01

    This report, the third of a series of annual reports, reviews the progress that has been made in the research and development program for the safe management and disposal of Canada's nuclear fuel wastes. The report summarizes activities over the past year, in the areas of public interaction, irradiated fuel storage and transportation, immobilization of irradiated fuel and fuel recycle wastes, research and development associated with deep underground disposal, and environmental and safety assessment

  2. The NOx system in nuclear waste. 1998 annual progress report

    International Nuclear Information System (INIS)

    Camaioni, D.; Meisel, D.

    1998-01-01

    'The objective of this project is to assist EM sites in the resolution of outstanding safety issues involved in the temporary storage of high-level waste (HLW) in large tanks. To achieve this objective, mechanisms of the radiolytic and radiolytically induced processes that occur in the waste are quantitatively studied. The information is incorporated into a computer modeling of the tanks chemistry under various scenarios and the predicted results are rapidly conveyed to the site operators. This report summarizes the technical achievements of a 3-year project that is now in its 2nd year of operation. The project is a collaborative effort between the ANL and PNNL and is strongly coupled to another EMSP project (''Interfacial Radiolysis Effects in Tank Waste Speciation'''' PI: T. Orlando, PNNL) and to the safety programs at the Hanford site (''Organic Tanks Safety Program: Waste Aging Studies'''', PI D. Camaioni, PNNL). Information from the project is also shared directly with Westinghouse Savannah River personnel. In general, the basic studies are performed at ANL and PNNL and the information is continuously shared with Tanks Safety Programs. To further facilitate the exchange of information and the immediate incorporation of results into operations, the authors conducted at least twice a year coordination meetings at the various laboratories where the site operators (e.g. from DE and SH, Numatec, WSRC, etc.) participate, both to present their needs and to obtain updated information.'

  3. Basalt Waste Isolation Project. Annual report, fiscal year 1979

    Energy Technology Data Exchange (ETDEWEB)

    1979-11-01

    This project is aimed at examining the feasibility and providing the technology to design and construct a radwaste repository in basalt formations beneath and within the Hanford Site. The project is divided into seven areas: systems integration, geosciences, hydrologic studies, engineered barriers, near-surface test facility, engineering testing, and repository engineering. This annual report summarizes key investigations in these seven areas. (DLC)

  4. Basalt Waste Isolation Project. Annual report, fiscal year 1979

    International Nuclear Information System (INIS)

    1979-11-01

    This project is aimed at examining the feasibility and providing the technology to design and construct a radwaste repository in basalt formations beneath and within the Hanford Site. The project is divided into seven areas: systems integration, geosciences, hydrologic studies, engineered barriers, near-surface test facility, engineering testing, and repository engineering. This annual report summarizes key investigations in these seven areas

  5. Northeast Waste Management Enterprise (NEWME) 1996 annual/final report

    International Nuclear Information System (INIS)

    Goland, A.; Kaplan, E.; Palmedo, P. Wortman, J.

    1997-01-01

    The Northeast Waste Management Enterprise was created in response to Dr. Clyde Frank's vision of a new partnership between research, industrial, and financial sectors, with the goal of speeding development and use (particularly at U.S. Department of Energy [DOE] facilities) of environmental remediation technologies. It was anticipated that this partnership would also strengthen the international competitiveness of the U.S. environmental industry. Brookhaven National Laboratory's (BNL) response to Dr. Frank was a proposal to create the Northeast Waste Management Alliance, later renamed the Northeast Waste Management Enterprise (NEWME). Recognizing the need to supplement its own technical expertise with acumen in business, financial management, and venture capital development, BNL joined forces with the Long Island Research Institute (LIRI). Since its inception at the end of FY 1993, NEWME has achieved several significant accomplishments in pursuing its original business and strategic plans. However, its successes have been constrained by a fundamental mismatch between the time scales required for technology commercialization, and the immediate need for available environmental technologies of those involved with ongoing environmental remediations at DOE facilities

  6. Radiation effects in nuclear waste materials. 1997 annual progress report

    Energy Technology Data Exchange (ETDEWEB)

    Weber, W.J.; Corrales, L.R.

    1997-06-01

    'The objective of this multidisciplinary, multi-institutional research effort is to develop a fundamental understanding at the atomic, microscopic, and macroscopic levels of radiation effects in glass and ceramics. This research will provide the underpinning science and models for evaluation and performance assessments of glass and ceramic waste forms for the immobilization and disposal of high-level tank waste, plutonium residues and scrap, and excess weapons plutonium. Studies will focus on the effects of ionization and elastic collision interactions on defect production, defect interactions, diffusion, solid-state phase transformations, and gas accumulation using actinide-containing materials, gamma irradiation, ion-beam irradiation, and electron-beam irradiation to simulate the effects of a-decay and p-decay on nuclear waste glasses and ceramics. This program will exploit a variety of structural, optical, and spectroscopic probes to characterize the nature and behavior of the defects, defect aggregates, and phase transforma-tions. Computer simulation techniques will be used to determine defect production, calculate defect stability, defect energies, damage processes within an a-recoil cascade, and defect/gas diffusion and interactions. A number of irradiation facilities and capabilities will be used, including user facilities at several national laboratories, to study the effects of irradiation under different conditions.'

  7. Northeast Waste Management Alliance (NEWMA). Annual report FY 1993

    Energy Technology Data Exchange (ETDEWEB)

    Goland, A.N.; Kaplan, E.

    1993-11-01

    Funding was provided to Brookhaven National Laboratory in the fourth quarter of FY93 to establish a regional alliance as defined by Dr. Clyde Frank during his visit to BNL on March 7, 1993. In collaboration with the Long Island Research Institute (LIRI), BNL developed a business plan for the Northeast Waste Management Alliance (NEWMA). Concurrently, informal discussions were initiated with representatives of the waste management industry, and meetings were held with local and state regulatory and governmental personnel to obtain their enthusiasm and involvement. A subcontract to LIRI was written to enable it to formalize interactions with companies offering new waste management technologies selected for their dual value to the DOE and local governments in the Northeast. LIRI was founded to develop and coordinate economic growth via introduction of new technologies. As a not-for-profit institution it is in an ideal position to manage the development of NEWMA through ready access to venture capital and strong interactions with the business community, universities, and BNL. Another subcontract was written with a professor at SUNY/Stony Brook to perform an evaluation of new pyrolitic processes, some of which may be appropriate for development by NEWMA. Independent endorsement of the business plan recently by another organization, GETF, with broad knowledge of DOE/EM-50 objectives, provides a further incentive for moving rapidly to implement the NEWMA strategy. This report describes progress made during the last quarter of FY93.

  8. Annual plan of research on safety techniques against low level radioactive wastes, FY1994-FY1999

    International Nuclear Information System (INIS)

    1994-01-01

    The safety research on the disposal of low level radioactive waste has been promoted based on the annual plan decided by the committee on radiative waste safety regulation of the Nuclear Safety Commission. Hereafter, the disposal of low level radioactive waste in ocean is never selected. As to the subjects of the safety research which should be carried out for five years from 1994, the necessity, the contents of research, the organs that carry out the research and so on were deliberated, and the results are made into the annual plan, therefore, it is reported. The way of thinking on the safety research, the contents for which efforts should be exerted as the safety research, and the matters to which attention should be paid are shown. As for the annual plan of safety research, the necessity and the outline of the safety research on the disposal in strata, the concrete subjects and their contents, and the necessity and the outline of the safety research on the reuse, the concrete subjects and their contents are reported. The radioactive waste is those produced by the operation of nuclear reactor facilities, those containing TRU nuclides and RI waste. (K.I.)

  9. Radiation effects on medium active waste forms. Annual report - 1988

    International Nuclear Information System (INIS)

    Johnson, D.; Wilding, C.; Lyon, C.

    1989-01-01

    Work has continued on measurements of dimensional changes, strength, and gas evolution on samples of several simulated waste forms under accelerated γ and α irradiation conditions. Samples of RMA5 (mixed ion exchangers in modified vinylester polymer) and RMA10 (incinerated PCM materials in cement) maintain their integrity during irradiation but samples of RMA3 (organic ion exchangers in cement) and RMA11.1 (mixed PCM materials in cement) swell and eventually disintegrate under some γ irradiation conditions. Disintegration of RMA3 samples occurred when samples were γ irradiated whilst immersed in water. Samples of RMA11.1 which cannot rapidly dry out swell, sometimes substantially, during γ irradiation. The principal gases of interest in gas evolution experiments are hydrogen and oxygen. Hydrogen is evolved under all circumstances but oxygen evolution does not always occur. Samples of RMA10 evolve oxygen when α irradiated in an inert atmosphere but oxygen concentration initially falls during α irradiation in air atmosphere. Samples of RMA11.1 absorb oxygen from an air atmosphere during both α and γ irradiation. A comparison has been carried out of the effects of γ and α irradiation on identical cement grouts using BFS/OPC mixes produced under high shear mixing conditions. In contrast to earlier results on such systems, no γ irradiated samples showed physical deterioration after irradiation to 9 MGy but the a irradiated samples all showed surface cracks after about 1 MGy. The gas evolution measurements showed that during α irradiation oxygen evolution commenced after a dose of ∼ 1 MGy whereas oxygen was completely removed from the atmosphere γ irradiation. Hydrogen was evolved under all conditions and the rate of production was found to be dependent upon the dose rate. More hydrogen was evolved during α irradiations than during γ irradiation. A technique for the measurement of hydrogen permeability through cement systems has been further developed

  10. Contesting danger

    DEFF Research Database (Denmark)

    Heathershaw, John; Megoran, Nick

    2011-01-01

    , the activities of international aid agencies and numerous lurid films, documentaries and novels. The article first establishes the tradition of inscribing danger to Central Asia, in both academic and policy discourse, from the colonial experience of the nineteenth century through to the post-Soviet transition......Western geopolitical discourse misrepresents and constructs Central Asia as an inherently and essentially dangerous place. This pervasive ‘discourse of danger’ obscures knowledge of the region, deforms scholarship and, because it has policy implications, actually endangers Central Asia....... This article identifies how the region is made knowable to a US–UK audience through three mutually reinforcing dimensions of endangerment: Central Asia as obscure, oriental, and fractious. This is evidenced in the writings of conflict resolution and security analysts, the practices of governments...

  11. RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report - Calendar Year 2014

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, Patrick [National Security Technologies, LLC, Mercury, NV (United States)

    2015-02-17

    This report summarizes the EPA identification number of each generator from which the Permittee received a waste stream, a description and quantity of each waste stream in tons and cubic feet received at the facility, the method of treatment, storage, and/or disposal for each waste stream, a description of the waste minimization efforts undertaken, a description of the changes in volume and toxicity of waste actually received, any unusual occurrences, and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101.

  12. RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report Calendar Year 2012, Nevada National Security Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Arnold, P. M.

    2013-02-21

    This report summarizes the U.S. Environmental Protection Agency (EPA) identification number of each generator from which the Permittee received a waste stream, a description and quantity of each waste stream in tons and cubic feet received at the facility, the method of treatment, storage, and/or disposal for each waste stream, a description of the waste minimization efforts undertaken, a description of the changes in volume and toxicity of waste actually received, any unusual occurrences, and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101, issued 10/17/10.

  13. RCRA Permit for a Hazardous Waste Management Facility Permit Number NEV HW0101 Annual Summary/Waste Minimization Report Calendar Year 2011

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Restoration

    2012-02-16

    This report summarizes the U.S. Environmental Protection Agency (EPA) identification number of each generator from which the Permittee received a waste stream; a description and quantity of each waste stream in tons and cubic feet received at the facility; the method of treatment, storage, and/or disposal for each waste stream; a description of the waste minimization efforts undertaken; a description of the changes in volume and toxicity of waste actually received; any unusual occurrences; and the results of tank integrity assessments. This Annual Summary/Waste Minimization Report is prepared in accordance with Section 2.13.3 of Permit Number NEV HW0101.

  14. Proceedings of the Third Annual Information Meeting DOE Low-Level Waste-Management Program

    International Nuclear Information System (INIS)

    Large, D.E.; Lowrie, R.S.; Stratton, L.E.; Jacobs, D.G.

    1981-12-01

    The Third Annual Participants Information Meeting of the Low-Level Waste Management Program was held in New Orleans, Louisiana, November 4-6, 1981 The specific purpose was to bring together appropriate representatives of industry, USNRC, program management, participating field offices, and contractors to: (1) exchange information and analyze program needs, and (2) involve participants in planning, developing and implementing technology for low-level waste management. One hundred seven registrants participated in the meeting. Presentation and workshop findings are included in these proceedings under the following headings: low-level waste activities; waste treatment; shallow land burial; remedial action; greater confinement; ORNL reports; panel workshops; and summary. Forty-six papers have been abstracted and indexed for the data base

  15. Proceedings of the Third Annual Information Meeting DOE Low-Level Waste-Management Program

    Energy Technology Data Exchange (ETDEWEB)

    Large, D.E.; Lowrie, R.S.; Stratton, L.E.; Jacobs, D.G. (comps.)

    1981-12-01

    The Third Annual Participants Information Meeting of the Low-Level Waste Management Program was held in New Orleans, Louisiana, November 4-6, 1981 The specific purpose was to bring together appropriate representatives of industry, USNRC, program management, participating field offices, and contractors to: (1) exchange information and analyze program needs, and (2) involve participants in planning, developing and implementing technology for low-level waste management. One hundred seven registrants participated in the meeting. Presentation and workshop findings are included in these proceedings under the following headings: low-level waste activities; waste treatment; shallow land burial; remedial action; greater confinement; ORNL reports; panel workshops; and summary. Forty-six papers have been abstracted and indexed for the data base.

  16. Fourteenth annual U.S. Department of Energy low-level radioactive waste management conference: Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-03-01

    This document contains 69 papers that were presented at the Fourteenth Annual U.S. Department of Energy Low-Level Radioactive Waste Management Conference, November 18--20, 1992, in Phoenix, Arizona. The papers address the following general topics: (a) Performance Management Track: risk assessment; waste characterization; site characterization; facility design; groundwater modeling; monitoring and modeling; and regulatory requirements; (b) Technical Track: waste minimization; new technologies; international perspectives; licensing issues; hot topics; commercial storage; DOE storage; treatment technologies; and mixed waste; and (c) Institutional Track: status report; changes in orders, regulations, and guidance; regulatory compliance issues; communicating risk; hot topics; and storage impacts. Papers have been processed separately for inclusion on the data base.

  17. Advanced waste forms research and development. Annual report

    International Nuclear Information System (INIS)

    McCarthy, G.J.

    1976-01-01

    Thermogravimetric analysis on cesium aluminosilicates was performed. Pollucite, CsAlSi 2 O 6 , appears to have more than adequate thermal stability for Cs fixation in supercalcine. The possibility of leaving Ru as RuO 2 during supercalcine crystallization is being assessed. The apatite solid solution [A/sub ss/] phases used in supercalcine phase formation models have been easily prepared as pure phases. Use of Ca instead of Sr as an alkaline earth additive yields a more stable A/sub ss/ phase. Weight ratios have been optimized for two firing temperatures in terms of soxhlet leachability. However, this is not the preferred approach to supercalcine consolidation. The phase formation models developed for PW-4b-type wastes were routinely applied to PW-7, in spite of several significant composition differences in the latter. Uranium oxide remains as a fluorite structure oxide after supercalcine crystallization, but it does seem to have incorporated either or both CeO 2 or ZrO 2 . Characterization of this F/sub ss/ phase will require further study. Based on observations during several complex compatibility studies, it appears that good overall thermal stability at as high as 1200 0 C might be attainable for nepheline based supercalcine formulations. A thorough literature review of the oxide crystal chemistry of Te has been completed

  18. First annual report of the Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Boulton, J.; Gibson, A.R.

    1979-12-01

    The research and development program for the safe, permanent disposal of Canada's nuclear fuel wastes has been established. This report, the first of a series of annual reports, reviews in general terms the progress which has been achieved. After briefly reviewing the rationale and organization of the program, the report summarizes activities in the area of public information, used fuel storage and transportation, immobilization of used fuel and fuel reprocessing wastes, research and development associated with deep underground disposal, and environmental and safety assessment. (auth) [fr

  19. Environmental surveillance for the INEL radioactive waste management complex. Annual report, 1979

    International Nuclear Information System (INIS)

    Wickham, L.E.; Janke, D.H.

    1980-12-01

    This document is the 1979 annual environmental surveillance report for the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory. Included are tabulated data from and discussions about routine radiological monitoring of atmospheric, hydrologic, geologic, and biotic environments of the RWMC. Also included are discussions of selected nonradiological pollutants (e.g., sodium, etc.). It is concluded that (a) RWMC operations have not adversely affected local, existing environments; (b) environmental conditions within the Transuranic Storage Area are not corrosive enough to adversely affect transuranic waste storage containers, and (c) the addition of lakebed soil to pit, trench, and soil test plot areas has altered the moisture cycle characteristic of RWMC soil

  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)

    None

    2000-01-01

    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

  2. Microbial degradation of low-level radioactive waste. Volume 2, Annual report for FY 1994

    International Nuclear Information System (INIS)

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

    1995-08-01

    The Nuclear Regulatory Commission stipulates in 10 CFR 61 that disposed low-level radioactive waste (LLW) be stabilized. To provide guidance to disposal vendors and nuclear station waste generators for implementing those requirements, the NRC developed the Technical Position on Waste Form, Revision 1. That document details a specified set of recommended testing procedures and criteria, including several tests for determining the biodegradation properties of waste forms. Cement has been widely used to solidify LLW; however, the resulting waste forms are sometimes susceptible to failure due to the actions of waste constituents, stress, and environment. The purpose of this research program is to develop modified microbial degradation test procedures that will be more appropriate than the existing procedures for evaluating the effects of microbiologically influenced chemical attack on cement-solidified LLW. Groups of microorganisms indigenous to LLW disposal sites are being employed that can metabolically convert organic and inorganic substrates into organic and mineral acids. Such acids aggressively react with cement and can ultimately lead to structural failure. Results over the past year on the application of mechanisms inherent in microbially influenced degradation of cement-based material are the focus of the annual report. Data-validated evidence of the potential for microbially influenced deterioration of cement-solidified LLW and subsequent release of radionuclides has been developed during this study

  3. Proceedings of the seventh annual participants' information meeting. DOE Low-Level Waste Management Program

    International Nuclear Information System (INIS)

    1986-02-01

    The Seventh Annual Department of Energy (DOE) Low-Level Waste Management Program (LLWMP) Participants' Information Meeting was held September 10-13, 1985 in Las Vegas, Nevada. The purpose of the meeting was to provide a forum for exchange of information on low-level radioactive waste management activities, requirements, and plans. Attendees included representatives from the DOE Nuclear Energy and Defense Low-Level Waste Management Programs, interim operations offices and their contractor operators; representatives from the US Nuclear Regulatory Commission, US Environmental Protection Agency, US Geological Survey, and their contractors; representatives of states and regions responsible for development of new commercial low-level waste disposal facilities; representatives of Great Britain, France, and Canada; representatives of utilities, private contractors, and parties concerned with low-level waste management issues. The meeting was organized by topical areas to allow for the exchange of information and the promotion of discussion on specific aspects of low-level waste management. Plenary sessions were held at the start and conclusion of the meeting while seven concurrent topical sessions were held during the intervening day and a half. Session chairmen from each of these concurrent sessions presented a summary of the discussion and conclusions resulting from their respective sessions at the final plenary session

  4. Annual summary of Immobilized Low-Activity Waste (ILAW) Performance Assessment for 2003 Incorporating the Integrated Disposal Facility Concept

    Energy Technology Data Exchange (ETDEWEB)

    MANN, F M

    2003-09-01

    To Erik Olds 09/30/03 - An annual summary of the adequacy of the Hanford Immobilized Low-Activity Tank Waste Performance Assessment (ILAW PA) is necessary in each year in which a full performance assessment is not issued.

  5. Hydrothermal processing of Hanford tank waste. Organic destruction technology development task annual report -- FY 1993

    International Nuclear Information System (INIS)

    Orth, R.J.; Schmidt, A.J.; Zacher, A.H.

    1993-09-01

    Low-temperature hydrothermal processing (HTP) is a thermal-chemical autogenous processing method that can be used to destroy organics and ferrocyanide in Hanford tank waste at temperatures from 250 C to 400 C. With HTP, organics react with oxidants, such as nitrite and nitrate, already present in the waste. Ferrocyanides and free cyanide will hydrolyze at similar temperatures and may also react with nitrates or other oxidants in the waste. No air or oxygen or additional chemicals need to be added to the autogenous HTP system. However, enhanced kinetics may be realized by air addition, and, if desired, chemical reductants can be added to the system to facilitate complete nitrate/nitrate destruction. Tank waste can be processed in a plug-flow, tubular reactor, or a continuous-stirred tank reactor system designed to accommodate the temperature, pressure, gas generation, and heat release associated with decomposition of the reactive species. The work described in this annual report was conducted in FY 1993 for the Organic Destruction Technology Development Task of Hanford's Tank Waste Remediation System (TWRS). This task is part of an overall program to develop organic destruction technologies originally funded by TWRS to meet tank safety and waste form disposal criteria and condition the feed for further pretreatment. During FY 1993 the project completed seven experimental test plans, a 30-hr pilot-scale continuous run, over 200 hr of continuous bench-scale HTP testing, and 20 batch HTP tests; two contracts were established with commercial vendors, and a commercial laboratory reactor was procured and installed in a glovebox for HTP testing with actual Hanford tank waste

  6. Cultural Resources Review for Closure of the nonradioactive Dangerous Waste Landfill and Solid Waste Landfill in the 600 Area, Hanford Site, Benton County, Washington, HCRC# 2010-600-018R

    Energy Technology Data Exchange (ETDEWEB)

    Gutzeit, Jennifer L.; Kennedy, Ellen P.; Bjornstad, Bruce N.; Sackschewsky, Michael R.; Sharpe, James J.; DeMaris, Ranae; Venno, M.; Christensen, James R.

    2011-02-02

    The U.S. Department of Energy Richland Operations Office is proposing to close the Nonradioactive Dangerous Waste Landfill (NRDWL) and Solid Waste Landfill (SWL) located in the 600 Area of the Hanford Site. The closure of the NRDWL/SWL entails the construction of an evapotranspiration cover over the landfill. This cover would consist of a 3-foot (1-meter) engineered layer of fine-grained soil, modified with 15 percent by weight pea gravel to form an erosion-resistant topsoil that will sustain native vegetation. The area targeted for silt-loam borrow soil sits in Area C, located in the northern central portion of the Fitzner/Eberhardt Arid Lands Ecology (ALE) Reserve Unit. The pea gravel used for the mixture will be obtained from both off-site commercial sources and an active gravel pit (Pit #6) located just west of the 300 Area of the Hanford Site. Materials for the cover will be transported along Army Loop Road, which runs from Beloit Avenue (near the Rattlesnake Barricade) east-northeast to the NRDWL/SWL, ending at State Route 4. Upgrades to Army Loop Road are necessary to facilitate safe bidirectional hauling traffic. This report documents a cultural resources review of the proposed activity, conducted according to Section 106 of the National Historic Preservation Act of 1966.

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

    International Nuclear Information System (INIS)

    Sagar, B.

    1997-01-01

    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. Waste Isolation Pilot Plant Annual Site Environmental Report for 2014. Emended

    International Nuclear Information System (INIS)

    2015-01-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2014 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: Characterize site environmental management performance; Summarize environmental occurrences and responses reported during the calendar year (CY); Confirm compliance with environmental standards and requirements; Highlight significant environmental accomplishments, including progress toward the DOE environmental sustainability goals made through implementation of the WIPP Environmental Management System (EMS).

  9. Nuclear waste repository simulation experiments, Asse Salt Mine, Federal Republic of Germany. Annual report, 1983

    International Nuclear Information System (INIS)

    Rothfuchs, T.; Luebker, D.; Coyle, A.; Kalia, H.

    1984-10-01

    This is the First Annual report (1983) which describes experiments simulating a nuclear waste respository at the 800-meter level of the Asse Salt Mine in the Federal Republic of Germany. The report describes the test equipment, the Asse Salt Mine, the pretest properties of the salt in the test gallery, and the mine proper. Also included are test data for the first six months of operations on brine migration rates, room closure rates, extensometer readings, stress measurements, and thermal mechanical behavior of the salt. The duration of the experiments will be two years, ending in December 1985. 3 references, 34 figures, 13 tables

  10. Waste Isolation Pilot Plant Annual Site Environmental Report for 2014. Emended

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2015-09-01

    The purpose of the Waste Isolation Pilot Plant (WIPP) Annual Site Environmental Report for 2014 (ASER) is to provide information required by U.S. Department of Energy (DOE) Order 231.1B, Environment, Safety, and Health Reporting. Specifically, the ASER presents summary environmental data to: Characterize site environmental management performance; Summarize environmental occurrences and responses reported during the calendar year (CY); Confirm compliance with environmental standards and requirements; Highlight significant environmental accomplishments, including progress toward the DOE environmental sustainability goals made through implementation of the WIPP Environmental Management System (EMS).

  11. Liquid and Gaseous Waste Operations Department annual operating report, CY 1992

    Energy Technology Data Exchange (ETDEWEB)

    Gillespie, M.A.; Maddox, J.J.; Scott, C.B.

    1993-03-01

    A total of 6.05 x 10[sup 7] gal of liquid waste was decontaminated by the Process Waste Treatment Plant (PWTP) ion exchange system during CY 1992. This averaged to 115 gpm throughout the year. When necessary, a wastewater sidestream of 50--80 gpm was treated through the use of a natural zeolite treatment system. An additional 8.00 x 10[sup 6] gal (average of 15 gpm throughout the year) were treated by the zeolite system. Therefore, the average total flow treated at the PWTP for CY 1992 was 130 gpm. In mid-June, the zeolite system was repiped to allow it the capability to treat the ion exchange system's discharge due to rising Cs problems in the wastewater. While being used to treat the ion exchange system's discharge, it cannot treat a sidestream of wastewater. During the year, the regeneration of the cation exchange resins resulted in the generation of 7.83 x 10[sup 3] gal of liquid low-level waste (LLLW) concentrate and 1.15 x 10[sup 4] gal of LLLW evaporator feed. The head-end softening process (precipitation/clarification) generated 604 drums (4.40 x 10[sup 3] ft[sup 3]) of solid low-level waste sludge. The zeolite treatment system generated approximately 8.40 x 10[sup 2] ft[sup 3] of spent zeolite resin, which was turned over to the Solid Waste Operations Department for disposal. See Table 1 for a monthly summary of activities at the PWTP. Figures 1, 2, 3, and 4 show a comparison of operations at the PWTP in 1992 with previous years. Figure 5 shows a comparison of annual rainfall at Oak Ridge National Laboratory (ORNL) since 1987. A total of 1.55 x 10[sup 8] gal of liquid waste (average of 294 gpm throughout the year) was treated at the Nonradiological Wastewater Treatment Plant (NRWTP). Of this amount, 1.40 x 10[sup 7] gal were treated by the precipitation/clarification process for removal of heavy metals. Twenty-five boxes (1.60 x 10[sup 3] ft[sup 3]) of solid sludge generated by the precipitation/clarification process were removed from the filter

  12. Liquid and Gaseous Waste Operations Department annual operating report, CY 1992

    Energy Technology Data Exchange (ETDEWEB)

    Gillespie, M.A.; Maddox, J.J.; Scott, C.B.

    1993-03-01

    A total of 6.05 x 10{sup 7} gal of liquid waste was decontaminated by the Process Waste Treatment Plant (PWTP) ion exchange system during CY 1992. This averaged to 115 gpm throughout the year. When necessary, a wastewater sidestream of 50--80 gpm was treated through the use of a natural zeolite treatment system. An additional 8.00 x 10{sup 6} gal (average of 15 gpm throughout the year) were treated by the zeolite system. Therefore, the average total flow treated at the PWTP for CY 1992 was 130 gpm. In mid-June, the zeolite system was repiped to allow it the capability to treat the ion exchange system`s discharge due to rising Cs problems in the wastewater. While being used to treat the ion exchange system`s discharge, it cannot treat a sidestream of wastewater. During the year, the regeneration of the cation exchange resins resulted in the generation of 7.83 x 10{sup 3} gal of liquid low-level waste (LLLW) concentrate and 1.15 x 10{sup 4} gal of LLLW evaporator feed. The head-end softening process (precipitation/clarification) generated 604 drums (4.40 x 10{sup 3} ft{sup 3}) of solid low-level waste sludge. The zeolite treatment system generated approximately 8.40 x 10{sup 2} ft{sup 3} of spent zeolite resin, which was turned over to the Solid Waste Operations Department for disposal. See Table 1 for a monthly summary of activities at the PWTP. Figures 1, 2, 3, and 4 show a comparison of operations at the PWTP in 1992 with previous years. Figure 5 shows a comparison of annual rainfall at Oak Ridge National Laboratory (ORNL) since 1987. A total of 1.55 x 10{sup 8} gal of liquid waste (average of 294 gpm throughout the year) was treated at the Nonradiological Wastewater Treatment Plant (NRWTP). Of this amount, 1.40 x 10{sup 7} gal were treated by the precipitation/clarification process for removal of heavy metals. Twenty-five boxes (1.60 x 10{sup 3} ft{sup 3}) of solid sludge generated by the precipitation/clarification process were removed from the filter press room.

  13. Liquid and Gaseous Waste Operations Department annual operating report, CY 1992

    International Nuclear Information System (INIS)

    Gillespie, M.A.; Maddox, J.J.; Scott, C.B.

    1993-03-01

    A total of 6.05 x 10 7 gal of liquid waste was decontaminated by the Process Waste Treatment Plant (PWTP) ion exchange system during CY 1992. This averaged to 115 gpm throughout the year. When necessary, a wastewater sidestream of 50--80 gpm was treated through the use of a natural zeolite treatment system. An additional 8.00 x 10 6 gal (average of 15 gpm throughout the year) were treated by the zeolite system. Therefore, the average total flow treated at the PWTP for CY 1992 was 130 gpm. In mid-June, the zeolite system was repiped to allow it the capability to treat the ion exchange system's discharge due to rising Cs problems in the wastewater. While being used to treat the ion exchange system's discharge, it cannot treat a sidestream of wastewater. During the year, the regeneration of the cation exchange resins resulted in the generation of 7.83 x 10 3 gal of liquid low-level waste (LLLW) concentrate and 1.15 x 10 4 gal of LLLW evaporator feed. The head-end softening process (precipitation/clarification) generated 604 drums (4.40 x 10 3 ft 3 ) of solid low-level waste sludge. The zeolite treatment system generated approximately 8.40 x 10 2 ft 3 of spent zeolite resin, which was turned over to the Solid Waste Operations Department for disposal. See Table 1 for a monthly summary of activities at the PWTP. Figures 1, 2, 3, and 4 show a comparison of operations at the PWTP in 1992 with previous years. Figure 5 shows a comparison of annual rainfall at Oak Ridge National Laboratory (ORNL) since 1987. A total of 1.55 x 10 8 gal of liquid waste (average of 294 gpm throughout the year) was treated at the Nonradiological Wastewater Treatment Plant (NRWTP). Of this amount, 1.40 x 10 7 gal were treated by the precipitation/clarification process for removal of heavy metals. Twenty-five boxes (1.60 x 10 3 ft 3 ) of solid sludge generated by the precipitation/clarification process were removed from the filter press room

  14. Proceedings of the fourth annual participants' information meeting, DOE Low-Level Waste Management Program

    International Nuclear Information System (INIS)

    Large, D.E.; Mezga, L.J.; Stratton, L.E.; Rose, R.R.

    1982-10-01

    The Fourth Annual Participants' Information Meeting of the Department of Energy Low-Level Waste Management Program was held in Denver, Colorado, August 31 to September 2, 1982. The purpose of the meeting was to report and evaluate technology development funded by the program and to examine mechanisms for technology transfer. The meeting consisted of an introductory plenary session, followed by two concurrent overview sessions and then six concurrent technical sessions. There were two group meetings to review the findings of the technical sessions. The meeting concluded with a plenary summary session in which the major findings of the meeting were addressed. All papers have been abstracted and indexed for the Energy Data Base

  15. Nuclear waste repository simulation experiments. Asse salt mine: Annual report 1984

    International Nuclear Information System (INIS)

    Rothfuchs, T.; Feddersen, H.K.; Schwarzianeck, P.; Staupendahl, G.; Coyle, A.J.; Kalia, H.; Eckert, J.

    1985-01-01

    This is the Second Annual Report (1984) which describes experiments simulating a nuclear waste repository at the 800 meter-level of the Asse Salt Mine in the Federal Republic of Germany. The report describes the Asse Salt Mine, the test equipment, and the pretest properties of the salt in the mine and in the vicinity of the test area. Also included are test data for the first sixteen months of operation on the following: brine migration rates, thermal mechanical behavior of the salt (including room closure, stress readings and thermal profiles) and borehole gas pressures. In addition to field data laboratory analyses of results are also included in this report. The duration of the experiment will be two years, ending in December 1985. (orig.)

  16. Nuclear waste repository simulation experiments, Asse salt mine, Federal Republic of Germany. Annual report 1984

    International Nuclear Information System (INIS)

    Rothfuchs, T.; Feddersen, H.K.; Schwarzianeck, P.; Staupendahl, G.; Coyle, A.J.; Eckert, J.; Kalia, H.

    1986-07-01

    This is the second joint annual report (1984) on experiments simulating a nuclear waste repository at the 800-m (2624-ft) level of the Asse salt mine in the Federal Republic of Germany. This report describes the Asse salt mine, the test equipment, and the pretest properties of the salt in the mine and in the vicinity of the test area. Also included are test data for the first 19 months of operation on the following: brine migration rates, thermal mechanical behavior of the salt (including room closure, stress reading, and thermal profiles), and borehole gas pressures. In addition to field data, laboratory analyses of results are included in this report. The duration of the experiment will be 2 years, ending in December 1985

  17. Annual technology assessment and progress report for the buried transuranic waste program at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Berreth, P.D.

    1984-11-01

    The US Department of Energy (DOE) is responsible for developing and implementing methods for the safe and environmentally acceptable disposal of radioactive waste. In 1983, DOE formulated a comprehensive plan to manage transuranic (TRU) defense waste. The DOE plan for buried TRU waste is to monitor it, take remedial actions as necessary, and reevaluate its safety periodically. The DOE strategy reflects concern that, based on present technology, retrieval and processing of buried waste may be risky and costly. To implement the DOE plan, EG and G Idaho, Inc., prime contractor at the Idaho National Engineering Laboratory (INEL), has developed a strategy for long-term management of the 2 million cubic feet of INEL buried TRU waste. That strategy involves four main activities: (a) environmental monitoring, (b) remedial action if necessary, (c) assimilation of data from both special studies and ongoing waste management activities, and (d) selection of a long-term management alternative in 1995. This report, submitted as the first in a series of annual reports, summarizes the buried TRU waste activities performed in fiscal year (FY) 1984 at the INEL in response to the DOE plan. Specifically, technologies applicable to buried waste confinement, retrieval, certification, and processing have been assessed, a long-range plan to conduct buried wasted studies over the next ten years has been prepared, and retrieval and soil management alternatives have been evaluated. 17 references, 7 figures, 1 table

  18. Illinois biomass resources: annual crops and residues; canning and food-processing wastes. Preliminary assessment

    Energy Technology Data Exchange (ETDEWEB)

    Antonopoulos, A A

    1980-06-01

    Illinois, a major agricultural and food-processing state, produces vast amounts of renewable plant material having potential for energy production. This biomass, in the form of annual crops, crop residues, and food-processing wastes, can be converted to alternative fuels (such as ethanol) and industrial chemicals (such as furfural, ethylene, and xylene). The present study provides a preliminary assessment of these Illinois biomass resources, including (a) an appraisal of the effects of their use on both agriculture and industry; (b) an analysis of biomass conversion systems; and (c) an environmental and economic evaluation of products that could be generated from biomass. It is estimated that, of the 39 x 10/sup 6/ tons of residues generated in 1978 in Illinois from seven main crops, about 85% was collectible. The thermal energy equivalent of this material is 658 x 10/sup 6/ Btu, or 0.66 quad. And by fermenting 10% of the corn grain grown in Illinois, some 323 million gallons of ethanol could have been produced in 1978. Another 3 million gallons of ethanol could have been produced in the same year from wastes generated by the state's food-processing establishments. Clearly, Illinois can strengthen its economy substantially by the development of industries that produce biomass-derived fuels and chemicals. In addition, a thorough evaluation should be made of the potential for using the state's less-exploitable land for the growing of additional biomass.

  19. Production of ethanol from refinery waste gases. Phase 2, technology development, annual report

    Energy Technology Data Exchange (ETDEWEB)

    Arora, D.; Basu, R.; Phillips, J.R.; Wikstrom, C.V.; Clausen, E.C.; Gaddy, J.L.

    1995-07-01

    Oil refineries discharge large volumes of H{sub 2}, CO, and CO{sub 2} from cracking, coking, and hydrotreating operations. This program seeks to develop a biological process for converting these waste gases into ethanol, which can be blended with gasoline to reduce emissions. Production of ethanol from all 194 US refineries would save 450 billion BTU annually, would reduce crude oil imports by 110 million barrels/year and emissions by 19 million tons/year. Phase II efforts has yielded at least 3 cultures (Clostridium ljungdahlii, Isolate O-52, Isolate C-01) which are able to produce commercially viable concentrations of ethanol from CO, CO{sub 2}, and H{sub 2} in petroleum waste gas. Single continuous stirred tank reactor studies have shown that 15-20 g/L of ethanol can be produced, with less than 5 g/L acetic acid byproduct. Culture and reactor optimization in Phase III should yield even higher ethanol concentrations and minimal acetic acid. Product recovery studies showed that ethanol is best recovered in a multi-step process involving solvent extraction/distillation to azeotrope/azeotropic distillation or pervaporation, or direct distillation to the azeotrope/azeotropic distillation or pervaporation. Projections show that the ethanol facility for a typical refinery would require an investment of about $30 million, which would be returned in less than 2 years.

  20. US Department of Energy National Solid Waste Information Management System (NSWIMS): Annual report for calendar year 1987

    Energy Technology Data Exchange (ETDEWEB)

    Scott, W.L.

    1988-07-01

    The Solid Waste Information Management System (SWIMS) is the database used to gather information for the US Department of Energy (DOE) on DOE and Department of Defense solid low-level radioactive waste (LLW). The National SWIMS Annual Report (NSWIMS) provides officials of the DOE with management information on the entire DOE/defense solid LLW cycle. The acronym for the annual report, NSWIMS, signifies that an improved format has been developed to make this document a more useful tool for assessing solid LLW management performance. Part I provides a composite summary of the DOE/defense solid LLW management. It includes data related to waste generation, forecasting, treatment, and disposal. Part II contains SWIMS computer-supplied information with discussions of the data presented, standardized and simplified data tables, and revised figures. All data are presented without interpretation and are potentially useful to users for evaluating trends, identifying possible problem areas, and defining future implications. 33 figs., 29 tabs.

  1. Liquid and Gaseous Waste Operations Department Annual Operating Report, CY 1993

    International Nuclear Information System (INIS)

    Maddox, J.J.; Scott, C.B.

    1994-02-01

    This report summarizes the activities of the waste management operations section of the liquid and gaseous waste operations department at ORNL for 1993. The process waste, liquid low-level waste, gaseous waste systems activities are reported, as well as the low-level waste solidification project. Upgrade activities is the various waste processing and treatment systems are summarized. A maintenance activity overview is provided, and program management, training, and other miscellaneous activities are covered

  2. Liquid and Gaseous Waste Operations Department Annual Operating Report, CY 1993

    Energy Technology Data Exchange (ETDEWEB)

    Maddox, J.J.; Scott, C.B.

    1994-02-01

    This report summarizes the activities of the waste management operations section of the liquid and gaseous waste operations department at ORNL for 1993. The process waste, liquid low-level waste, gaseous waste systems activities are reported, as well as the low-level waste solidification project. Upgrade activities is the various waste processing and treatment systems are summarized. A maintenance activity overview is provided, and program management, training, and other miscellaneous activities are covered.

  3. Transuranic waste program at EG and G Idaho, Inc. Annual technical report

    International Nuclear Information System (INIS)

    Smith, T.H.; Tolman, C.R.

    1980-12-01

    This document summarizes the objectives and technical achievements of the transuranic (TRU) waste research and development program conducted at EG and G Idaho, Inc., during fiscal year 1980. The TRU waste activities covered in this report include: INEL TRU Waste EIS (Environmental Impact Statement), including preparation of the EIS, Support Studies, and the Public Participation Program; INEL TRU Waste Projects, including System Analysis, Stored Waste projects, and Buried Waste projects; and Waste Management Materials Studies, including Process Control and Durability studies

  4. Seventh annual DOE LLWMP participants' information meeting. DOE Low-Level Waste Management Program. Abstracts

    International Nuclear Information System (INIS)

    1985-08-01

    The following sessions were held: International Low-Level Waste Management Activities; Low-Level Waste Disposal; Characteristics and Treatment of Low-Level Waste; Environmental Monitoring and Performance; Greater Confinement and Alternative Disposal Methods; Low-Level Waste Management; Corrective Measures; Performance Prediction and Assessment; and Siting New Defense and Commercial Low-Level Waste Disposal Facilities

  5. 1993 annual report of hazardous waste activities for the Oak Ridge K-25 site

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    This report is a detailed listing of all of the Hazardous Waste activities occurring at Martin Marietta`s K-25 site. Contained herein are hazardous waste notification forms, waste stream reports, generator fee forms and various TSDR reports.

  6. 1993 annual report of hazardous waste activities for the Oak Ridge K-25 site

    International Nuclear Information System (INIS)

    1994-02-01

    This report is a detailed listing of all of the Hazardous Waste activities occurring at Martin Marietta's K-25 site. Contained herein are hazardous waste notification forms, waste stream reports, generator fee forms and various TSDR reports

  7. Annual Transportation Report for Radioactive Waste Shipments to and from the Nevada Test Site, Fiscal Year 2006

    Energy Technology Data Exchange (ETDEWEB)

    DOE/NNSA NSO

    2007-01-01

    In February 1997, the U.S. Department of Energy, Nevada Operations Office 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). The U.S. Department of Energy, Nevada Operations Office 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 (RWMS) 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) 2006.

  8. Annual Report - FY 2001, Radioactive Waste Shipments To and From the Nevada Test Site (NTIS), February 2002

    International Nuclear Information System (INIS)

    U.S. Department of Energy, National Nuclear Security Administration, Nevada Operations Office

    2002-01-01

    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)

  9. 1993 Annual report on waste generation and waste minimization progress as required by DOE Order 5400.1, Hanford Site

    International Nuclear Information System (INIS)

    Kirkendall, J.R.; Engel, J.A.

    1994-01-01

    More important than waste generation numbers, the pollution prevention and waste minimization successes achieved at Hanford in 1993 have reduced waste and improved operations at the Site. Just a few of these projects are: A small research nuclear reactor, unused and destined for disposal as low level radioactive waste, was provided to a Texas University for their nuclear research program, avoiding 25 cubic meters of waste and saving $116,000. By changing the slope on a asphalt lot in front of a waste storage pad, run-off rainwater was prevented from becoming mixed low level waste water, preventing 40 cubic meters of waste and saving $750,000. Through more efficient electrostatic paint spraying equipment and a solvent recovery system, a paint shop reduced hazardous waste by 3,500 kilograms, saving $90,800. During the demolition of a large decommissioned building, more than 90% of the building's material was recycled by crushing the concrete for use on-Site and selling the steel to an off-Site recycler, avoiding a total of 12,600 metric tons of waste and saving $450,000. Additionally, several site-wide programs have avoided large quantities of waste, including the following: Through expansion of the paper and office waste recycling program which includes paper, cardboard, newspaper, and phone books, 516 metric tons of sanitary waste was reduced, saving $68,000. With the continued success of the excess chemicals program, which finds on-Site and off-Site customers for excess chemical materials, hazardous waste was reduced by 765,000 liters of liquid chemicals and 50 metric tons of solid chemicals, saving over $700,000 in disposal costs

  10. 1997 annual ground control operating plan for the Waste Isolation Pilot Plant

    International Nuclear Information System (INIS)

    1997-02-01

    This plan presents background information and a working guide to assist Mine Operations and Engineering in developing strategies for addressing ground control issues at the Waste Isolation Pilot Plant (WIPP). With the anticipated receipt of waste in late 1997, this document provides additional detail to Panel 1 activities and options. The plan also serves as a foundation document for development and revision of the annual long-term ground control plan. Section 2.0 documents the current status of all underground excavations with respect to location, geology, geometry, age, ground support, operational use, projected life, and physical conditions. Section 3.0 presents the methods used to evaluate ground conditions, including visual observations of the roof, ribs, and floor, inspection of observation holes, and review of instrumentation data. Section 4.0 lists several ground support options and specific applications of each. Section 5.0 discusses remedial ground control measures that have been implemented to date. Section 6.0 presents projections and recommendations for ground control actions based on the information in Sections 2.0 through 5.0 of this plan and on a rating of the critical nature of each specific area. Section 7.0 presents a summary statement, and Section 8.0 includes references. Appendix A provides an overview and critique of ground control systems that have been, or may be, used at the site. Because of the dynamic nature of the underground openings and associated geotechnical activities, this plan will be revised as additional data are incorporated

  11. Solidification of problem wastes: Annual progress report, October 1985-September 1986

    International Nuclear Information System (INIS)

    Franz, E.M.; Heiser, J.H. III; Colombo, P.

    1987-02-01

    This report describes initial work on the development of solidification systems for sodium nitrate waste and compacted waste. Sodium nitrate waste has been solidified in three types of materials: polyethylene, polyester-styrene (PES), and latex cement. Evaluations of the properties of the waste form, such as the ANS 16.1 leaching test, water immersion test and compressive strength measurements were performed on the waste forms containing various amounts of sodium nitrate. 9 refs., 9 figs., 7 tabs

  12. 1994 Annual report on waste generation and waste minimization progress as required by DOE Order 5400.1, Hanford Site

    International Nuclear Information System (INIS)

    1995-09-01

    Many Waste Minimization/Pollution Prevention successes at the Hanford Site occur every day without formal recognition. A few of the successful projects are: T-Plant helps facilities reuse equipment by offering decontamination services for items such as gas cylinders, trucks, and railcars, thus saving disposal and equipment replacement costs. Custodial Services reviewed its use of 168 hazardous cleaning products, and, through a variety of measures, replaced them with 38 safer substitutes, one for each task. Scrap steel contaminated with low level radioactivity from the interim stabilization of 107-K and 107-C was decontaminated and sold to a vendor for recycling. Site-wide programs include the following: the Pollution Prevention Opportunity Assessment (P2OA) program at the Hanford site was launched during 1994, including a training class, a guidance document, technical assistance, and goals; control over hazardous materials purchased was achieved by reviewing all purchase requisitions of a chemical nature; the Office Supply Reuse Program was established to redeploy unused or unwanted office supply items. In 1994, pollution prevention activities reduced approximately 274,000 kilograms of hazardous waste, 2,100 cubic meters of radioactive and mixed waste, 14,500,000 kilograms of sanitary waste, and 215,000 cubic meters off liquid waste and waste water. Pollution Prevention activities also saved almost $4.2 million in disposal, product, and labor costs. Overall waste generation increased in 1994 due to increased work and activity typical for a site with an environmental restoration mission. However, without any Waste Minimization/Pollution Prevention activities, solid radioactive waste generation at Hanford would have been 25% higher, solid hazardous waste generation would have been 30% higher, and solid sanitary waste generation would have been 60% higher

  13. Proceedings of the tenth annual DOE low-level waste management conference: Session 5: Waste characterization and quality assurance

    Energy Technology Data Exchange (ETDEWEB)

    1988-12-01

    This document contains six papers on various aspects of low-level radioactive waste management. Topics include quality assurance programs; source terms; waste characterization programs; and DOE's information network modifications. Individual papers were processed separately for the data base. (TEM)

  14. Payment Of the New Mexico Environment Department- Hazardous Waste Bureau Annual Business and Generation Fees Calendar Year 2011

    Energy Technology Data Exchange (ETDEWEB)

    Juarez, Catherine L. [Los Alamos National Laboratory

    2012-08-31

    The purpose of this letter is to transmit to the New Mexico Environment Department-Hazardous Waste Bureau (NMED-HWB), the Los alamos National Laboratory (LANL) Annual Business and Generation Fees for calendar year 2011. These fees are required pursuant to the provisions of New Mexico Hazardous Waste Act, Chapter 74, Article 4, NMSA (as amended). The Laboratory's Fenton Hill Facility did not generate any hazardous waste during the entire year, and is not required to pay a fee for calendar year 2011. The enclosed fee represents the amount for a single facility owned by the Department of Energy and co-operated by the Los Alamos National Security, LLC (LANS).

  15. 1995 Annual report on waste generation and waste mainization progress as required by DOE order 5400.1, Hanford site

    Energy Technology Data Exchange (ETDEWEB)

    Betsch, M.D.

    1996-09-24

    While waste generation numbers are important, the true measure of success is waste minimized. Many Waste Minimization/Pollution Prevention (WMin/P2) successes at the Hanford Site occur every day without formal recognition as pollution prevention, as they have become part of a culture of best management practices. As an example, the success of the excess and reuse program, both informal and formal, documents the Wmin/P2 culture that exists in the pollution prevention representatives and employees at the facilities.

  16. ORNL nuclear waste programs annual progress report for period ending September 30, 1982

    International Nuclear Information System (INIS)

    1983-05-01

    Research progress is reported in 20 activities under the headings: spent fuels, defense waste management, commercial waste management, remedial action, and conventional reactors. Separate entries were prepared for each activity

  17. ORNL nuclear waste programs annual progress report for period ending September 30, 1982

    Energy Technology Data Exchange (ETDEWEB)

    1983-05-01

    Research progress is reported in 20 activities under the headings: spent fuels, defense waste management, commercial waste management, remedial action, and conventional reactors. Separate entries were prepared for each activity.

  18. 1992 annual report on low-level radioactive waste management progress

    International Nuclear Information System (INIS)

    1993-11-01

    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

  19. Waste Tank Vapor Characterization Project: Annual status report for FY 1995

    International Nuclear Information System (INIS)

    Ligotke, M.W.; Fruchter, J.S.; Huckaby, J.L.; Birn, M.B.; McVeety, B.D.; Evans, J.C. Jr.; Pool, K.H.; Silvers, K.L.; Goheen, S.C.

    1995-11-01

    This report compiles information collected during the Fiscal Year 1995 pertaining to the waste tank vapor characterization project. Information covers the following topics: project management; organic sampling and analysis; inorganic sampling and analysis; waste tank vapor data reports; and the waste tanks vapor database

  20. Liquid and Gaseous Waste Operations Department annual operating report CY 1994

    International Nuclear Information System (INIS)

    Maddox, J.J.; Scott, C.B.

    1995-03-01

    This report presents details about the operation of the liquid and gaseous waste department of Oak Ridge National Laboratory for the calendar year 1994. Topics discussed include; process waste system, upgrade activities, low-level liquid radioactive waste solidification project, maintenance activities, and other activities such as training, audits, and tours

  1. Annual Report 2011 : Institute for Nuclear Waste Disposal. (KIT Scientific Reports ; 7617)

    OpenAIRE

    Geckeis, H. [Hrsg.; Stumpf, T. [Hrsg.

    2012-01-01

    The R&D at the Institute for Nuclear Waste Disposal, INE, (Institut für Nukleare Entsorgung) of the Karlsruhe Institute of Technology (KIT) focuses on (i) long term safety research for nuclear waste disposal, (ii) immobilization of high level radioactive waste (HLW), (iii) separation of minor actinides from HLW and (iv) radiation protection.

  2. Health-care waste incineration and related dangers to public health: case study of the two teaching and referral hospitals in Kenya.

    Science.gov (United States)

    Njagi, Nkonge A; Oloo, Mayabi A; Kithinji, J; Kithinji, Magambo J

    2012-12-01

    There are practically no low cost, environmentally friendly options in practice whether incineration, autoclaving, chemical treatment or microwaving (World Health Organisation in Health-care waste management training at national level, [2006] for treatment of health-care waste. In Kenya, incineration is the most popular treatment option for hazardous health-care waste from health-care facilities. It is the choice practiced at both Kenyatta National Hospital, Nairobi and Moi Teaching and Referral Hospital, Eldoret. A study was done on the possible public health risks posed by incineration of the segregated hazardous health-care waste in one of the incinerators in each of the two hospitals. Gaseous emissions were sampled and analyzed for specific gases the equipment was designed and the incinerators Combustion efficiency (CE) established. Combustion temperatures were also recorded. A flue gas analyzer (Model-Testos-350 XL) was used to sample flue gases in an incinerator under study at Kenyatta National Hospital--Nairobi and Moi Teaching and Referral Hospital--Eldoret to assess their incineration efficiency. Flue emissions were sampled when the incinerators were fully operational. However the flue gases sampled in the study, by use of the integrated pump were, oxygen, carbon monoxide, nitrogen dioxide, nitrous oxide, sulphur dioxide and No(x). The incinerator at KNH operated at a mean stack temperature of 746 °C and achieved a CE of 48.1 %. The incinerator at MTRH operated at a mean stack temperature of 811 °C and attained a CE of 60.8 %. The two health-care waste incinerators achieved CE below the specified minimum National limit of 99 %. At the detected stack temperatures, there was a possibility that other than the emissions identified, it was possible that the two incinerators tested released dioxins, furans and antineoplastic (cytotoxic drugs) fumes should the drugs be subjected to incineration in the two units.

  3. Spent Fuel and Waste Management Technology Development Program. Annual progress report

    Energy Technology Data Exchange (ETDEWEB)

    Bryant, J.W.

    1994-01-01

    This report provides information on the progress of activities during fiscal year 1993 in the Spent Fuel and Waste Management Technology Development Program (SF&WMTDP) at the Idaho Chemical Processing Plant (ICPP). As a new program, efforts are just getting underway toward addressing major issues related to the fuel and waste stored at the ICPP. The SF&WMTDP has the following principal objectives: Investigate direct dispositioning of spent fuel, striving for one acceptable waste form; determine the best treatment process(es) for liquid and calcine wastes to minimize the volume of high level radioactive waste (HLW) and low level waste (LLW); demonstrate the integrated operability and maintainability of selected treatment and immobilization processes; and assure that implementation of the selected waste treatment process is environmentally acceptable, ensures public and worker safety, and is economically feasible.

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

    International Nuclear Information System (INIS)

    2010-06-01

    The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2009 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, events or incidents, environmental monitoring, wastes management, public information, opinion of the Health and safety Committee (CHSCT)

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

    International Nuclear Information System (INIS)

    2009-06-01

    The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2008 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, events or incidents, environmental monitoring, wastes management, public information

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

    International Nuclear Information System (INIS)

    2011-06-01

    The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2010 activity report of the center for short-lived low- and intermediate-level wastes. It presents a review of the activities of the center: presentation of the installations, safety and radiation protection, events or incidents, environmental monitoring, wastes management, public information, recommendations of the Health and safety Committee (CHSCT)

  7. Emissions and waste in The Netherlands. Annual report 1996 and estimations for 1997; Emissies en afval in Nederland. Jaarrapport 1996 en ramingen 1997

    Energy Technology Data Exchange (ETDEWEB)

    Draaijers, G.P.J.; Berdowski, J.J.M.; Coenen, P.W.H.G.; Leneman, H.; Rood, G.A.; De Vries, D.J.; Zonneveld, E.A. [eds.

    1999-01-01

    An overview is given of the most important results of a survey of the emission of polluting materials into the air, water and soil in the Netherlands in 1996. Also estimates of emissions for 1997 are presented. For the first time data on waste production and waste processing were compiled and are presented in this annual report. 32 refs.

  8. 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.

  9. 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.

  10. 2011 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond

    International Nuclear Information System (INIS)

    Lewis, Mike

    2012-01-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond from November 1, 2010 through October 31, 2011. The report contains the following information: Facility and system description Permit required effluent monitoring data and loading rates Groundwater monitoring data Status of compliance activities Noncompliance and other issues Discussion of the facility's environmental impacts During the 2011 permit year, approximately 166 million gallons of wastewater were discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters were below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

  11. 1997 annual report on waste generation and waste minimization progress as required by DOE Order 5400.1, Hanford Site

    International Nuclear Information System (INIS)

    Segall, P.

    1998-01-01

    Hanford's missions are to safely clean up and manage the site's legacy wastes, and to develop and deploy science and technology. Through these missions Hanford will contribute to economic diversification of the region. Hanford's environmental management or cleanup mission is to protect the health and safety of the public, workers, and the environment; control hazardous materials; and utilize the assets (people, infra structure, site) for other missions. Hanford's science and technology mission is to develop and deploy science and technology in the service of the nation including stewardship of the Hanford Site. Pollution Prevention is a key to the success of these missions by reducing the amount of waste to be managed and identifying/implementing cost effective waste reduction projects. Hanford's original mission, the production of nuclear materials for the nation's defense programs, lasted more than 40 years, and like most manufacturing operations, Hanford's operations generated large quantities of waste and pollution. However, the by-products from Hanford operations pose unique problems like radiation hazards, vast volumes of contaminated water and soil, and many contaminated structures including reactors, chemical plants and evaporation ponds. The cleanup activity is an immense and challenging undertaking, which includes characterization and decommissioning of 149 single shell storage tanks, treating 28 double shell tanks, safely disposing of over 2,100 metric tons of spent nuclear fuel stored on site, removing numerous structures, and dealing with significant solid waste, ground water, and land restoration issues

  12. Annual report 1999. Department of wastes disposal and storage; Rapport annuel d'activite 1999. Departement d'Entreposage et de Stockage des Dechets

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    This annual report presents the organization, the personnel, the collaborations, the scientific researches and the publications of the Department of wastes disposal and storage of the CEA. A thematic presentation of the research and development programs is provided bringing information on the liquid effluents processing, the materials and solid wastes processing, the wastes conditioning, the characterization, the storage, the radionuclides chemistry and migration, the dismantling and the environment. (A.L.B.)

  13. Impact of LWR decontaminations on solidification, waste disposal and associated occupational exposure. Annual report

    International Nuclear Information System (INIS)

    Davis, M.S.

    1983-08-01

    This report describes generic and specific aspects of hard and soft chemical decontaminations and considers the radiation and thermal stability of the reagents involved. Disposal options for LWR decontamination wastes are reviewed and advantages and disadvantages related to the options are discussed. Studies indicating the potential impact of these wastes on a shallow land burial ability to retain radionuclides are summarized. Processes being considered for the management of spent ion-exchange resins are reviewed. Problems associated with the state-of-the-art of incineration, pyrolysis, wet air oxidation, acid digestion, and chemical disgestion are evaluated. The solidification and disposal of decontamination wastes are considered with respect to criteria given in the Licensing Rule for Land Disposal of Radioactive Waste, 10 CFR 61. These are evaluated with respect to possible solidification in cement, bitumen, and plastics. The various options in mixing decontamination wastes with normal LWR resin waste are discussed with respect to their impacts on occupational exposure. 27 tables

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

    International Nuclear Information System (INIS)

    2012-08-01

    The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2011 activity report of the center for very-low-level radioactive wastes. It presents a review of the activities of the center: presentation of the installations, safety, security and radiation protection, environmental monitoring and effluents, public information and communication

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

    International Nuclear Information System (INIS)

    2011-09-01

    The National Radioactive Waste Management Agency (Andra), was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. The Andra operates two storage centers in the Aube region (France): the center for short-lived low- and intermediate-level wastes, and the center for very-low-level radioactive wastes. This document is the 2010 activity report of the center for very-low-level radioactive wastes. It presents a review of the activities of the center: presentation of the installations, safety, security and radiation protection, environmental monitoring and effluents, public information and communication

  16. 1996 annual report on low-level radioactive waste management progress. Report to Congress

    International Nuclear Information System (INIS)

    1997-11-01

    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

  17. WASTE PROCESSING ANNUAL NUCLEAR SAFETY RELATED R AND D REPORT FOR CY2008

    Energy Technology Data Exchange (ETDEWEB)

    Fellinger, A.

    2009-10-15

    The Engineering and Technology Office of Waste Processing identifies and reduces engineering and technical risks associated with key waste processing project decisions. The risks, and actions taken to mitigate those risks, are determined through technology readiness assessments, program reviews, technology information exchanges, external technical reviews, technical assistance, and targeted technology development and deployment (TDD). The Office of Waste Processing TDD program prioritizes and approves research and development scopes of work that address nuclear safety related to processing of highly radioactive nuclear wastes. Thirteen of the thirty-five R&D approved work scopes in FY2009 relate directly to nuclear safety, and are presented in this report.

  18. Report to Congress: 1995 Annual report on low-level radioactive waste management progress

    International Nuclear Information System (INIS)

    1996-06-01

    This report is prepared in response to the Low-Level Radioactive Waste Policy 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 progress of states and compact regions during calendar year 1995 in establishing new disposal facilities for commercially-generated low-level radioactive waste. The report emphasizes significant issues and events that have affected progress, and also includes an introduction that provides background information and perspective on United States policy for low-level radioactive waste disposal

  19. Measurements and models for hazardous chemical and mixed wastes. 1998 annual progress report

    International Nuclear Information System (INIS)

    Holcomb, C.; Louie, B.; Mullins, M.E.; Outcalt, S.L.; Rogers, T.N.; Watts, L.

    1998-01-01

    'Aqueous waste of various chemical compositions constitutes a significant fraction of the total waste produced by industry in the US. A large quantity of the waste generated by the US chemical process industry is waste water. In addition, the majority of the waste inventory at DoE sites previously used for nuclear weapons production is aqueous waste. Large quantities of additional aqueous waste are expected to be generated during the clean-up of those sites. In order to effectively treat, safely handle, and properly dispose of these wastes, accurate and comprehensive knowledge of basic thermophysical property information is paramount. This knowledge will lead to huge savings by aiding in the design and optimization of treatment and disposal processes. The main objectives of this project are: Develop and validate models that accurately predict the phase equilibria and thermodynamic properties of hazardous aqueous systems necessary for the safe handling and successful design of separation and treatment processes for hazardous chemical and mixed wastes. Accurately measure the phase equilibria and thermodynamic properties of a representative system (water + acetone + isopropyl alcohol + sodium nitrate) over the applicable ranges of temperature, pressure, and composition to provide the pure component, binary, ternary, and quaternary experimental data required for model development. As of May, 1998, nine months into the first year of a three year project, the authors have made significant progress in the database development, have begun testing the models, and have been performance testing the apparatus on the pure components.'

  20. Proceedings of the tenth annual DOE low-level waste management conference: Session 4: Waste treatment minimization

    International Nuclear Information System (INIS)

    1988-12-01

    This document contains eleven papers on various aspects of low-level radioactive waste management. Topics in this volume include: volume reduction plans; incentitives; and cost proposals; acid detoxification and reclamation; decontamination of lead; leach tests; West Valley demonstration project status report; and DOE's regional management strategies. Individual papers were processed separately for the data base

  1. Ways out of danger

    International Nuclear Information System (INIS)

    Eppler, E.

    1981-01-01

    The volume divides into five sections: ways out of danger; pressure leading into danger; what might save us, and will it grow to become effective; tedious paths out of danger; companions out of danger. The author puts the question whether the true art of politics will be restored. He shows that by reducing politics to mere crisis management we shall not be enabled to overcome the serious problems of the eighties. He points out future possibilities by making clear the chances and misdevelopments of energy policy, of foreign, development and defence policy. The political experience of recent years, the new approach showing different needs and ways of life should be taken seriously as hopeful signs and ought to be reflected in politics again. (HSCH) [de

  2. The dangers of plutonium

    International Nuclear Information System (INIS)

    Koelzer, W.

    1978-01-01

    After outlining the physical and chemical properties of plutonium, the author compares toxic substances inhaled and ingested; it is found that plutonium is far less dangerous than botulin or anthrax spores. (GL) [de

  3. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Health A-Z Symptoms Glasses & Contacts Tips & Prevention News Ask an Ophthalmologist Patient Stories Español Eye Health / News Halloween Hazard: The Hidden Dangers of Buying Decorative ...

  4. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Hidden Dangers of Buying Decorative Contact Lenses Without a Prescription Leer en Español: Peligros asociados con los ... contacto de color Sep. 26, 2013 It started as an impulsive buy from a souvenir shop, but ...

  5. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Patient Stories Español Eye Health / News Halloween Hazard: The Hidden Dangers of Buying Decorative Contact Lenses Without ... been properly fitted by an eye care professional, the lenses stuck to my eye like a suction ...

  6. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Español Eye Health / News Halloween Hazard: The Hidden Dangers of Buying Decorative Contact Lenses Without a Prescription ... people with high myopia? Mar 29, 2017 New Technology Helps the Legally Blind Be More Independent Oct ...

  7. Annual Hanford Site Environmental Permitting status report

    International Nuclear Information System (INIS)

    SONNICHSEN, J.C.

    1999-01-01

    The information contained in, and/or referenced in, this Annual Hanford Site Environmental Permitting Status Report addresses Permit Condition II.W (Other Permits and/or Approvals) of the Dangerous Waste Portion of the Resource Conservation and Recovery Act Permit for the Treatment, Storage, and Disposal of Dangerous Waste, issued by the Washington State Department of Ecology (WA7890008967). Condition II.W specifies that the Permittees are responsible for obtaining all other applicable federal, state, and local permits authorizing the development and operation of the Hanford Facility. Condition II.W further specifies that the Permittees are to use their best efforts to obtain such permits. For the purposes of this Permit Condition, ''best efforts'' mean submittal of documentation and/or approval(s) in accordance with schedules specified in applicable regulations, or as determined through negotiations with the applicable regulatory agencies

  8. US Department of Energy National Solid Waste Information Management System (NSWIMS) annual report for calendar year 1988

    Energy Technology Data Exchange (ETDEWEB)

    Watanabe, T.

    1989-09-01

    This report is generated annually from the National Solid Waste Information Management System (SWIMS) database. The SWIMS database operates under NOMAD2, fourth generation database management system. The database resides on an IBM 3083 mainframe with a virtual machine operating system. This system was implemented to meet the requirements of Energy Research and Development Administration Manual. The SWIMS database has kept pace with requirements of subsequent directives and complies with current Department of Energy (DOE) orders for retention of data on the management of solid low-level radioactive waste (LLW). SWIMS provides a comprehensive method for collecting and maintaining data related to management of US DOE and Department of Defense (DOE/Defense) related LLW. 33 figs., 29 tabs.

  9. Chemical Waste Landfill Annual Post-Closure Care Report Calendar Year 2014

    Energy Technology Data Exchange (ETDEWEB)

    Mitchell, Michael Marquand [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Little, Bonnie Colleen [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-03-01

    The CWL is a 1.9-acre remediated interim status landfill located in the southeastern corner of SNL/NM Technical Area III (Figures 2-1 and 2-2) undergoing post-closure care in accordance with the PCCP (NMED October 2009 and subsequent revisions). From 1962 until 1981, the CWL was used for the disposal of chemical and solid waste generated by SNL/NM research activities. Additionally, a small amount of radioactive waste was disposed of during the operational years. Disposal of liquid waste in unlined pits and trenches ended in 1981, and after 1982 all liquid waste disposal was terminated. From 1982 through 1985, only solid waste was disposed of at the CWL, and after 1985 all waste disposal ended. The CWL was also used as a hazardous waste drum-storage facility from 1981 to 1989. A summary of the CWL disposal history is presented in the Closure Plan (SNL/NM December 1992) along with a waste inventory based upon available disposal records and information.

  10. Proceedings of the sixth annual Participants' Information Meeting DOE Low-Level Waste Management Program

    International Nuclear Information System (INIS)

    1984-12-01

    Sessions were held on disposal technology, characteristics and treatment of low-level waste, environmental aspects and performance prediction, predicting source terms for low-level wastes (LLW), performance assessment for LLW disposal facilities, and approaches to LLW facility siting and characteristics. Fifty-six papers were indexed separately

  11. 2016 Annual Reuse Report for the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Ponds

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, Michael George [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-02-01

    This report describes conditions and information, as required by the state of Idaho, Department of Environmental Quality Reuse Permit I-161-02, for the Advanced Test Reactor Complex Cold Waste Ponds located at Idaho National Laboratory from November 1, 2015–October 31, 2016. The effective date of Reuse Permit I-161-02 is November 20, 2014 with an expiration date of November 19, 2019. This report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Permit required groundwater monitoring data • Status of compliance activities • Issues • Discussion of the facility’s environmental impacts. During the 2016 permit year, 180.99 million gallons of wastewater were discharged to the Cold Waste Ponds. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest in well USGS-065, which is the closest downgradient well to the Cold Waste Ponds. Sulfate and total dissolved solids concentrations decrease rapidly as the distance downgradient from the Cold Waste Ponds increases. Although concentrations of sulfate and total dissolved solids are significantly higher in well USGS-065 than in the other monitoring wells, both parameters remained below the Ground Water Quality Rule Secondary Constituent Standards in well USGS-065. The facility was in compliance with the Reuse Permit during the 2016 permit year.

  12. Semi-annual status report of the Canadian Nuclear Fuel Waste Management Program, April 1--September 30, 1991

    Energy Technology Data Exchange (ETDEWEB)

    Wright, E.D. [comp.

    1992-02-01

    This report is the eleventh in a series of semi-annual status reports on the research and development program for the safe management and disposal of Canada's nuclear fuel waste. it describes progress achieved in the three major subprograms, engineered systems, natural systems and performance assessment, from 1991 April 1 to September 30. It also gives a brief description of the activities being carried out in preparation for the public and governmental review of the disposal concept. Since 1987, this program has been jointly funded by AECL and Ontario Hydro under the auspices of the CANDU Owners Group (COG).

  13. Annual Report for 2008 - 2009 Detection Monitoring at the Environmental Management Waste Management Facility, Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Walker J.R.

    2010-03-01

    This annual Environmental Monitoring Report (EMR) presents results of environmental monitoring performed during fiscal year (FY) 2009 (October 1, 2008 - September 30, 2009) at the Environmental Management Waste Management Facility (EMWMF). The EMWMF is an operating state-of-the-art hazardous waste landfill located in Bear Creek Valley (BCV) west of the U.S. Department of Energy (DOE) Y-12 National Security Complex (Y-12) on the DOE Oak Ridge Reservation (ORR) in Oak Ridge, Tennessee (Appendix A, Fig. A.1). Opened in 2002 and operated by a DOE prime contractor, Bechtel Jacobs Company LLC (BJC), the EMWMF was built specifically to accommodate disposal of acceptable solid wastes generated from Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) remedial actions for former waste sites and buildings that have been impacted by past DOE operations on the ORR and at DOE sites off the ORR within the state of Tennessee. Environmental monitoring at the EMWMF is performed to detect and monitor the impact of facility operations on groundwater, surface water, stormwater, and air quality and to determine compliance with applicable or relevant and appropriate requirements (ARARs) specified in governing CERCLA decision documents. Annually, the EMR presents an evaluation of the groundwater, surface water, stormwater, and air monitoring data with respect to the applicable EMWMF performance standards. The purpose of the evaluation is to: (1) identify monitoring results that indicate evidence of a contaminant release from the EMWMF to groundwater, surface water, stormwater, or air, and (2) recommend appropriate changes to the associated sampling and analysis requirements, including sampling locations, methods, and frequencies; field measurements; or laboratory analytes that may be warranted in response to the monitoring data. Sect. 2 of this annual EMR provides background information relevant to environmental monitoring at the landfill, including

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

    International Nuclear Information System (INIS)

    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

  15. 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.

  16. 1994 annual report on waste generation and waste minimization progress as required by DOE Order 5400.1

    International Nuclear Information System (INIS)

    Irwin, E.F.; Poligone, S.E.

    1995-01-01

    The Y-12 Plant serves as a key manufacturing technology center for the development and demonstration of unique materials, components, and services of importance to the Department of Energy (DOE) and the nation. This is accomplished through the reclamation and storage of nuclear materials, manufacture of nuclear materials, manufacture of components for the nation's defense capabilities, support to national security programs, and services provided to other customers as approved by DOE. We are recognized by our people, the community, and our customers as innovative, responsive, and responsible. We are a leader in worker health and safety, environmental protection, and stewardship of our national resources. As a DOE facility, Y-12 also supports DOE's waste minimization mission. Data contained in this report represents waste generation in Tennessee

  17. Dynamic effects of tank waste aging on radionuclide-complexant interactions. 1998 annual progress report

    International Nuclear Information System (INIS)

    Arterburn, J.B.; Chamberlin, R.

    1998-01-01

    'The overall objective of this project is to provide a scientific basis for safely processing complexant-containing high-level tank wastes for disposal. The key goals are to identify a means to prepare realistic complexant-containing tank waste simulants, and to use those simulants to determine the relative importance of organic complexants and their breakdown products on the partitioning of important radionuclides. These goals will be accomplished by artificially aging complexant-containing tank waste simulants using microwave, ultrasound, and photolysis techniques. The simulants will be compared to samples of actual Hanford tank wastes to determine the most realistic aging method, on the basis of the organic fragmentation and the partitioning behavior of the important radionuclides 90 Sr, 99 Tc, and 239 Pu. Also, the authors will use their simulant aging process to investigate the relative effects of chelator degradation products on the partitioning of important radionuclides from the waste. Using NMR-active labels in the chelators, they will use a combinatorial approach of generating multiple chelator fragments in a single experiment and then determining which fragments have a negative effect on the separations chemistry. The successful completion of this goal will specifically identify the most problematic organic fragments in complexant-containing waste and provide the basis for developing successful treatment strategies for these wastes. This report summarizes work carried out at Los Alamos during the first 8 months of a 3-year project.'

  18. Waste-Form Development Program. Annual progress report, October 1981-September 1982

    Energy Technology Data Exchange (ETDEWEB)

    Neilson, R.M. Jr.; Colombo, P.

    1982-09-01

    Low-level wastes (LLW) at nuclear facilities have traditionally been solidified using portland cement (with and without additives). Urea-formaldehyde has been used for LLW solidification while bitumen (asphalt) and thermosetting polymers will be applied to domestic wastes in the near future. Operational difficulties have been observed with each of these solidification agents. Such difficulties include incompatibility with waste constitutents inhibiting solidification, premature setting, free standing water and fires. Some specific waste types have proven difficult to solidify with one or more of the contemporary agents. Similar problems are also anticipated for the solidification of new wastes, which are generated using advanced volume reduction technologies, and with the application of additional agents which may be introduced in the near future for the solidification of LLW. In the Waste Form Development program, contemporary solidification agents are being investigated relative to their potential applications to major fuel cycle and non-fuel cycle LLW streams. The range of conditions under which these solidification agents can be satisfactorily applied to specific LLW streams is being determined. These studies are primarily directed towards defining operating parameters for both improved solidification of problem wastes such as ion exchange resins, organic liquids and oils for which prevailing processes, as currently employed, appear to be inadequate, and solidification of new LLW streams including high solids content evaporator concentrates, dry solids, and incinerator ash generated from advanced volume reduction technologies. Solidified waste forms are tested and evaluated to demonstrate compliance with waste form performance and shallow land burial (SLB) acceptance criteria and transportation requirements (both as they currently exist and as they are anticipated to be modified with time).

  19. UNITED STATES DEPARTMENT OF ENERGY OFFICE OF ENVIRONMENTAL MANAGEMENT WASTE PROCESSING ANNUAL TECHNOLOGY DEVELOPMENT REPORT 2008

    Energy Technology Data Exchange (ETDEWEB)

    Bush, S.

    2009-11-05

    The Office of Waste Processing identifies and reduces engineering and technical risks and uncertainties of the waste processing programs and projects of the Department of Energy's Environmental Management (EM) mission through the timely development of solutions to technical issues. The risks, and actions taken to mitigate those risks, are determined through technology readiness assessments, program reviews, technology information exchanges, external technical reviews, technical assistance, and targeted technology development and deployment. The Office of Waste Processing works with other DOE Headquarters offices and project and field organizations to proactively evaluate technical needs, identify multi-site solutions, and improve the technology and engineering associated with project and contract management. Participants in this program are empowered with the authority, resources, and training to implement their defined priorities, roles, and responsibilities. The Office of Waste Processing Multi-Year Program Plan (MYPP) supports the goals and objectives of the U.S. Department of Energy (DOE) - Office of Environmental Management Engineering and Technology Roadmap by providing direction for technology enhancement, development, and demonstration that will lead to a reduction of technical risks and uncertainties in EM waste processing activities. The MYPP summarizes the program areas and the scope of activities within each program area proposed for the next five years to improve safety and reduce costs and environmental impacts associated with waste processing; authorized budget levels will impact how much of the scope of activities can be executed, on a year-to-year basis. Waste Processing Program activities within the Roadmap and the MYPP are described in these seven program areas: (1) Improved Waste Storage Technology; (2) Reliable and Efficient Waste Retrieval Technologies; (3) Enhanced Tank Closure Processes; (4) Next-Generation Pretreatment Solutions; (5

  20. Waste-Form Development Program. Annual progress report, October 1981-September 1982

    International Nuclear Information System (INIS)

    Neilson, R.M. Jr.; Colombo, P.

    1982-09-01

    Low-level wastes (LLW) at nuclear facilities have traditionally been solidified using portland cement (with and without additives). Urea-formaldehyde has been used for LLW solidification while bitumen (asphalt) and thermosetting polymers will be applied to domestic wastes in the near future. Operational difficulties have been observed with each of these solidification agents. Such difficulties include incompatibility with waste constitutents inhibiting solidification, premature setting, free standing water and fires. Some specific waste types have proven difficult to solidify with one or more of the contemporary agents. Similar problems are also anticipated for the solidification of new wastes, which are generated using advanced volume reduction technologies, and with the application of additional agents which may be introduced in the near future for the solidification of LLW. In the Waste Form Development program, contemporary solidification agents are being investigated relative to their potential applications to major fuel cycle and non-fuel cycle LLW streams. The range of conditions under which these solidification agents can be satisfactorily applied to specific LLW streams is being determined. These studies are primarily directed towards defining operating parameters for both improved solidification of problem wastes such as ion exchange resins, organic liquids and oils for which prevailing processes, as currently employed, appear to be inadequate, and solidification of new LLW streams including high solids content evaporator concentrates, dry solids, and incinerator ash generated from advanced volume reduction technologies. Solidified waste forms are tested and evaluated to demonstrate compliance with waste form performance and shallow land burial (SLB) acceptance criteria and transportation requirements (both as they currently exist and as they are anticipated to be modified with time)

  1. United States Department Of Energy Office Of Environmental Management Waste Processing Annual Technology Development Report 2008

    International Nuclear Information System (INIS)

    Bush, S.

    2009-01-01

    The Office of Waste Processing identifies and reduces engineering and technical risks and uncertainties of the waste processing programs and projects of the Department of Energy's Environmental Management (EM) mission through the timely development of solutions to technical issues. The risks, and actions taken to mitigate those risks, are determined through technology readiness assessments, program reviews, technology information exchanges, external technical reviews, technical assistance, and targeted technology development and deployment. The Office of Waste Processing works with other DOE Headquarters offices and project and field organizations to proactively evaluate technical needs, identify multi-site solutions, and improve the technology and engineering associated with project and contract management. Participants in this program are empowered with the authority, resources, and training to implement their defined priorities, roles, and responsibilities. The Office of Waste Processing Multi-Year Program Plan (MYPP) supports the goals and objectives of the U.S. Department of Energy (DOE) - Office of Environmental Management Engineering and Technology Roadmap by providing direction for technology enhancement, development, and demonstration that will lead to a reduction of technical risks and uncertainties in EM waste processing activities. The MYPP summarizes the program areas and the scope of activities within each program area proposed for the next five years to improve safety and reduce costs and environmental impacts associated with waste processing; authorized budget levels will impact how much of the scope of activities can be executed, on a year-to-year basis. Waste Processing Program activities within the Roadmap and the MYPP are described in these seven program areas: (1) Improved Waste Storage Technology; (2) Reliable and Efficient Waste Retrieval Technologies; (3) Enhanced Tank Closure Processes; (4) Next-Generation Pretreatment Solutions; (5

  2. Study on the establishment of technical standards of radioactive wastes (annual report)

    International Nuclear Information System (INIS)

    Kim, Jhin Wung; Hwang, Y. S.; Kim, S. H.; Yoo, J. H.; Lee, I. H.; Yang, H. B.; Rhim, J. K.

    1997-03-01

    From 1989, KAERI and KINS have worked together to set up national regulations to safely manage radioactive wastes. This year project covers 3 items : 1) post-closure surveillance criteria and closure criteria for disposal of LLW wastes, 2) standard format and contents of safety analysis report for spent fuel interim storage, and 3) review of existing regulations. Results from detailed research shall be used to set up the MOST notices on the safe management of radioactive wastes. Even though this project has been stopped after the national rearrangement on the management of LLW, KINS which jointly has studied this project shall independently study it in the future. (author)

  3. Environmental surveillance for Waste Management Facilities at the Idaho National Engineering Laboratory. Annual report 1994

    Energy Technology Data Exchange (ETDEWEB)

    Wright, K.C.; Wilhelmsen, R.N.; Borsella, B.W.; Miles, M.

    1995-08-01

    This report describes calendar year 1994 environmental surveillance activities of Environmental Monitoring of Lockheed Martin Idaho Technologies, performed at Waste Management Facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Included are results of the sampling performed by the Radiological Environmental Surveillance Program, INEL Environmental Surveillance Program, and the United States Geological Survey. The primary purposes of monitoring are to evaluate environmental conditions, to provide and interpret data, to ensure compliance with applicable regulations or standards, and to ensure protection of human health and the environment. This report compares 1994 environmental surveillance data with US Department of Energy derived concentration guides and with data from previous years.

  4. 1994 annual report on low-level radioactive waste management progress

    International Nuclear Information System (INIS)

    1995-04-01

    This report for calendar year 1994 summarizes the progress that states and compact regions made during the year in establishing new low-level radioactive waste disposal facilities. Although events that have occurred in 1995 greatly alter the perspective in terms of storage versus disposal, the purpose of this report is to convey the concerns as evidenced during calendar year 1994. Significant developments occurring in 1995 are briefly outlined in the transmittal letter and will be detailed in the report for calendar year 1995. The report also provides summary information on the volume of low-level radioactive waste received for disposal in 1994 by commercially operated low-level radioactive waste disposal facilities, and is prepared 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

  5. Reactivity of peroxynitrite: Implications for Hanford waste management and remediation. 1998 annual progress report

    Energy Technology Data Exchange (ETDEWEB)

    Lymar, S.; Wishart, J.

    1998-06-01

    'The broad objective of this project is to provide quantitative mechanistic information relevant to: (i) the extent and nature of radiation-induced chemical modification of the nuclear defense waste that occurs during storage, and (ii) the extent of accumulation of peroxynitrite in the waste and its potential use in remediation. Within this context, the specific goals are: To determine the radiochemical yields of peroxynitrite in chemical mixtures simulating the various phases (salt cake, slurry, supernatant) of radioactive waste; Through mechanistic studies of metal- and CO{sub 2}-catalyzed oxidations by peroxynitrite, to estimate the extent of peroxynitrite-mediated oxidative degradation of organic waste components and determine the feasibility of using peroxynitrite in remediation technologies, e.g., for the destruction of organic complexants and the removal of chromium for more efficient vitrification. This report summarizes work after the first year of a three-year project.'

  6. Liquid and Gaseous Waste Operations Department annual operating report, CY 1995

    International Nuclear Information System (INIS)

    Maddox, J.J.; Scott, C.B.

    1996-03-01

    This report describes the operating activities, upgrade activities, maintenance, and other activities regarding liquid and gaseous low level radioactive waste management at the Oak Ridge National Laboratory. Miscellaneous activities include training, audits, tours, and environmental restoration support

  7. High-level waste-basalt interactions. Annual progress report, February 1, 1977--September 30, 1977

    Energy Technology Data Exchange (ETDEWEB)

    McCarthy, G.J.; Scheetz, B.E.

    1978-05-01

    Commercial radioactive waste can be placed under ground in a basalt repository to contain significant amounts of radioactive decay heat for the first hundred or so years, which constitutes the ''thermal period'' of waste isolation, if the feasibility is determined that a basalt geology is a suitable medium for storage of radioactive wastes. Several physical-chemical changes analogous to natural geochemical processes can occur in and around this repository during the thermal period. The waste canister can act as a heat source and cause changes in the mineralogy and properties of the surrounding basalts. Geochemically, this is ''contact metamorphism.'' This phenomenon needs to be investigated because it could affect the behavior of the basalt with regard to migration of long-lived radionuclides away from the immediate repository. It is well known that even the relatively low-grade hydrothermal conditions possible in the repository (temperatures up to 400 degrees Centigrade; pressures up to 300 bars) can cause extensive modifications in rocks and minerals. At the end of the thermal period, the residue of the original waste plus the waste-basalt interaction products would constitute the actual waste form (or ''source term'') subject to the low-temperature leaching and migration processes under investigation in other laboratories. During the last eight months of fiscal year 1977, a program was initiated at The Pennsylvania State University which had as its objective the determination of the nature and implication of any chemical or mineralogical changes in, or interactions between, each candidate radioactive waste form and representative Columbia River Basalt under the various relevant repository conditions during the thermal period. Results of these investigations are given.

  8. High-level waste-basalt interactions. Annual progress report, February 1, 1977--September 30, 1977

    International Nuclear Information System (INIS)

    McCarthy, G.J.; Scheetz, B.E.

    1978-05-01

    Commercial radioactive waste can be placed under ground in a basalt repository to contain significant amounts of radioactive decay heat for the first hundred or so years, which constitutes the ''thermal period'' of waste isolation, if the feasibility is determined that a basalt geology is a suitable medium for storage of radioactive wastes. Several physical-chemical changes analogous to natural geochemical processes can occur in and around this repository during the thermal period. The waste canister can act as a heat source and cause changes in the mineralogy and properties of the surrounding basalts. Geochemically, this is ''contact metamorphism.'' This phenomenon needs to be investigated because it could affect the behavior of the basalt with regard to migration of long-lived radionuclides away from the immediate repository. It is well known that even the relatively low-grade hydrothermal conditions possible in the repository (temperatures up to 400 degrees Centigrade; pressures up to 300 bars) can cause extensive modifications in rocks and minerals. At the end of the thermal period, the residue of the original waste plus the waste-basalt interaction products would constitute the actual waste form (or ''source term'') subject to the low-temperature leaching and migration processes under investigation in other laboratories. During the last eight months of fiscal year 1977, a program was initiated at The Pennsylvania State University which had as its objective the determination of the nature and implication of any chemical or mineralogical changes in, or interactions between, each candidate radioactive waste form and representative Columbia River Basalt under the various relevant repository conditions during the thermal period. Results of these investigations are given

  9. Air and Waste Management Association 86th annual meeting and exhibition

    International Nuclear Information System (INIS)

    Anon.

    1993-01-01

    This book presents conference abstracts from the 1993 meeting of the Air and Waste Management Association. General topics include air pollutants and their modeling, transport, monitoring, and control; atmospheric chemistry; air pollution sources, including mobile and stationary pollutant sources; health risks of air pollution; waste management, processing, and disposal; urban air quality; remedial actions for contaminated sites; air pollution in Europe; meteorolgy and terrain considerations in air pollution

  10. Research and development for treatment and disposal technologies of TRU waste. JFY 2007 annual report

    International Nuclear Information System (INIS)

    Kamei, Gento; Honda, Akira; Mihara, Morihiro; Oda, Chie; Murakami, Hiroshi; Masuda, Kenta; Yamaguchi, Kohei; Matsuda, Setsuro; Ichige, Satoru; Takahashi, Kuniaki; Meguro, Yoshihiro; Yamaguchi, Hiromi; Sakakibara, Tetsuro; Sasaki, Toshiki

    2008-11-01

    Based on Japanese governmental policy and general scheme, research and development of geological disposal technology for TRU waste has been proceeding to improve reliability of the safety assessment of the co-locational disposal of TRU waste and of HLW, to expand the basement of generic safety assessment, and to develop the alternative technology to cope with the broad geologic environment of Japan. Japan Atomic Energy Agency is dealing with the assignments in the governmental generic scheme. We report here the progress of the studies at the end of H19 (2007) Japanese fiscal year, which are (1) treatment and packaging of TRU waste including applicability of calcination for unpacking and sorting of wastes, characterization and inspection methodology of TRU waste, (2) evaluation of long-term mechanical stability in the near-field including development of a creep mode of rock and analyses of mechanical behavior of TRU waste repository, (3) performance assessment of the disposal system including data acquisition and preparation on radionuclides migration, cementitious material alteration, bentonite and hostrock alteration with alkaline solution and nitrate effect, and (4) alternative technology development including decomposition of nitrate. (author)

  11. Semantic Gaps Are Dangerous

    DEFF Research Database (Denmark)

    Ejstrup, Michael; le Fevre Jakobsen, Bjarne

    Semantic gaps are dangerous Language adapts to the environment where it serves as a tool to communication. Language is a social agreement, and we all have to stick to both grammaticalized and non-grammaticalized rules in order to pass information about the world around us. As such language develops...... unpolite language and tend to create dangerous relations where specialy language creates problems and trouble that could be avoided if we had better language tools at hand. But we have not these tools of communication, and we are in a situation today where media and specially digital and social media......, supported by new possibilities of migration, create dangerous situations. How can we avoid these accidental gaps in language and specially the gaps in semantic and metaphoric tools. Do we have to keep silent and stop discusing certain isues, or do we have other ways to get acces to sufficient language tools...

  12. Development of inorganic ion exchangers for nuclear waste remediation. 1997 annual progress report

    International Nuclear Information System (INIS)

    Clearfield, A.; Collins, J.L.; Egan, B.Z.

    1997-01-01

    'In this research program, Oak Ridge National Laboratory (ORNL) is collaborating with Texas A and M University in the development of highly selective inorganic ion exchangers for the removal of cesium and strontium from nuclear tank-waste and from groundwater. Inorganic ion exchangers are developed and characterized at Texas A and M University; ORNL is involved in preparing the powders in engineered forms and testing the performance of the sorbents in actual nuclear waste solutions. The Texas A and M studies are divided into two main categories: (1) exchangers for tank wastes and (2) exchangers for groundwater remediation. These are subdivided into exchangers for use in acid and alkaline solutions for tank wastes and those that can be recycled for use in groundwater remediation. The exchangers will also be considered for in situ immobilization of radionuclides. The approach will involve a combination of exchanger synthesis, structural characterization, and ion exchange behavior. ORNL has developed a technique for preparing inorganic ion exchangers in the form of spherules by a gel-sphere internal gelation process. This technology, which was developed and used for making nuclear fuels, has the potential of greatly enhancing the usability of many other special inorganic materials because of the improved flow dynamics of the spherules. Also, pure inorganic spherules can be made without the use of binders. ORNL also has access to actual nuclear waste in the form of waste tank supernatant solutions for testing the capabilities of the sorbents for removing the cesium and strontium radionuclides from actual waste solutions. The ORNL collaboration will involve the preparation of the powdered ion exchangers, developed and synthesized at Texas A and M, in the form of spherules, and evaluating the performance of the exchangers in real nuclear waste solutions. Selected sorbents will be provided by Texas A and M for potential incorporation into microspheres, and the performance

  13. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Annual Meeting Clinical Education Practice Management Member Services Advocacy Foundation About Subspecialties & More Eye Health Home Annual Meeting Clinical Education Practice Management Member Services Advocacy Foundation About Subspecialties & More Academy Publications EyeNet Ophthalmology ...

  14. Air transport of dangerous goods

    OpenAIRE

    Gregor, Petr

    2009-01-01

    Diploma thesis topic deals with air transport of dangerous goods. In the beginning part it describes air cargo transportation itself as well as the main characteristics. Thesis introduces organizations involved in international transport of dangerous goods. Next part of diploma thesis reveals project analysis of air transportation of dangerous goods in respect of IATA Dangerous Goods regulations and procedures. Thesis also covers introduction to air transportation of dangerous goods in specif...

  15. Testing and evaluation of solidified high-level waste forms. Joint annual progress report 1983

    International Nuclear Information System (INIS)

    Malow, G.

    1985-01-01

    A second joint programme of the European Atomic Community was started in 1981 under the indirect action programme (1980-84), Action No 5 'Testing and evaluation of the properties of various potential materials for immobilizing high activity waste'. The overall objective of the research is to test various European potential solidified high-level radioactive waste forms so as to predict their behaviour after disposal. The most important aspect is to produce data to calculate the activity release from the waste products under the attack of various aqueous solutions. The experiments were partly performed under waste repository relevant conditions and partly under simplified conditions for investigating basic activity release mechanisms. The topics of the programme were: (i) studies of basic leaching mechanisms; (ii) studies of hydrothermal leaching and surface attack of waste glasses; (iii) leach test carried out in contact with granite at low water flow rates; (iv) static leach tests with specimen surrounded by canister and backfill materials; (v) specific isotope leach tests in slowly flowing water; (vi) leach test of actinide spiked samples; (vii) leach tests of highly radioactive samples; (viii) leach tests of alpha radiation stability; (ix) studies of mechanical stability; (x) studies of mineral phases as model compounds and phase relations

  16. Annual Waste Minimization Summary Report for the National Nuclear Security Administration Nevada Site Office

    International Nuclear Information System (INIS)

    Alfred J. Karns

    2007-01-01

    This report summarizes the waste minimization efforts undertaken by National Security Technologies, LLC (NSTec), for the U. S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NNSA/NSO), during CY06. This report was developed in accordance with the requirements of the Nevada Test Site (NTS) Resource Conservation and Recovery Act (RCRA) Permit ((number s ign)NEV HW0021) and as clarified in a letter dated April 21, 1995, from Paul Liebendorfer of the Nevada Division of Environmental Protection to Donald Elle of the DOE, Nevada Operations Office. The NNSA/NSO Pollution Prevention (P2) Program establishes a process to reduce the volume and toxicity of waste generated by the NNSA/NSO and ensures that proposed methods of treatment, storage, and/or disposal of waste minimize potential threats to human health and the environment. The following information provides an overview of the P2 Program, major P2 accomplishments during the reporting year, a comparison of the current year waste generation to prior years, and a description of efforts undertaken during the year to reduce the volume and toxicity of waste generated by the NNSA/NSO

  17. Colloidal agglomerates in tank sludge: Impact on waste processing. 1997 annual progress report

    International Nuclear Information System (INIS)

    Virden, J.W.

    1997-01-01

    'Disposal of millions of gallons of existing radioactive wastes is a major remediation problem for the Department of Energy (DOE). Although radionuclides are the most hazardous waste constituents. the components of greatest concern from a waste processing standpoint are insoluble sludges consisting of submicron colloidal particles. Depending on processing conditions, these colloidal particles can form agglomerate networks that could clog transfer lines or interfere with solid-liquid separations such as settle-decant operations. Under different conditions, the particles can be dispersed to form very fine suspended particles that will not create sediment in settle- decant steps and that can foul and contaminate downstream treatment components including ion exchangers or filtrations systems. Given the wide range of tank chemistries present at Hanford and other DOE sites, it is impractical to measure the properties of all potential processing conditions to design effective treatment procedures. Instead. a framework needs to be established to allow sludge property trends to be predicted on a sound scientific basis. The scientific principles of greatest utility in characterizing, understanding, and controlling the physical properties of sludge fall in the realm of colloid chemistry. The objectives of this work are to accomplish the following: understand the factors controlling the nature and extent of colloidal agglomeration under expected waste processing conditions determine how agglomeration phenomena influence physical properties relevant to waste processing including rheology, sedimentation. and filtration develop strategies for optimizing processing conditions via control of agglomeration phenomena.'

  18. Task 1.6 -- Mixed waste treatment. Semi-annual report, January 1--June 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    Rindt, J.R.

    1997-08-01

    Mixed-waste sites make up the majority of contaminated sites, yet remediation techniques used at such sites often target only the most prevalent contaminant. A better understanding of site situation (i.e., most common types of contamination), current remediation techniques, and combinations of techniques would provide insight into areas in which further research should be performed. The first half of this task program year consisted of a survey of common types of mixed-wastes sites and a detailed literature search of the remediation techniques and combinations of techniques that were currently available. From this information, an assessment of each of the techniques was made and combined into various ways appropriate to mixed-waste protocol. This activity provided insight into areas in which further research should be performed.

  19. The problem of industrial wastes

    International Nuclear Information System (INIS)

    Hamdan, Fouad

    1998-01-01

    The paper is the result of a feasibility study conducted for the Green peace Office in Lebanon. The overall goal of the study was to work towards implementing a national waste management plan and to combat the import of hazardous wastes from developing countries.The author focuses on the illegal trade of industrial wastes from developed to under developed countries. The trade of toxic wastes causes on environmental pollution. As for Lebanese industries, the main problem is toxic industrial wastes. About 4000 tones/day of domestic wastes are produced in Lebanon. 326000 tones of industrial wastes contain toxic substances are annually produced and wastes growth rate is expected to increase to one million tone/year in 2010. A disaster is threatening Lebanon especially that no policy were taken to deal with the huge growth of wastes. This problem affect on population health especially in the region of Bourj Hammoud. Analysis of ground water in the region of Chekka, confirm the existence of water pollution caused by toxic materials In addition, analysis of Petro coke used in the National Lebanese Cement Industry, contain a high rate of Polycyclic Aromatic Hydrocarbons. Green peace is aware of the danger of wastes in air, water and land pollution and preventing environment of any source of pollution this will certainly lead to a sustainable development of the country

  20. The Aube low- and medium activity waste storage Centre. 2009 annual report

    International Nuclear Information System (INIS)

    2010-01-01

    After a brief presentation of the ANDRA (the French national agency for the management of radioactive wastes), this report presents the Aube storage Centre installations and main results for the year 2009. It describes the various measures implemented and obtained results in terms of nuclear safety and of radioprotection. It indicates the different incidents which occurred in these installations in 2009, presents the activities in the field of control of the environment and of the releases. It describes how wastes are managed and actions undertaken for information transparency

  1. TRU waste form studies with special reference to iron-enriched basalt: 1980. Annual report

    International Nuclear Information System (INIS)

    Flinn, J.E.; Henslee, S.P.; Kelsey, P.V. Jr.

    1981-06-01

    Material studies were performed on iron-enriched basalt (IEB) as a waste form containment medium for transuranic wastes. Specimens from laboratory scale, as well as large scale melts, were used in the evaluation. The studies included melting and casting, slag-refractory interaction, slag fruit assessments, volatility of sodium salts from IEB melts, chemical and structure homogeneity, metallic dissolution tests, physical properties, and devitrification associated with the development of mineral phases. In addition, durability tests, which included leaching and mechanical behavior, were performed

  2. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Ophthalmologist Patient Stories Español Eye Health / News Halloween Hazard: The Hidden Dangers of Buying Decorative Contact Lenses ... One Use Facts About Colored Contacts and Halloween Safety Colored Contact Lens Facts Over-the-Counter Costume ...

  3. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Health / News Halloween Hazard: The Hidden Dangers of Buying Decorative Contact Lenses Without a Prescription Leer en Español: Peligros asociados con los lentes de contacto de color Sep. 26, 2013 It started as an impulsive buy from a souvenir shop, but 10 hours ...

  4. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... an Ophthalmologist Patient Stories Español Eye Health / News Halloween Hazard: The Hidden Dangers of Buying Decorative Contact ... After One Use Facts About Colored Contacts and Halloween Safety Colored Contact Lens Facts Over-the-Counter ...

  5. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Tips & Prevention News Ask an Ophthalmologist Patient Stories Español Eye Health / News Halloween Hazard: The Hidden Dangers ... Decorative Contact Lenses Without a Prescription Leer en Español: Peligros asociados con los lentes de contacto de ...

  6. Dangerous Raw Oysters

    Centers for Disease Control (CDC) Podcasts

    2013-08-05

    Dr. Duc Vugia, chief of the Infectious Diseases Branch at the California Department of Public Health, discusses the dangers of eating raw oysters.  Created: 8/5/2013 by National Center for Emerging and Zoonotic Infectious Diseases (NCEZID).   Date Released: 8/7/2013.

  7. FY2010 ANNUAL REVIEW E-AREA LOW-LEVEL WASTE FACILITY PERFORMANCE ASSESSMENT AND COMPOSITE ANALYSIS

    Energy Technology Data Exchange (ETDEWEB)

    Butcher, T.; Swingle, R.; Crapse, K.; Millings, M.; Sink, D.

    2011-01-01

    The E-Area Low-Level Waste Facility (ELLWF) consists of a number of disposal units described in the Performance Assessment (PA)(WSRC, 2008b) and Composite Analysis (CA)(WSRC, 1997; WSRC, 1999): Low-Activity Waste (LAW) Vault, Intermediate Level (IL) Vault, Trenches (Slit Trenches [STs], Engineered Trenches [ETs], and Component-in-Grout [CIG] Trenches), and Naval Reactor Component Disposal Areas (NRCDAs). This annual review evaluates the adequacy of the approved 2008 ELLWF PA along with the Special Analyses (SAs) approved since the PA was issued. The review also verifies that the Fiscal Year (FY) 2010 low-level waste (LLW) disposal operations were conducted within the bounds of the PA/SA baseline, the Savannah River Site (SRS) CA, and the Department of Energy (DOE) Disposal Authorization Statement (DAS). Important factors considered in this review include waste receipts, results from monitoring and research and development (R&D) programs, and the adequacy of controls derived from the PA/SA baseline. Sections 1.0 and 2.0 of this review are a summary of the adequacy of the PA/SA and CA, respectively. An evaluation of the FY2010 waste receipts and the resultant impact on the ELLWF is summarized in Section 3.1. The results of the monitoring program, R&D program, and other relevant factors are found in Section 3.2, 3.3 and 3.4, respectively. Section 4.0 contains the CA annual determination similarly organized. SRS low-level waste management is regulated under DOE Order 435.1 (DOE, 1999a) and is authorized under a DAS as a federal permit. The original DAS was issued by the DOE-Headquarters (DOE-HQ) on September 28, 1999 (DOE, 1999b) for the operation of the ELLWF and the Saltstone Disposal Facility (SDF). The 1999 DAS remains in effect for the regulation of the SDF. Those portions of that DAS applicable to the ELLWF were superseded by revision 1 of the DAS on July 15, 2008 (DOE, 2008b). The 2008 PA and DAS were officially implemented by the facility on October 31, 2008

  8. Proceedings of the Fifth Annual Participants' Information Meeting: DOE Low-Level Waste Management Program

    International Nuclear Information System (INIS)

    1983-12-01

    The meeting consisted of the following six sessions: (1) plenary session I; (2) disposal technology; (3) characteristics and treatment of low-level waste; (4) environmental aspects and performance prediction; (5) overall summary sessions; and (6) plenary session II. Fifty two papers of the papers presented were processed for inclusion in the Energy Data Base

  9. Task 3 - Pyrolysis of plastic waste. Semi-annual report, April 1- September 30, 1997

    International Nuclear Information System (INIS)

    Ness, R.O.; Aulich, T.R.

    1997-09-01

    The Energy and Environmental Research Center is developing a technology for the thermal decomposition of high-organic-content, radionuclide-contaminated mixed wastes and spent (radioactive) ion-exchange resins from the nuclear power industry that will enable the separation and concentration of radionuclides as dry particulate solids and the generation of nonradioactive condensable and noncondensable gas products. Successful application of the technology will enable a significant volume reduction of radioactive waste and the production of an inexpensively disposable nonradioactive organic product. The project objective is to develop and demonstrate the commercial viability of a continuous thermal decomposition process that can fulfill the following requirements: separate radionuclides from radioactive waste streams containing a variety of types and levels of polymers, chlorinated species, and other organics, including rubber, oils, resins, and cellulosic-based materials; concentrate radionuclides in a homogeneous, dry particulate product that can be recovered, handled, and disposed of efficiently and safely; separate and recover any chlorine present (as PVC, chlorinated solvents, or inorganic chlorine) in the contaminated mixed-waste stream; and yield a nonradioactive, low-chlorine-content, condensable organic product that can be economically disposed. Progress is described

  10. Research and development on ultimate storage of radioactive wastes. Annual report, 1977

    International Nuclear Information System (INIS)

    The present deals with the activities of the Entwicklungsgemeinschaft Tieflagerung which was founded on 1 January 1978 and consists of institutes, branches and working groups both of the Gesellschaft fuer Strahlen- und Umweltforschung mbH Muenchen and the Kernforschungszentrum Karlsruhe which are engaged in the field of radioactive waste disposal. This report presents a survey of the work performed in that field in 1977. The mining and construction work is discussed, which was carried out both underground and above at the Asse Salt Mine near Remlingen and which was done for repair, maintenance, and expansion of operation in accordance with its future purpose. The experimental disposal of low-level wastes on the 750-m and 725-m level was continued in the time period under review. Only seven drums of intermediate-level waste were experimentally disposed of in 1977. The disposal field and the operational equipment for the single test disposal of spent fuel elements from the AVR reactor were completed and are ready for operation. Due to legal, political, and transport problems there is a delay of the start of the test disposal. The mining of the prototype cavity was finished reaching a fina depth of 996.1 m. Moreover, the report gives information on means for radiation protection and the results of the environmental surveillance program. Also the present status of the research activities and their results, especially in the field of disposal of high-level waste, rock mechanics, and safety studies is reported

  11. UNITED STATES DEPARTMENT OF ENERGY WASTE PROCESSING ANNUAL TECHNOLOGY DEVELOPMENT REPORT 2007

    Energy Technology Data Exchange (ETDEWEB)

    Bush, S

    2008-08-12

    The Office of Environmental Management's (EM) Roadmap, U.S. Department of Energy--Office of Environmental Management Engineering & Technology Roadmap (Roadmap), defines the Department's intent to reduce the technical risk and uncertainty in its cleanup programs. The unique nature of many of the remaining facilities will require a strong and responsive engineering and technology program to improve worker and public safety, and reduce costs and environmental impacts while completing the cleanup program. The technical risks and uncertainties associated with cleanup program were identified through: (1) project risk assessments, (2) programmatic external technical reviews and technology readiness assessments, and (3) direct site input. In order to address these needs, the technical risks and uncertainties were compiled and divided into the program areas of: Waste Processing, Groundwater and Soil Remediation, and Deactivation and Decommissioning (D&D). Strategic initiatives were then developed within each program area to address the technical risks and uncertainties in that program area. These strategic initiatives were subsequently incorporated into the Roadmap, where they form the strategic framework of the EM Engineering & Technology Program. The EM-21 Multi-Year Program Plan (MYPP) supports the goals and objectives of the Roadmap by providing direction for technology enhancement, development, and demonstrations that will lead to a reduction of technical uncertainties in EM waste processing activities. The current MYPP summarizes the strategic initiatives and the scope of the activities within each initiative that are proposed for the next five years (FY2008-2012) to improve safety and reduce costs and environmental impacts associated with waste processing; authorized budget levels will impact how much of the scope of activities can be executed, on a year-to-year basis. As a result of the importance of reducing technical risk and uncertainty in the EM Waste

  12. Proceedings of the fourth annual participants' information meeting, DOE Low-Level Waste Management Program

    Energy Technology Data Exchange (ETDEWEB)

    Large, D.E.: Mezga, L.J.; Stratton, L.E.; Rose, R.R. (comps.)

    1982-10-01

    The Fourth Annual Participants' Information Meeting of the Department of Energy Low-Level Waste Management Program was held in Denver, Colorado, August 31 to September 2, 1982. The purpose of the meeting was to report and evaluate technology development funded by the program and to examine mechanisms for technology transfer. The meeting consisted of an introductory plenary session, followed by two concurrent overview sessions and then six concurrent technical sessions. There were two group meetings to review the findings of the technical sessions. The meeting concluded with a plenary summary session in which the major findings of the meeting were addressed. All papers have been abstracted and indexed for the Energy Data Base.

  13. Power plant waste heat utilization in aquaculture. Semi-annual report, No. 2, 1 November 1977--1 June 1978

    Energy Technology Data Exchange (ETDEWEB)

    Guerra, C.R.; Godfriaux, B.L.

    1978-06-01

    The principal objective is to evaluate, at proof-of-concept scale, the potential of intensive aquaculture operations using power plant thermal discharges to enhance productivity. The field experiments involve the rearing of rainbow trout (Salmo gairdneri), channel catfish (Ictalurus punctatus) and American eel (Anguilla rostrata) for successive periods (semi-annual) in accordance with the temperature of the thermal effluents. Striped bass (Morone saxatilis) and the freshwater shrimp (Macrobrachium rosenbergii) are also being tested in smaller, laboratory size culture systems. The above mentioned species were selected because of their economic importance. They will be evaluated for food quality and marketability with the cooperation of potential commercial users. Aquaculture facilities were constructed at a steam electric generating plant for studies determining use for waste heat released into condenser cooling water. Growth rates, food conversion ratios, disease problems and mortality rates are being studied in the project. (Color illustrations reproduced in black and white) (Portions of this document are not fully legible)

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

    International Nuclear Information System (INIS)

    Yasue, Ken-ichi; Asamori, Koichi; Niwa, Masakazu; Hanamuro, Takahiro; Saito-Kokubu, Yoko; Sueoka, Shigeru; Makuuchi, Ayumu; Ikuta, Masafumi; Matsubara, Akihiro; Tamura, Hajimu; Kobori, Kazuo; Ishimaru, Tsuneari; Umeda, Koji

    2014-03-01

    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)

  15. Waste-Management Education and Research Consortium (WERC) annual progress report, 1992--1993

    International Nuclear Information System (INIS)

    1993-01-01

    This report contains the following appendices: Appendix A - Requirements for Undergraduate Level; Appendix B - Requirements for Graduate Level; Appendix C - Graduate Degree In Environmental Engineeringat New Mexico State University; Appendix D - Non-degree Certificate program; Appendix E - Curriculum for Associate Degree Program in Radioactive ampersand Hazardous Waste Materials; Appendix F - Curriculum for NCC Program in Earth ampersand Environmental Sciences; Appendix G - Brochure of 1992 Teleconference Series; Appendix H - Sites for Hazardous/Radioactive Waste Management Series; Appendix I - WERC Interactive Television Courses; Appendix J - WERC Research Seminar Series Brochures; Appendix K - Summary of Technology Development of the Third Year; Appendix L - List of Major Publications Resulting From WERC; Appendix M - Types of Equipment at WERC Laboratories; and Appendix N - WERC Newsletter Examples

  16. Waste-Management Education and Research Consortium (WERC) annual progress report, 1992--1993

    Energy Technology Data Exchange (ETDEWEB)

    Eiceman, Gary A.; King, J. Phillip; Smith, Geoffrey B.; Park, Su-Moon; Munson-McGee, Stuart H.; Rajtar, Jerzy; Chen, Z.; Johnson, James E.; Heger, A. Sharif; Martin, David W.; Wilks, Maureen E.; Schreyer, H. L.; Thomson, Bruce M.; Samani, Zohrab A.; Hanson, Adrian; Cadena, Fernando; Gopalan, Aravamudan; Barton, Larry L.; Sillerud, Laurel O.; Fekete, Frank A.; Rogers, Terry; Lindemann, William C.; Pigg, C. Joanne; Blake, Robert; Kieft, Thomas L.; Ross, Timothy J.; LaPointe, Joe L.; Khandan, Nirmala; Bedell, Glenn W.; Rayson, Gary D.; Leslie, Ian H.; Ondrias, Mark R.; Starr, Gregory P.; Colbaugh, Richard; Niemczyk, Thomas M.; Campbell, Andrew; Phillips, Fred; Wilson, John L.; Gutjahr, Allan; Sammis, T. W.; Steinberg, Stanly; Nuttall, H. E.; Genin, Joseph; Conley, Edgar; Aimone-Martin, Catherine T.; Wang, Ming L.; Chua, Koon Meng; Smith, Phillip; Skowland, Chris T.; McGuckin, Tom; Harrison, Glenn; Jenkins-Smith, Hank C.; Kelsey, Charles A.

    1993-02-15

    This report contains the following appendices: Appendix A - Requirements for Undergraduate Level; Appendix B - Requirements for Graduate Level; Appendix C - Graduate Degree In Environmental Engineeringat New Mexico State University; Appendix D - Non-degree Certificate program; Appendix E - Curriculum for Associate Degree Program in Radioactive Hazardous Waste Materials; Appendix F - Curriculum for NCC Program in Earth Environmental Sciences; Appendix G - Brochure of 1992 Teleconference Series; Appendix H - Sites for Hazardous/Radioactive Waste Management Series; Appendix I - WERC Interactive Television Courses; Appendix J - WERC Research Seminar Series Brochures; Appendix K - Summary of Technology Development of the Third Year; Appendix L - List of Major Publications Resulting From WERC; Appendix M - Types of Equipment at WERC Laboratories; and Appendix N - WERC Newsletter Examples.

  17. Waste-Management Education and Research Consortium (WERC) annual progress report, 1992--1993. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    1993-02-15

    This report contains the following appendices: Appendix A - Requirements for Undergraduate Level; Appendix B - Requirements for Graduate Level; Appendix C - Graduate Degree In Environmental Engineeringat New Mexico State University; Appendix D - Non-degree Certificate program; Appendix E - Curriculum for Associate Degree Program in Radioactive & Hazardous Waste Materials; Appendix F - Curriculum for NCC Program in Earth & Environmental Sciences; Appendix G - Brochure of 1992 Teleconference Series; Appendix H - Sites for Hazardous/Radioactive Waste Management Series; Appendix I - WERC Interactive Television Courses; Appendix J - WERC Research Seminar Series Brochures; Appendix K - Summary of Technology Development of the Third Year; Appendix L - List of Major Publications Resulting From WERC; Appendix M - Types of Equipment at WERC Laboratories; and Appendix N - WERC Newsletter Examples.

  18. 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.

  19. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Services Advocacy Foundation About Subspecialties & More Eye Health Home Annual Meeting Clinical Education Practice Management Member Services Advocacy Foundation About Subspecialties & ...

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

    International Nuclear Information System (INIS)

    Y. E.Townsend

    2001-01-01

    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

  1. The characterisation and immobilisation of Winfrith reactor (SGHWR) wastes - annual report September 1985

    International Nuclear Information System (INIS)

    Holland, T.R.; Lee, D.J.

    1985-09-01

    Progress is reported in a programme to characterise both the sludge wastes generated during operation and maintenance of the Winfrith SGHWR, and the solidified end product after cementation. The main programme includes the preparation of more representative simulant sludges, the effect of scale on process parameters and product properties, continued tests on cemented sludge, the active demonstration of sludge homogenisation, sludge dewatering, the characterisation of homogenised active sludge and data evaluation and report presentation. (UK)

  2. 1999 Annual Mixed Waste Management Facility Groundwater Correction - Action Report (Volumes I, II, and III)

    Energy Technology Data Exchange (ETDEWEB)

    Chase, J.

    2000-06-14

    This Corrective Action Report (CAR) for the Mixed Waste Management Facility (MWMF) is being prepared to comply with the Resource Conservation and Recovery Act (RCRA) Permit Number SC1 890 008 989, dated October 31, 1999. This CAR compiles and presents all groundwater sampling and monitoring activities that are conducted at the MWMF. As set forth in previous agreements with South Carolina Department of Health and Environmental Control (SCDHEC), all groundwater associated with the Burial Ground Complex (BGC) (comprised of the MWMF, Low-Level Radioactive Waste Disposal Facility, and Old Radioactive Waste Burial Ground) will be addressed under this RCRA Permit. This CAR is the first to be written for the MWMF and presents monitoring activities and results as an outcome of Interim Status and limited Permitted Status activities. All 1999 groundwater monitoring activities were conducted while the MWMF was operated during Interim Status. Changes to the groundwater monitoring program were made upon receipt of the RCRA Permit, where feasible. During 1999, 152 single-screened and six multi-screened groundwater monitoring wells at the BGC monitored groundwater quality in the uppermost aquifer as required by the South Carolina Hazardous Waste Management Regulations (SCHWMR), settlement agreements 87-52-SW and 91-51-SW, and RCRA Permit SC1 890 008 989. However, overall compliance with the recently issued RCRA Permit could not be implemented until the year 2000 due to the effective date of the RCRA Permit and scheduling of groundwater monitoring activities. Changes have been made to the groundwater monitoring network to meet Permit requirements for all 2000 sampling events.

  3. 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.

  4. Interfacial radiolysis effects in tank waste speciation. 1998 annual progress report

    International Nuclear Information System (INIS)

    Camaioni, D.; Meisel, D.; Orlando, T.M.

    1998-01-01

    'The purpose of this program is to deliver pertinent, fundamental information that can be used to make technically defensible decisions on safety issues and processing strategies associated with storage and clean up of DOE mixed chemical and radioactive wastes. The radioactive and chemical wastes present in DOE underground storage tanks contain complex mixtures of sludges, salts, and supernatant liquids. These mixtures, which contain a wide variety of oxide materials, aqueous solvents, and organic components, are constantly bombarded with gamma quanta, beta and alpha particles produced via the decay of radioactive isotopes. Currently, there is a vital need to understand radiolysis of organic and inorganic species present in mixed waste tanks because these processes: (a) produce mixtures of toxic, flammable, and potentially explosive gases (i.e., H 2 , N 2 O and volatile organics) (b) degrade organics, possibly to gas-generating organic fragments, even as the degradation reduces the hazards associated with nitrate-organic mixtures, (c) alter the surface chemistry of insoluble colloids in tank sludge, influencing sedimentation and the gas/solid interactions that may lead to gas entrapment phenomena. This report summarizes the technical achievements of a 3-year project that is now in its 2nd year. Progress in three areas is reported: (1) radiation effects at NaNO 3 crystal interfaces, (2) reactions of organic complexants with NO 2 in water, and (3) radiation effects in oxide particles.'

  5. The Waste-Management Education and Research Consortium (WERC) annual progress report, 1990--1991

    International Nuclear Information System (INIS)

    1991-01-01

    In February, 1990, the Secretary of Energy, James Watkins approved a grant for a waste (management) education and research consortium program by New Mexico State University (NMSU) to the US Department of Energy (DOE) . This program known by the acronym, ''WERC'' includes NMSU, the University of New Mexico (UNM), the New Mexico Institute of Mining and Technology (NMIMT), the Los Alamos National Laboratory and the Sandia National Laboratories. The program is designed to provide an integrated approach to the national need via the following: (1) Education in waste management by the Consortium universities resulting in graduate, undergraduate, and associate degrees with concentration in environmental management. The term waste management is used in a broad sense throughout this paper and includes all aspects of environmental management and environmental restoration. (2) Research programs at the leading edge, providing training to faculty and students and feeding into the education programs. (3) Education and research at the campuses, as well as from three field sites. (4) Ties with other multi-disciplinary university facilities. (5) Ties with two National Laboratories located in New Mexico. (6) Technology transfer and education via an existing fiber optic network, a proposed satellite link, and an existing state-wide extension program. (7) An outreach program to interest others in environmental management, especially precollege students, minority students and practitioners in the field. This report summarizes the accomplishments and status at the end of the first year

  6. The Waste-Management Education and Research Consortium (WERC) annual progress report, 1990--1991

    Energy Technology Data Exchange (ETDEWEB)

    None

    1991-02-25

    In February, 1990, the Secretary of Energy, James Watkins approved a grant for a waste (management) education and research consortium program by New Mexico State University (NMSU) to the US Department of Energy (DOE) . This program known by the acronym, WERC'' includes NMSU, the University of New Mexico (UNM), the New Mexico Institute of Mining and Technology (NMIMT), the Los Alamos National Laboratory and the Sandia National Laboratories. The program is designed to provide an integrated approach to the national need via the following: (1) Education in waste management by the Consortium universities resulting in graduate, undergraduate, and associate degrees with concentration in environmental management. The term waste management is used in a broad sense throughout this paper and includes all aspects of environmental management and environmental restoration. (2) Research programs at the leading edge, providing training to faculty and students and feeding into the education programs. (3) Education and research at the campuses, as well as from three field sites. (4) Ties with other multi-disciplinary university facilities. (5) Ties with two National Laboratories located in New Mexico. (6) Technology transfer and education via an existing fiber optic network, a proposed satellite link, and an existing state-wide extension program. (7) An outreach program to interest others in environmental management, especially precollege students, minority students and practitioners in the field. This report summarizes the accomplishments and status at the end of the first year.

  7. Aube's storage centre for low and intermediate level wastes: Annual report 2008

    International Nuclear Information System (INIS)

    2008-01-01

    After a presentation of the ANDRA (the French national Agency for radioactive waste management), its missions, its facilities, and its financing, this report reviews the activity of its storage centre for low and intermediate level wastes located on the territory of three towns in the Aube district. It briefly describes the facilities, the different categories of liquid effluents and their associated networks. It indicates some important figures characterizing the centre's operation. It describes the main safety objectives, technical measures and results in terms of radioprotection. It reports the main events in the relationship with the safety authority. It also briefly describes the incidents and accidents which occurred in 2008. It presents and specifies some results of the numerous environmental analyses performed around the centre (radioactivity measurements in air, water, milk, mushrooms, fishes, and so on), comments the radiologic impact of releases, and actions to improve these results. It gives assessments of the amount of produced wastes and describes their processing and management. Information actions are presented and the CHSCT (Committee of hygiene, safety, and working conditions) are reported

  8. La mesure du danger

    CERN Document Server

    Manceron, Vanessa; Revet, Sandrine

    2014-01-01

    La mesure du danger permet d’explorer des dangers de nature aussi diverse que la délinquance, la pollution, l’écueil maritime, la maladie ou l’attaque sorcellaire, l’extinction d’espèces animales ou végétales, voire de la Planète tout entière. Au croisement de la sociologie, de l’anthropologie et de l’histoire, les différents articles analysent les pratiques concrètes de mesure pour tenter de comprendre ce qui se produit au cours de l’opération d’évaluation du danger sans préjuger de la nature de celui-ci. L’anthropologie a contribué à la réflexion sur l’infortune en s’intéressant aux temporalités de l’après : maladies, catastrophes, pandémies, etc. et en cherchant à rendre compte de l’expérience des victimes, de leur vie ordinaire bouleversée, de la recomposition du quotidien. Elle s’intéresse aussi aux autres types de mesures, les savoirs incorporés, qui reposent sur l’odorat, la vue ou le toucher et ceux qui ressortent d’une épistémologie « non ...

  9. Potential dangers of cannabis.

    Science.gov (United States)

    Kaymakçalan, S

    1975-01-01

    Cannabis is not a harmless drug. The potential dangers of cannabis are briefly reviewed in this report. The above-mentioned observations on cannabis users should be kept in mind and carefully examined by all physicians. One could expect that as more potent cannabis preparations become available, some of the toxic manifestations which now seem rare might become more frequent. Some of the remarks about the dangers of cannabis may not be proved in future studies, and they may represent only our anxiety. However, prior to the elimination of these fears, no steps should be taken toward the legalizing of marijuana. At present there is no scientific evidence that cannabis is less harmful than either tobacco or alcohol. The opposite may be true. The analogy can be drawn between opium and cannabis. The permissive attitude toward the use of opium can easily lead to the use of morphine and other opiates. If we legalize the use of marijuana, we cannot prevent the use of more dangerous derivatives of cannabis; namely, hashish, cannabis oil and THC, itself. In my opinion, in the light of our present knowledge, legalizing of marijuana could be hazardous both for the individual and for society.

  10. Solid Waste Management Units And Areas Of Concern Annual Long-Term Monitoring & Maintenance Report For Calendar Year 2016.

    Energy Technology Data Exchange (ETDEWEB)

    Dotson, Patrick Wells [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Little, Bonnie Colleen [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-02-01

    Long-term controls were maintained at 21 Solid Waste Management Units (SWMUs) and Areas of Concern (AOCs) in accordance with the requirements of the “Long-Term Monitoring and Maintenance Plan for SWMUs and AOCs Granted Corrective Action Complete with Controls” in Attachment M of the Resource Conservation and Recovery Act Facility Operating Permit, which took effect February 26, 2015. Maintenance and controls at these SWMUs and AOCs are described and documented in this report. Conditions requiring maintenance or repair activities were not identified for any of the inspected SWMUs or AOCs. Based upon the inspections performed and site conditions observed, the administrative and physical institutional controls in place at the SWMUs and AOCs are effectively providing continued protection of human health and the environment. This report does not present monitoring and maintenance activities for SWMU 76, the Mixed Waste Landfill; those activities adhere to the approved MWL LTMM Plan, Section 4.8.1 requiring a separate annual report which will be submitted to the NMED by June 30, 2017.

  11. Annual report 2000. Department of wastes disposal and storage; Rapport annuel d'activite 2000. Departement d'Entreposage et de Stockage des Dechets

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-07-01

    This annual report presents the missions, the organization, the researches progress, the events, the publications and the personnel formation of the Department of wastes disposal and storage in the year 2000, one of the CEA fuel cycle Direction. (A.L.B.)

  12. Low-Level Burial Grounds dangerous waste permit application: Request for exemption from lined trench requirements and from land disposal restrictions for residual liquid at 218-E-12B Burial Ground Trench 94

    International Nuclear Information System (INIS)

    1992-10-01

    This document has been prepared and is being submitted to the respective agencies to satisfy three objectives of the US Department of Energy (DOE) Richland Field Office (DOE-RL) concerning Trench 94 of the 218-E-12B Burial Ground. The 218-E-12B Burial Ground is located in the 200 East Area of the Hanford Facility. Figure 1-1 shows the general location of the Hanford Site. The 218-E-12B Burial Ground is one of eight burial grounds included in the Low-Level Burial Grounds (LLBG), a treatment, storage and/or disposal (TSD) unit. Decommissioned, defueled naval submarine reactor compartments (SRCs) contain radioactivity caused by exposure of structural components to neutrons during normal operation of the submarines. After all the alternatives were evaluated in the US Department of the Navy 1984 environmental impact statement (EIS) (USN 1984), land burial of the SRCs was selected as the preferred disposal option. The SRCs currently are sent to Trench 94 of the 218-E-12B Burial Ground. In addition to radioactivity, the SRCs disposed in. The DOE-RL's three objectives in preparing and submitting this document are as follows. Request from Ecology an exemption from dangerous waste landfill liner and leachate collection and removal system (hereinafter referred to as liner/leachate system) requirements for Trench 94 of the 218-E-12B Burial Ground. Petition Ecology to exempt residual liquid in the SRCs from land disposal restrictions. Obtain EPA Region 10 review and comment on the request to Ecology for exemption from liner/leachate system requirements

  13. Interfacial radiolysis effects in tank waste speciation. 1997 annual progress report

    International Nuclear Information System (INIS)

    Orlando, T.M.

    1997-01-01

    'The purpose of this program is to deliver pertinent, fundamental information that can be used to make technically defensible decisions on safety issues and processing strategies associated with mixed chemical and radioactive waste cleanup. In particular, an understanding of radiolysis in mixed-phase systems typical of U. Department of Energy (DOE) heterogeneous, radioactive/chemical wastes will be established. This is an important scientific concern with respect to understanding tank waste chemistry issues; it has received relatively little attention. The importance of understanding solid-state radiolysis, secondary electron interactions, charge-transfer dynamics, and the general effect of heterogeneous solids (interface and particulate surface chemistry) on tank waste radiation processes will be demonstrated. In particular, the author will investigate (i) the role of solid-state and interfacial radiolysis in the generation of gases, (ii) the mechanisms of organic compound degradation, (iii) scientific issues underlying safe interim storage, and (iv) the effects of colloid surface-chemical properties on waste chemistry. Controlled radiolysis studies of NaNO 3 solids and SiO 2 particles were carried out using pulsed, low- (5--150 eV) and high- (3 MeV) energy electron-beams at Pacific Northwest National Laboratory (PNNL) and at Argonne National Laboratory (ANL), respectively. The pulsed, low-energy electron beams probe the inelastic scattering and secondary cascading effects produced by high-energy beta and gamma particles. Pulsed radiolysis allows time-resolved measurements of the high-energy processes induced by these particles. Using low-energy (10--75 eV) electron-beam irradiation of nominally dry NaNO 3 solution-grown and melt-grown single crystals, they observed H + , Na + , O + , NO + , NO, NO 2 , O 2 , and O( 3 P) desorption signals. The threshold measurements and yields indicate that the degradation proceeds mainly via destruction of the nitrate moiety. The

  14. The sonophysics and sonochemistry of liquid waste quantification and remediation. 1998 annual progress report

    International Nuclear Information System (INIS)

    Matula, T.J.

    1998-01-01

    'To perform an in-depth and comprehensive study of the fundamentals of acoustic cavitation and nonlinear bubble dynamics, to elucidate the fundamental physics of sonochemical reactions, to examine the potential of sonoluminescence to quantify and to monitor the presence of alkali metals and other elements in waste liquids, to design and to evaluate more effective sonochemical reactors for waste remediation, and to determine the optimal acoustical parameters in the use of sonochemistry for liquid-waste-contaminant remediation. This report summarizes work performed during year 2 of a 3-year project. The goals included performing near-IR spectroscopy of sonoluminescence. Cells have been designed for multi-bubble sonoluminescence (MBSL) and single-bubble sonoluminescence (SBSL) spectroscopy experiments. The MBSL cells are designed around a 20 kHz acoustic horn with replaceable titanium tips from Sonics and Materials. The horn is pressure-fitted into a stainless steel cell via O-rings and a compression ring, to seal the cell up to 100 psi for pressure experiments. The cell is thermostated by circulating coolant in a jacket, as well as flowing the cell fluid (at 4L/min.) through a temperature control bath. Several ports are located on the cell for gas ports (one for headspace, another for bubbling), a pressure transducer, a thermocouple, a needle hydrophone, and a septum port for addition or withdrawal of samples. The total volume is approximately 80 mL with a 10 mL head space. Directly opposite the horn tip is a 2 cm quartz window against which a fiber optic bundle is placed. Light collected through the fiber optic is imaged onto one of several detection systems.'

  15. Studies of nuclear-waste migration in geologic media. Annual report, November 1976--October 1977

    International Nuclear Information System (INIS)

    Seitz, M.G.; Rickert, P.G.; Fried, S.M.; Friedman, A.M.; Steindler, M.J.

    1978-03-01

    The confinement of nuclear wastes in geologic formations is being considered as a method of permanently disposing of the waste. Laboratory experiments (column infiltration, static absorption, and batch partitioning experiments) were performed with nuclides of Cs, Pu, Np, and Am to examine the migratory characteristics of long-lived radionuclides that could be mobilized by groundwaters infiltrating a nuclear waste repository and the surrounding geologic body. In column infiltration experiments, the positions of peak concentrations of Cs in chalk or shale columns; Pu in limestone; Am in limestone, sandstone, or tuff; and Np in a limestone column did not move when the columns were infiltrated with water. However, fractions of each of the nuclides were seen downstream from the peaks, indicating that there was a large dispersion in the relative migration rates of each of the trace elements in the lithic materials studied. The results of static absorption experiments indicate that Pu and Am are strongly absorbed from solution by the common rocks studied and that their migration relative to ground-water flow is thereby retarded. In addition, the reaction rates of dissolved nuclides with rocks were found to vary considerably in different rock-element systems. Batch partitioning experiments were performed to test whether absorption processes are reversible. After granulated basalt and americium-bearing water were contacted in an absorption step, part of the water was replaced with water free of Am and the Am repartitioned between rock and solution. The distribution of Am after desorption was comparable to its distribution after absorption. In cntrast, when tablets of various rocks were allowed to dry between absorption and desorption tests, Pu and Am were not generally desorbed from the tablets. This suggests that reversible reactions of nuclides, between waters and rocks may be upset by treatments such as drying

  16. Waste-Management Education and Research Consortium (WERC) annual progress report, 1992--1993

    International Nuclear Information System (INIS)

    1993-01-01

    In February, 1990, The Secretary of Energy, James Watkins, approved a grant for a waste (management) education and research consortium program proposed by New Mexico State University (NMSU) to the US Department of Energy (DOE). This program known by the acronym, ''WERC'' includes as its founding members NMSU, the University of New Mexico (UNM), the New Mexico Institute of Mining and Technology the Los Alamos National Laboratory, and the Sandia National Laboratories. The Navajo Community College joined the program later in 1991. The program has the mission of expanding the nation's capability to address the issues related to management of all types of waste. The program is unique and innovative in many aspects. It provides an integrated approach to this national need, and includes: (1) Education in waste management at the educational institutions resulting in graduate, undergraduate, and associate degrees with concentration in environmental management. (2) Professional development via teleconference for industry and government. (3) Technology development programs at the leading edge, providing hands-on training at the leading edge to students and information feeding into the education programs. (4) Education by technology development at the campuses, as well as from four field sites. (5) Ties with other multidisciplinary university facilities. (6) Ties with two National Laboratories (Los Alamos ampersand Sandia) located in New Mexico and with the Oak Ridge Associated Universities and others. (7) Technology transfer and education via an existing fiber optic network, a satellite link, and an existing state-wide extension program. (8) Outreach programs of special interest to precollege students, communities and business and government leaders throughout the United States. This report summarizes the accomplishments and status at the end of the third year

  17. Waste-Management Education and Research Consortium (WERC) annual progress report, 1991--1992

    International Nuclear Information System (INIS)

    1992-01-01

    In February, 1990, the Secretary of Energy, James Watkins approved a grant for a waste (management) education and research consortium program by New Mexico State University (NMSU) to the US Department of Energy (DOE). This program known by the acronym, ''WERC'' includes NMSU, the University of New Mexico (UNM), the New Mexico Institute of Mining and Technology (NMIMT), Navajo Community College, the Los Alamos National Laboratory and the Sandia National Laboratories. The program is designed to provide an integrated approach to the national need via the following: (1) Education in waste management to reach thousands of students by the three Consortium universities and the affiliate college resulting in graduate, undergraduate, and associate degrees with concentration in environmental management. (The term waste or environmental management is used in a broad sense throughout this paper and includes all aspects of environmental management and environmental restoration.) (2) Professional development via teleconference for industry and government. (3) Technology development programs at the leading edge, providing training to students and information to faculty feeding into the education programs. (4) Education and technology development at the campuses, as well as from four field sites. (5) Ties with other multidisciplinary university facilities. (6) Ties with two National Laboratories (Los Alamos ampersand Sandia) located in New Mexico, the Oak Ridge Associated Universities and others. (7) Technology transfer and education via an existing fiber optic network, a satellite link, and an existing state-wide extension program. (8) Outreach program of special interest to pre-college students, communities and business and government leaders throughout the United States. This report summarizes the accomplishments and status at the end of the second year

  18. 2010 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada National Security Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    2011-01-01

    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) 2010. This annual summary report presents data and conclusions from the FY 2010 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.

  19. Waste-Management Education and Research Consortium (WERC) annual progress report, 1991--1992

    International Nuclear Information System (INIS)

    1992-01-01

    This report contains the following appendices: Appendix A - Requirements for Undergraduate Level; Appendix B - Requirements for Graduate Level; Appendix C - Graduate Degree In Environmental Engineering; Appendix D - Non-degree Certificate Program; Appendix E - Curriculum for Associate Degree Program; Appendix F - Curriculum for NCC Program; Appendix G - Information 1991 Teleconference Series; Appendix H - Information on 1992 Teleconference Series; Appendix I - WERC interactive Television Courses; Appendix J - WERC Research Seminar Series; Appendix K - Sites for Hazardous/Radioactive Waste Management Series; Appendix L- Summary of Technology Development of the Second Year; Appendix M - List of Major Publications Resulting from WERC; Appendix N - Types of Equipment at WERC Laboratories

  20. 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.

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

    International Nuclear Information System (INIS)

    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

  2. Waste-Management Education and Research Consortium (WERC) annual progress report, 1991--1992. Appendixes

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-07

    This report contains the following appendices: Appendix A - Requirements for Undergraduate Level; Appendix B - Requirements for Graduate Level; Appendix C - Graduate Degree In Environmental Engineering; Appendix D - Non-degree Certificate Program; Appendix E - Curriculum for Associate Degree Program; Appendix F - Curriculum for NCC Program; Appendix G - Information 1991 Teleconference Series; Appendix H - Information on 1992 Teleconference Series; Appendix I - WERC interactive Television Courses; Appendix J - WERC Research Seminar Series; Appendix K - Sites for Hazardous/Radioactive Waste Management Series; Appendix L- Summary of Technology Development of the Second Year; Appendix M - List of Major Publications Resulting from WERC; Appendix N - Types of Equipment at WERC Laboratories.

  3. Waste-Management Education and Research Consortium (WERC) annual progress report, 1991--1992

    Energy Technology Data Exchange (ETDEWEB)

    Maji, A. K.; Thomson, Bruce M.; Samani, Zohrab A.; Hanson, Adrian; Cadena, Fernando; Gopalan, Aravamudan; Barton, Larry L.; Sillerud, Laurel O.; Fekete, Frank A.; Rogers, Terry; Lindermann, William C.; Pigg, C. Joanne; Blake, Robert; Kieft, Thomas L.; Ross, Timothy J.; LaPointe, Joe L.; Khandan, Nirmala; Bedell, Glenn W.; Rayson, Gary D.; Leslie, Ian H.; Ondrias, Mark R.; Sarr, Gregory P.; Colbaugh, Richard; Angel, Edward; Niemczyk, Thomas M.; Bein, Thomas; Campbell, Andrew; Phillips, Fred; Wilson, John L.; Gutjahr, Allan; Sammis, T. W.; Steinberg, Stanly; Nuttall, H. E.; Genin, Joseph; Conley, Edgar; Aimone-Martin, Catherine T.; Wang, Ming L.; Chua, Koon Meng; Smith, Phillip; Leslie, Ian; Skowlund, Chris T.; McGuckin, Tom; Jenkins-Smith, Hank C.

    1992-04-07

    This report contains the following appendices: Appendix A - Requirements for Undergraduate Level; Appendix B - Requirements for Graduate Level; Appendix C - Graduate Degree In Environmental Engineering; Appendix D - Non-degree Certificate Program; Appendix E - Curriculum for Associate Degree Program; Appendix F - Curriculum for NCC Program; Appendix G - Information 1991 Teleconference Series; Appendix H - Information on 1992 Teleconference Series; Appendix I - WERC interactive Television Courses; Appendix J - WERC Research Seminar Series; Appendix K - Sites for Hazardous/Radioactive Waste Management Series; Appendix L- Summary of Technology Development of the Second Year; Appendix M - List of Major Publications Resulting from WERC; Appendix N - Types of Equipment at WERC Laboratories.

  4. Overcoming negative tendencies concerning public attitude to potentially dangerous technologies

    International Nuclear Information System (INIS)

    Barinov, A.; Shmelev, S.

    1995-01-01

    The Moscow Scientific industrial Association RADON is an enterprise with potentially dangerous technology. RADON fulfils the collection, transportation, treatment and disposal of radioactive waste from Moscow region. The inhabitants of this region consider it, and that is true, to be essentially dangerous. We understood, that it is necessary to change the situation and give the public the true information about RADON's activity. For this purpose 4 years ago we developed a new Department, the Department or External Relations

  5. Seismic surface wave tomography of waste sites. 1997 annual progress report

    International Nuclear Information System (INIS)

    Long, T.L.

    1997-01-01

    'The objective of the Seismic Surface Wave Tomography of Waste Sites is to develop a robust technique for field acquisition and analysis of surface wave data for the interpretation of shallow structures, such as those associated with the burial of wastes. The analysis technique is to be developed and tested on an existing set of seismic data covering the K-901 burial site at the East Tennessee Technology Park. Also, a portable prototype for a field acquisition system will be designed and developed to obtain additional data for analysis and testing of the technique. The K-901 data have been examined and a preliminary Single Valued Decomposition inversion has been obtained. The preliminary data indicates a need for additional seismic data to ground-truth the inversion. The originally proposed gravity data acquisition has been dropped because sufficient gravity data are now available for a preliminary analysis and because the seismic data are considered more critical to the interpretation. The proposed prototype for the portable acquisition and analysis system was developed during the first year and will be used in part of the acquisition of additional seismic data.'

  6. Geotechnical support and topical studies for nuclear waste geologic repositories: Annual report, fiscal year 1987

    International Nuclear Information System (INIS)

    1988-01-01

    This multidisciplinary project was initiated in fiscal year 1986. It comprises 11 reports in two major interrelated tasks: The technical assistance part of the project includes reviewing the progress of the major projects in the DOE Office of Civilian Radioactive waste Management (OCRWM) Program and advising the Engineering and Geotechnology Division on significant technical issues facing each project; analyzing geotechnical data, reports, tests, surveys and plans for the different projects; reviewing and commenting on major technical reports and other program documents such as Site Characterization Plans (SCP) and Study Plans; and providing scientific and technical input at technical meetings. The topical studies activity comprises studies on scientific and technical ions and issues of significance to in-situ testing, test analysis methods, and site characterization of nuclear waste geologic repositories. The subjects of study were selected based on discussions with DOE staff. One minor topic is a preliminary consideration and planning exercise for postclosure monitoring studies. The major task, with subtasks involving various geoscience disciplines, is a study of the mechanical, hydraulic, geophysical and geochemical properties of fractures in geologic rock masses

  7. Characterization and monitoring of 300 Area facility liquid waste streams: 1994 Annual report

    International Nuclear Information System (INIS)

    Manke, K.L.; Riley, R.G.; Ballinger, M.Y.; Damberg, E.G.; Evans, J.C.; Julya, J.L.; Olsen, K.B.; Ozanich, R.M.; Thompson, C.J.; Vogel, H.R.

    1995-04-01

    This report summarizes the results of characterizing and monitoring the following sources during calendar year 1994: liquid waste streams from Buildings 306, 320, 324, 326, 331, and 3720 in the 300 Area of Hanford Site and managed by the Pacific Northwest Laboratory; treated and untreated Columbia River water (influent); and water at the confluence of the waste streams (that is, end-of-pipe). Data were collected from March to December before the sampling system installation was completed. Data from this initial part of the program are considered tentative. Samples collected were analyzed for chemicals, radioactivity, and general parameters. In general, the concentrations of chemical and radiological constituents and parameters in building wastewaters which were sampled and analyzed during CY 1994 were similar to historical data. Exceptions were the occasional observances of high concentrations of chloride, nitrate, and sodium that are believed to be associated with excursions that were occurring when the samples were collected. Occasional observances of high concentrations of a few solvents also appeared to be associated with infrequent building r eases. During calendar year 1994, nitrate, aluminum, copper, lead, zinc, bis(2-ethylhexyl) phthalate, and gross beta exceeded US Environmental Protection Agency maximum contaminant levels

  8. Fundamental thermodynamics of actinide-bearing mineral waste forms. 1998 annual progress report

    International Nuclear Information System (INIS)

    Ebbinghaus, B.B.; Williamson, M.A.

    1998-01-01

    'The end of the Cold War raised the need for the technical community to be concerned with the disposition of excess nuclear weapon material. The plutonium will either be converted into mixed-oxide fuel for use in nuclear reactors or immobilized in glass or ceramic waste forms and placed in a repository. The stability and behavior of plutonium in the ceramic materials as well as the phase behavior and stability of the ceramic material in the environment is not well established. In order to provide technically sound solutions to these issues, thermodynamic data are essential in developing an understanding of the chemistry and phase equilibria of the actinide-bearing mineral waste form materials proposed as immobilization matrices. Mineral materials of interest include zircon, zirconolite, and pyrochlore. High temperature solution calorimetry is one of the most powerful techniques, sometimes the only technique, for providing the fundamental thermodynamic data needed to establish optimum material fabrication parameters, and more importantly, understand and predict the behavior of the mineral materials in the environment. The purpose of this project is to experimentally determine the enthalpy of formation of actinide orthosilicates, the enthalpy of formation of actinide substituted zircon, zirconolite and pyrochlore, and develop an understanding of the bonding characteristics and stability of these materials. This report summarizes work after eight months of a three year project.'

  9. Waste Isolation Pilot Plant annual site environmental report for calendar year 1992

    International Nuclear Information System (INIS)

    1993-01-01

    The US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Operational Environmental Monitoring Plan (OEMP) defined a comprehensive set of parameters which are monitored to detect potential environmental impacts and establish baselines for future environmental evaluations. Surface water and groundwater, air, soil, and biotics are monitored for radioactivity levels. Nonradiological environmental monitoring activities include air, water quality, soil properties, meteorological measurements and determination of the status of the local biological community. Ecological studies focus on the immediate area surrounding the WIPP site with emphasis on the salt storage pile. The baseline radiological surveillance covers a broader geographic area including nearby ranches, villages, and cities. Since the WIPP is still in its preoperational phase (i.e., no waste has been received) certain operational requirements of DOE Orders 5400.1, 5400.5, and the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T) are not relevant. Therefore, this report does not discuss items such as radionuclide emissions and effluents and subsequent doses to the public

  10. Waste Isolation Pilot Plant annual site environmental report for calendar year 1992

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-31

    The US Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Operational Environmental Monitoring Plan (OEMP) defined a comprehensive set of parameters which are monitored to detect potential environmental impacts and establish baselines for future environmental evaluations. Surface water and groundwater, air, soil, and biotics are monitored for radioactivity levels. Nonradiological environmental monitoring activities include air, water quality, soil properties, meteorological measurements and determination of the status of the local biological community. Ecological studies focus on the immediate area surrounding the WIPP site with emphasis on the salt storage pile. The baseline radiological surveillance covers a broader geographic area including nearby ranches, villages, and cities. Since the WIPP is still in its preoperational phase (i.e., no waste has been received) certain operational requirements of DOE Orders 5400.1, 5400.5, and the Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE/EH-0173T) are not relevant. Therefore, this report does not discuss items such as radionuclide emissions and effluents and subsequent doses to the public.

  11. Dangers of environmental pollution

    International Nuclear Information System (INIS)

    Schaer, M.

    1978-01-01

    Environmental pollution is ever increasing. Protection of the environment must not be neglected for economic reasons. Damage to health due to environmental effects is hard to determine epidemiologically as there are nearly always several causes to consider at the same time. Still, the increase in environmental pollution results in increased damage to humans, animals, and plants. The many dangers to health can be illustrated by the example of energy demand and the different ways to meet it. It is highly necessary to create environmental laws which aim at a reduction of environmental pollution. (orig.) [de

  12. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Management Member Services Advocacy Foundation About Subspecialties & More Eye Health Home Annual Meeting Clinical Education Practice Management ... Education Center Redmond Ethics Center Global Ophthalmology Guide Eye Health Find an Ophthalmologist Academy Store Eye Health ...

  13. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Center Laser Surgery Education Center Redmond Ethics Center Global Ophthalmology Guide Find an Ophthalmologist Advanced Search Annual Meeting Clinical Education Practice Management Member Services Advocacy Foundation About Subspecialties & ...

  14. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Eye Health Home Annual Meeting Clinical Education Practice Management Member Services Advocacy Foundation About Subspecialties & More Academy Publications EyeNet Ophthalmology Ophthalmology Retina Information for: International Ophthalmologists Media Medical Students Patients and Public Technicians ...

  15. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Services Advocacy Foundation About Subspecialties & More Eye Health Home Annual Meeting Clinical Education Practice Management Member Services ... had not been properly fitted by an eye care professional, the lenses stuck to my eye like ...

  16. Dangers of Indoor Tanning

    Science.gov (United States)

    ... Registration General information Housing & travel Education Exhibit hall Mobile app 2019 Annual Meeting Derm Exam Prep Course ... SkinPAC State societies Scope of practice Truth in advertising NP/PA laws Action center Public and patients ...

  17. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Center Global Ophthalmology Guide Find an Ophthalmologist Advanced Search Annual Meeting Clinical Education Practice Management Member Services ... Center Global Ophthalmology Guide Find an Ophthalmologist Advanced ... Subspecialties Cataract/Anterior Segment Comprehensive Ophthalmology Cornea/External ...

  18. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Annual Meeting Clinical Education Practice Management Member Services Advocacy Foundation About Subspecialties & More Academy Publications EyeNet Ophthalmology Ophthalmology Retina Information for: International Ophthalmologists Media Medical Students Patients and Public Technicians ...

  19. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Member Services Advocacy Foundation About Subspecialties & More Eye Health Home Annual Meeting Clinical Education Practice Management Member ... Center Redmond Ethics Center Global Ophthalmology Guide Eye Health Find an Ophthalmologist Academy Store Eye Health A- ...

  20. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Eye Health Home Annual Meeting Clinical Education Practice Management Member Services Advocacy Foundation About Subspecialties & More Academy Publications EyeNet Ophthalmology Ophthalmology Retina Information for: International Ophthalmologists Media Medical Students Patients and ...

  1. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Ethics Center Global Ophthalmology Guide Find an Ophthalmologist Advanced Search Annual Meeting Clinical Education Practice Management Member ... Ethics Center Global Ophthalmology Guide Find an Ophthalmologist Advanced ... Subspecialties Cataract/Anterior Segment Comprehensive Ophthalmology Cornea/ ...

  2. Colored Contact Lens Dangers

    Medline Plus

    Full Text Available ... Meeting Clinical Education Practice Management Member Services Advocacy Foundation About Subspecialties & More Eye Health Home Annual Meeting Clinical Education Practice Management Member Services Advocacy Foundation About Subspecialties & More Academy Publications EyeNet Ophthalmology Ophthalmology ...

  3. Waste tank safety program annual status report for FY 1993, Task 5: Toxicology and epidemiology

    International Nuclear Information System (INIS)

    Mahlum, D.D.; Young, J.Y.

    1993-09-01

    A toxicology team independently reviewed analytical data and provided advice concerning potential health effects associated with exposure to tank-vapor constituents at the Hanford site. Most of the emphasis was directed toward Tank 241-C-103, but a preliminary assessment was also made of the toxicologic implication of the cyanide levels in the headspace of Tank 241-C-108. The objectives of this program are to (1) review procedures used for sampling vapors from various tanks, (2) identify constituents in tank-vapor samples that could be related to symptoms reported by waste-tank workers, (3) evaluate the toxicologic implications of those constituents by comparison to established toxicologic data bases, (4) provide advice for additional analytical efforts, and (5) support other activities as requested by the project manager and the cognizant Westinghouse Hanford Company Tank Vapor Issues Safety Resolution Manager

  4. Technical Advisory Committee on the nuclear fuel waste management program : thirteenth annual report

    International Nuclear Information System (INIS)

    Shemilt, L.W.

    1993-03-01

    Since the last reporting period by the Technical Advisory Committee (TAC) the emphasis of the work in the Canadian Nuclear Fuel Waste Management Program (CNFWMP) has been on the writing of the Environmental Impact Statement (EIS) and the associated set of nine primary reference documents as well as supporting documents. These are in preparation for submission to the Environmental Assessment Review Panel who will lead the national evaluation of the disposal concept under the auspices of the Federal Environmental Assessment Review Office (FEARO). The disposal concept developed over the last fourteen years by Atomic Energy of Canada Limited (AECL) and anticipated to be presented by means of the EIS in 1994, is based on a multiple system of natural and man-made barriers wherein nuclear waste is first enclosed in corrosion-resistant containers, designed to last at least 500 years, and then placed in a vault excavated 500 - 1000 m deep in granitic rocks of the Canadian Shield. After container emplacement either in or on the floor of the vault, and with a surrounding buffer material of a bentonite clay/sand mixture, the vault will be backfilled and sealed with crushed rock, buffer and sand, as will be the shafts and exploratory boreholes. The case study being presented by AECL to demonstrate the safety of this concept and the technology to implement it, relies on computer simulations of a hypothetical disposal site with geological characteristics similar to those at the Underground Research Laboratory (URL) in the Whiteshell Research Area (WRA) located in Manitoba. The preliminary simulation results suggest that safe containment can be achieved provided that the waste is surrounded by a sparsely-fractured zone of rock wherein movement of contaminants carried by groundwater is modelled as a diffusive as opposed to a advective process. The principal focus of work during the past year within the environmental and safety assessment has been to complete the Post

  5. Annual Report, Fall 2016: Identifying Cost Effective Tank Waste Characterization Approaches

    Energy Technology Data Exchange (ETDEWEB)

    Reboul, S. H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); DiPrete, D. P. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2016-12-12

    This report documents the activities that were performed during the second year of a project undertaken to improve the cost effectiveness and timeliness of SRNL’s tank closure characterization practices. The activities performed during the first year of the project were previously reported in SRNL-STI-2015-00144. The scope of the second year activities was divided into the following three primary tasks: 1) develop a technical basis and strategy for improving the cost effectiveness and schedule of SRNL’s tank closure characterization program; 2) initiate the design and assembly of a new waste removal system for improving the throughput and reducing the personnel dose associated with extraction chromatography radiochemical separations; and 3) develop and perform feasibility testing of three alternative radiochemical separation protocols holding promise for improving high resource demand/time consuming tank closure sample analysis methods.

  6. Commercial Nuclear Waste Research and Development Program. Annual report, fiscal year 1985

    International Nuclear Information System (INIS)

    1985-12-01

    Nuclear waste handling, packaging, and dry storage testing for the Department of Energy (DOE) Commercial Nuclear Waste Research and Development Program are conducted at the E-MAD (Engine Maintenance, Assembly and Disassembly) facility in Area 25 of the Nevada Test Site. Brief discussions of E-MAD activities are included in this report. Significant accomplishments for this period are as follows: (1) Integrity monitoring of the 17 fuel assemblies located at E-MAD was performed to determine if handling, packaging, or storage had affected the overall integrity of the fuel. (2) The 24-month Dry Storage Fuel Integrity Demonstration Test being conducted at the E-MAD facility was completed. Two fuel rods, removed from the assembly prior to the test, were reinserted into the fuel assembly. (3) The remaining nine fuel assemblies were removed from their seal-welded canisters and characterized to verify their integrity following storage tests. (4) The decay heat rates of five fuel assemblies were measured using the E-MAD boiling water calorimeter. The measured decay heat rates were compared to predicted rates. (5) At DOE/NV request, plans were prepared and submitted to ship the 17 E-MAD fuel assemblies to the Idaho National Engineering Laboratory and then shut down the E-MAD facility. (6) The revised safety assessment document was approved and transmitted to DOE/NV. (7) Quality Assurance personnel assisted in the completion of the DOE/NV Quality Assurance Manual and it was approved and published. (8) Technical support was provided to Lawrence Livermore National Laboratories in the decontamination of electronic equipment

  7. 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)

    1990-01-01

    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

  8. 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)

    1990-01-01

    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

  9. Acid-base behavior in hydrothermal processing of wastes. 1997 annual progress report

    International Nuclear Information System (INIS)

    1997-01-01

    'A major obstacle to the development of hydrothermal technology for treating DOE wastes has been a lack of scientific knowledge of solution chemistry, thermodynamics and transport phenomena. The progress over the last year is highlighted in the following four abstracts from manuscripts which have been submitted to journals. The authors also have made considerable progress on a spectroscopic study of the acid-base equilibria of Cr(VI). They have utilized novel spectroscopic indicators to study acid-base equilibria up to 380 C. Until now, very few systems have been studied at such high temperatures, although this information is vital for hydrothermal processing of wastes. The pH values of aqueous solutions of boric acid and KOH were measured with the optical indicator 2-naphthol at temperatures from 300 to 380 C. The equilibrium constant Kb-l for the reaction B(OH)3 + OH - = B(OH) -4 was determined from the pH measurements and correlated with a modified Born model. The titration curve for the addition of HCl to sodium borate exhibits strong acid-strong base behavior even at 350 C and 24.1 MPa. At these conditions, aqueous solutions of sodium borate buffer the pH at 9.6 t 0.25. submitted to Ind. Eng. Chem. Res. Acetic Acid and HCl Acid-base titrations for the KOH-acetic acid or NH 3 -acetic acid systems were monitored with the optical indicator 2-naphthoic acid at 350 C and 34 MPa, and those for the HCl;Cl- system with acridine at 380 C and up to 34 MPa (5,000 psia ). KOH remains a much stronger base than NH,OH at high temperature. From 298 K to the critical temperature of water, the dissociation constant for HCl decreases by 13 orders of magnitude, and thus, the basicity of Cl - becomes significant. Consequently, the addition of NaCl to HCl raises the pH. The pH titration curves may be predicted with reasonable accuracy from the relevant equilibrium constants and Pitzer''s formulation of the Debye- Htickel equation for the activity coefficients.'

  10. Acid-base behavior in hydrothermal processing of wastes. 1998 annual progress report

    International Nuclear Information System (INIS)

    Johnson, K.P.; Rossky, P.J.

    1998-01-01

    'A new technology, hydrothermal oxidation (also called supercritical water oxidation), is being developed to treat high level nuclear wastes. Nitrates are reduced to nitrogen; furthermore, phosphates, alumina sludge, and chromium are solubilized, and the sludge is reconstituted as fine oxide particles. A major obstacle to development of this technology has been a lack of scientific knowledge of chemistry in hydrothermal solution above 350 C, particularly acid-base behavior, and transport phenomena, which is needed to understand corrosion, metal-ion complexation, and salt precipitation and recovery. The objective is to provide this knowledge with in-situ UV-vis spectroscopic measurements and fully molecular computer simulation. A major objective of the experimental studies has been to determine the equilibria for Cr(VI) up to 420 C as this is a key species to be removed from nuclear wastes. A wide range of concentrations of KOH and perchloric acid were utilized to manipulate the acid-base equilibria and to understand the effects of ion solvation and ion pairing. The second system is the equilibria between nitric acid, nitrous acid, nitrogen dioxide, nitrite and nitrate ions and oxygen. For both of these systems, chemical equilibria has not been measured previously in hydrothermal solution at these temperatures. On the theoretical side, the authors have focused on the study of the transport properties of aqueous ions in supercritical water. The motivation for these studies is two fold. First, although transport coefficients are fundamental to solution chemistry reaction rates, the behavior of such transport properties over wide ranges of density and temperature are not well established experimentally, particularly at the densities typically of interest (< 0.5 g/cc). Second, due to practical challenges, ionic association equilibria in SCW is typically accessed via measurements of conductivity followed by analysis through a theoretical model that incorporates ion

  11. Commercial Nuclear Waste Research and Development Program. Annual report, fiscal year 1984

    International Nuclear Information System (INIS)

    1985-01-01

    This document is a report of fiscal year 1984 activities performed to meet task objectives of the Nevada Nuclear Waste Storage Investigations (NNWSI) Project Plan. Noteworthy accomplishments were: operation of a fuel temperature test which evaluates fuel performance in an environment expected for metal cask storage. This test is being performed for the DOE Richland Operations Dry Storage Fuel Integrity Demonstration Program; characterization of fuel assemblies and storage canisters, which includes fuel assembly visual inspection, videotape and still photography, and contamination swipe sampling; and canister gas and full volume filtration sampling, contamination swipe sampling, and residue collection; removal of fuel assemblies from seal welded storage canisters, using the E-MAD canister cutter; integrity monitoring of fuel assemblies in seal welded canisters, by sampling and analysis of canister cover gas; and fuel assemblies in unwelded canisters, by collection and analysis of fuel surface contamination swipe samples and canister residue; emplacement/removal of canisterized fuel assemblies in the E-MAD drywells; and preparation of a summary storage history of all fuel assemblies at the E-MAD facility, including FY 1983 activities involving those fuel assemblies

  12. Annual Status Report (FY2010) Composite Analysis of Low-Level Waste Disposal in the Central Plateau at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Nichols, W. E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

    2011-01-11

    In accordance with the U.S. Department of Energy (DOE) requirements in DOE O 435.1 Chg 1, Radioactive Waste Management, and implemented by DOE/RL-2000-29, Maintenance Plan for the Composite Analysis of the Hanford Site, Southeast Washington, the DOE Richland Operations Office (DOE-RL), also known as RL, has prepared this annual status report for fiscal year (FY) 2010 of PNNL-11800, Composite Analysis for Low-Level Waste Disposal in the 200 Area Plateau of the Hanford Site, hereafter referred to as the Composite Analysis.

  13. Studies of nuclear waste migration in geologic media. Annual report, October 1978-September 1979

    International Nuclear Information System (INIS)

    Seitz, M.G.; Rickert, P.G.; Couture, R.A.; Williams, J.; Meldgin, N.; Fried, S.M.; Friedman, A.M.; Steindler, M.J.

    1980-01-01

    Experimental results obtained this year confirm the results obtained in previous years - that nuclides migrating by fluid flow in rock often exhibit complex behavior not predicted by simple chromatographic-type models. A phenomenon found previously to lead to complex behavior for leached radionuclides is that the amount of adsorbed nuclide was not proportional to the nuclide concentration in solution (nonlinear adsorption isotherm). For cesium adsorption on limestone and on basalt, nonlinear isotherms were found this year to occur in the range of cesium concentrations in the groundwater of about 10 -3 to 10 -9 M. Because cesium concentrations in this range can readily be attained by the leaching of solid waste by groundwater, the effects of nonlinear isotherms are germane to nuclide migration. This dependence of cesium migration on the leached concentration of cesium emphasizes the importance of treating the leaching and migration processes simultaneously such as is done in the leach-migration experiments performed in this work. The existence of nonlinear isotherms precludes the use of a single partition coefficient (K/sub d/) to describe cesium migration at an arbitrary cesium concentration above 10 -9 M. Nonetheless, nonlinear isotherms can be studied experimentally (e.g., to give K/sub d/ as a function of concentration) and effects of nonlinear adsorption can be predicted quantitatively. Comparison of results from column and batch tests indicate that, in addition to nonlinear adsorption, kinetic effects need to be considered in predicting nuclide migration from the partition coefficients measured in batch tests. Results of batch experiments of 2 weeks or longer duration pertained to migration expected only at the very lowest (< 50 m/y) groundwater flow rates of interest

  14. Dangers and Pleasures

    DEFF Research Database (Denmark)

    Järvinen, Margaretha Maria; Østergaard, Jeanette

    2011-01-01

    to ‘hard’ illegal drugs; and, finally, the pro-drug position, characteristic of drug users with low risk perceptions and high pleasure-orientation. We use the focus group interviews to demonstrate how youths occupying these differing positions argue for and against drugs and which risks and pleasures......This is a study of young people’s conceptions of illegal drug use as dangerous and/or pleasurable and an analysis of the relationship between attitudes to drugs, drinking, friends’ reported drug use and own experience with drug use and drinking. The article applies a mixed methods approach using...... both survey data and focus group interviews. The main statistical method is Multiple Correspondence Analysis (MCA), which constructs a social space of young people’s attitudes to drugs and drug experiences relationally. We identify four interrelated positions on illegal drug use among 17 to 19-year...

  15. Nye County nuclear waste repository project office independent scientific investigations program. Summary annual report, May 1996--April 1997

    International Nuclear Information System (INIS)

    1997-05-01

    This annual summary report, prepared by Multimedia Environmental Technology, Inc. (MET) on behalf of Nye County Nuclear Waste Project Office, summarizes the activities that were performed during the period from May 1, 1996 to April 30, 1997. These activities were conducted in support of the Independent Scientific Investigation Program (ISIP) of Nye County at the Yucca Mountain Site (YMS). The Nye County NWRPO is responsible for protecting the health and safety of the Nye County residents. NWRPO's on-site representative is responsible for designing and implementing the Independent Scientific Investigation Program (ISIP). Major objectives of the ISIP include: (1) Investigating key issues related to conceptual design and performance of the repository that can have major impact on human health, safety, and the environment. (2) Identifying areas not being addressed adequately by DOE Nye County has identified several key scientific issues of concern that may affect repository design and performance which were not being adequately addressed by DOE. Nye County has been conducting its own independent study to evaluate the significance of these issues

  16. Nye County Nuclear Waste Repository Project Office independent scientific investigations program annual report, May 1997 - April 1998

    International Nuclear Information System (INIS)

    1998-07-01

    This annual summary report, prepared by the Nye County Nuclear Waste Repository Project Office (NWRPO), summarizes the activities that were performed during the period from May 1, 1997 to April 30, 1998. These activities were conducted in support of the Independent Scientific Investigation Program (ISIP) of Nye County at the Yucca Mountain Site (YMS). The Nye County NWRPO is responsible for protecting the health and safety of the Nye County residents. NWRPO's on-site representative is responsible for designing and implementing the Independent Scientific Investigation Program (ISIP). Major objectives of the ISIP include: Investigating key issues related to conceptual design and performance of the repository that can have major impact on human health, safety, and the environment; identifying areas not being addressed adequately by the Department of Energy (DOE). Nye County has identified several key scientific issues of concern that may affect repository design and performance which were not being adequately addressed by DOE. Nye County has been conducting its own independent study to evaluate the significance of these issues. This report summarizes the results of monitoring from two boreholes and the Exploratory Studies Facility (ESF) tunnel that have been instrumented by Nye County since March and April of 1995. The preliminary data and interpretations presented in this report do not constitute and should not be considered as the official position of Nye County. The ISIP presently includes borehole and tunnel instrumentation, monitoring, data analysis, and numerical modeling activities to address the concerns of Nye County

  17. 2006 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Gregory J, Shott, Vefa Yucel

    2007-03-01

    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, 2006) 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 as an annual summary report to the 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 (DOE, 2000; 2002). The DOE, National Nuclear Security Administration Nevada Site Office performed annual reviews in fiscal year (FY) 2006 by evaluating operational factors and research results that impact the continuing validity of the PAs and CAs results. This annual summary report presents data and conclusions from the FY 2006 review, and determines the adequacy of the PAs and CAs. Operational factors, such as the waste form and containers, facility design, waste receipts, and closure plans, as well as monitoring results and research and development (R&D) activities, were reviewed in FY 2006 for determination of 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 for determination of the adequacy of the CAs.

  18. 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)

    Anon.

    1989-01-01

    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

  19. 2006 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    Gregory J; Shott, Vefa Yucel

    2007-01-01

    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, 2006) 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 as an annual summary report to the 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 (DOE, 2000; 2002). The DOE, National Nuclear Security Administration Nevada Site Office performed annual reviews in fiscal year (FY) 2006 by evaluating operational factors and research results that impact the continuing validity of the PAs and CAs results. This annual summary report presents data and conclusions from the FY 2006 review, and determines the adequacy of the PAs and CAs. Operational factors, such as the waste form and containers, facility design, waste receipts, and closure plans, as well as monitoring results and research and development (R and D) activities, were reviewed in FY 2006 for determination of 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 for determination of the adequacy of the CAs

  20. 2004 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    Vefa Yucel

    2005-01-01

    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 (Bechtel Nevada, 2000) requires an annual review to assess the adequacy of the performance assessments (PAs) and composite analyses (CAs) for each of the facilities, and reports the results in an annual summary report to the U.S. Department of Energy 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 (U.S. Department of Energy [DOE]). The U.S. Department of Energy National Nuclear Security Administration Nevada Site Office performed annual reviews in fiscal year (FY) 2004 by evaluating operational factors and research results that impact the continuing validity of the PA and CA results. This annual summary report presents data and conclusions from the FY 2004 review, and determines the adequacy of the PAs and CAs. Operational factors, such as the waste form and containers, facility design, waste receipts, closure plans, as well as monitoring results and research and development (R and D) activities were reviewed in FY 2004 for the determination of 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 for the determination of the adequacy of the CAs

  1. 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)

    Anon.

    1989-01-01

    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

  2. Proceedings of the eighth annual DOE low-level waste management forum: Executive summary, opening plenary session, closing plenary session, attendees

    International Nuclear Information System (INIS)

    1987-02-01

    The Eighth Annual DOE (Department of Energy) Low-Level Waste Management Forum was held in September 1986, in Denver, Colorado, to provide a forum for exchange of information on low-level radioactive waste (LLW) management activities, requirements, and plans. The one hundred ninety attendees included representatives from the DOE Nuclear Energy and Defense Low-Level Waste Management Programs, DOE Operations Offices and their contractors; representatives from the US Nuclear Regulatory Commission (NRC), US Environmental Protection Agency (EPA), US Geological Survey, and their contractors; representatives of states and regions responsible for development of new commercial low-level waste disposal facilities; representatives of utilities, private contractors, disposal facility operators, and other parties concerned with low-level waste management issues. Plenary sessions were held at the beginning and conclusion of the meeting, while eight concurrent topical sessions were held during the intervening two days. The meeting was organized by topical areas to allow for information exchange and discussion on current and future low-level radioactive waste management challenges. Session chairmen presented summaries of the discussions and conclusions resulting from their respective sessions. Selected papers in this volume have been processed for inclusion in the Energy Data Base

  3. Proceedings of the eighth annual DOE low-level waste management forum: Executive summary, opening plenary session, closing plenary session, attendees

    Energy Technology Data Exchange (ETDEWEB)

    1987-02-01

    The Eighth Annual DOE (Department of Energy) Low-Level Waste Management Forum was held in September 1986, in Denver, Colorado, to provide a forum for exchange of information on low-level radioactive waste (LLW) management activities, requirements, and plans. The one hundred ninety attendees included representatives from the DOE Nuclear Energy and Defense Low-Level Waste Management Programs, DOE Operations Offices and their contractors; representatives from the US Nuclear Regulatory Commission (NRC), US Environmental Protection Agency (EPA), US Geological Survey, and their contractors; representatives of states and regions responsible for development of new commercial low-level waste disposal facilities; representatives of utilities, private contractors, disposal facility operators, and other parties concerned with low-level waste management issues. Plenary sessions were held at the beginning and conclusion of the meeting, while eight concurrent topical sessions were held during the intervening two days. The meeting was organized by topical areas to allow for information exchange and discussion on current and future low-level radioactive waste management challenges. Session chairmen presented summaries of the discussions and conclusions resulting from their respective sessions. Selected papers in this volume have been processed for inclusion in the Energy Data Base.

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

    International Nuclear Information System (INIS)

    1992-01-01

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

  5. Manifesto for a Dangerous Sociology

    Directory of Open Access Journals (Sweden)

    Cisneros, César

    2008-05-01

    Full Text Available Based on my experience as a Mexican sociologist, I argue for the practice of a "Dangerous Sociology". I examine the process of sociological observation to show the need for such a practice. Some dimensions of this "Dangerous Sociology" are defined.

  6. A dangerous mixture

    Directory of Open Access Journals (Sweden)

    Anna Piva

    2014-03-01

    Full Text Available A 59-year old woman was admitted for fatigue and arm paresthesias with Trousseau sign. Her medical history included thyroidectomy and hypercholesterolemia recently treated with simvastatin. Laboratory tests showed severe hypokalemia and hypocalcemia, severe increase in muscle enzymes, metabolic alkalosis; low plasma renin activity, increased thyroid-stimulating hormone, normal free thyroxine, increased parathyroid hormone, decreased vitamin D3; alterations in electrolyte urinary excretion, cortisol and aldosterone were excluded. Hypothesizing a statin-related myopathy, simvastatin was suspended; the patient reported use of laxatives containing licorice. Electrolytes normalized with intravenous supplementation. Among many biochemical alterations, none stands out as a major cause for muscular and electrolyte disorders. All co-factors are inter-connected, starting with statin-induced myopathy, worsened by hypothyroidism, secondary hyperaldosteronism and vitamin D deficiency, leading to hypocalcemia and hypokalemia, perpetrating muscular and electrolyte disorders. The importance of considering clinical conditions as a whole emerges with multiple co-factors involved. Another issue concerns herbal products and their potential dangerous effects.

  7. Annual technology assessment and progress report for the Buried Transuranic Waste Studies Program at the Idaho National Engineering Laboratory (1987)

    International Nuclear Information System (INIS)

    Loomis, G.G.; Low, J.O.

    1988-01-01

    This report presents FY-87 activities for the Buried Transuranic (TRU) Waste Studies Program at the Idaho National Engineering Laboratory (INEL). This program investigates techniques to provide long-term confinement of buried TRU waste, as well as methods of retrieval. The confinement method of in situ grouting was examined in a simulated shallow-land buried TRU waste pit constructed adjacent to the RWMC TRU waste burial pits. The in situ grouting technique involved an experimental dyanmic compaction process which simultaneously grouts and compacts the waste. The simulated waste pit consisted of regions of randomly dumped drums, stacked boxes, and stacked drums, thus representing the various conditions of buried waste at the RWMC. Simulated waste and airborne tracers were loaded into the various simulated buried waste containers. Pregrouting and post-grouting data, such as hydraulic conductivity, were obtained to assess the hydrological integrity of the grouted waste material. In addition, post-grouting destructive examinations were performed and the results analyzed. Retrieval and processing of the TRU buried waste is also being examined at the INEL. At a conceptual level, retrieval of TRU buried waste involves a movable containment building to confine airborne particulate, heavy equipment to remove the waste, processing equipment, and equipment to control the air quality within the building. Studies were performed in FY-87 to identify containment building requirements such as type, mobility, and ventilation. An experimental program to demonstrate the retrieval technique using existing INEL heavy equipment has also been identified. 11 refs., 17 figs., 11 tabs

  8. Coastal erosion and mass wasting along the Canadian Beaufort Sea based on annual airborne LiDAR elevation data

    Science.gov (United States)

    Obu, Jaroslav; Lantuit, Hugues; Grosse, Guido; Günther, Frank; Sachs, Torsten; Helm, Veit; Fritz, Michael

    2017-09-01

    Erosion of permafrost coasts has received increasing scientific attention since 1990s because of rapid land loss and the mobilisation potential of old organic carbon. The majority of permafrost coastal erosion studies are limited to time periods from a few years to decades. Most of these studies emphasize the spatial variability of coastal erosion, but the intensity of inter-annual variations, including intermediate coastal aggradation, remains poorly documented. We used repeat airborne Light Detection And Ranging (LiDAR) elevation data from 2012 and 2013 with 1 m horizontal resolution to study coastal erosion and accompanying mass-wasting processes in the hinterland. Study sites were selected to include different morphologies along the coast of the Yukon Coastal Plain and on Herschel Island. We studied elevation and volume changes and coastline movement and compared the results between geomorphic units. Results showed simple uniform coastal erosion from low coasts (up to 10 m height) and a highly diverse erosion pattern along coasts with higher backshore elevation. This variability was particularly pronounced in the case of active retrogressive thaw slumps, which can decrease coastal erosion or even cause temporary progradation by sediment release. Most of the extremes were recorded in study sites with active slumping (e.g. 22 m of coastline retreat and 42 m of coastline progradation). Coastline progradation also resulted from the accumulation of slope collapse material. These occasional events can significantly affect the coastline position on a specific date and can affect coastal retreat rates as estimated in long term by coastline digitalisation from air photos and satellite imagery. These deficiencies can be overcome by short-term airborne LiDAR measurements, which provide detailed and high-resolution information about quickly changing elevations in coastal areas.

  9. Proceedings of the tenth annual DOE low-level waste management conference: Session 6: Closure and decommissioning

    International Nuclear Information System (INIS)

    1988-12-01

    This document contains eight papers on various aspects of low-level radioactive waste management. Topics include: site closure; ground cover; alternate cap designs; performance monitoring of waste trenches; closure options for a mixed waste site; and guidance for environmental monitoring. Individual papers were processed separately for the data base

  10. Annual Report RCRA Post-Closure Monitoring and Inspections for CAU 112: Area 23 Hazardous Waste Trenches, Nevada Test Site, Nevada, for the period October 2000-July 2001

    International Nuclear Information System (INIS)

    Tobiason, D. S.

    2002-01-01

    This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the Area 23 Hazardous Waste Trenches Resource Conservation and Recovery Act (RCRA) unit, located in Area 23 of the Nevada Test Site, Nye County, Nevada, during the October 2000--July 2001 monitoring period. Inspections of the Area 23 Hazardous Waste Trenches RCRA unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. Physical inspections of the closure were completed quarterly and indicated that the site is in good condition with no significant findings noted. An annual subsidence survey of the elevation markers was conducted in July 2001. There has been no subsidence at any of the markers since monitoring began eight years ago. Precipitation for the period October 2000 through July 2001 was 9.42 centimeters (cm) (3.71 inches [in]) (U.S. National Weather Service, 2001). The prior year annual rainfall (January 2000 through December 2000) was 10.44 cm (4.1 1 in.). The recorded average annual rainfall for this site from 1972 to January 2000 is 14.91 cm (5.87 in.). The objective of the neutron logging program is to monitor the soil moisture conditions along 30 neutron access tubes and detect changes that may be indicative of moisture movement at a point located directly beneath each trench. All monitored access tubes are within the compliance criteria of less than 5 percent residual volumetric moisture content at the compliance point directly beneath each respective trench. Soil conditions remain dry and stable underneath the trenches

  11. 2013 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond

    Energy Technology Data Exchange (ETDEWEB)

    Mike Lewis

    2014-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (#LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond from November 1, 2012–October 31, 2013. The report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Groundwater monitoring data • Status of compliance activities • Noncompliance issues • Discussion of the facility’s environmental impacts. During the 2013 permit year, approximately 238 million gallons of wastewater was discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters are below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

  12. 2014 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, Mike [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site’s Advanced Test Reactor Complex Cold Waste Pond from November 1, 2013–October 31, 2014. The report contains the following information; Facility and system description; Permit required effluent monitoring data and loading rates; Permit required groundwater monitoring data; Status of compliance activities; Noncompliance issues; and Discussion of the facility’s environmental impacts. During the 2014 permit year, approximately 238 million gallons of wastewater were discharged to the Cold Waste Pond. This is well below the maximum annual permit limit of 375 million gallons. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters are below the Ground Water Quality Rule Secondary Constituent Standards in the downgradient monitoring wells.

  13. Proceedings of the eighth annual DOE low-level waste management forum: Technical Session 8, Future DOE low-level waste management

    International Nuclear Information System (INIS)

    1987-02-01

    This volume contains the following papers: (1) DOE Systems Approach and Integration; (2) Impacts of Hazardous Waste Regulation on Low-Level Waste Management; (3) Site Operator Needs and Resolution Status; and (4) Establishment of New Disposal Capacity for the Savannah River Plant. All papers have been processed for inclusion in the Energy Data Base. (AT)

  14. 2016 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    Energy Technology Data Exchange (ETDEWEB)

    Cafferty, Kara Grace [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (WRU-I-0160-01, Modification 1, formerly LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2015, through October 31, 2016.

  15. Characteristics of wastes and soils which affect transport of radionuclides through the soil and their relationship to waste management. Annual report FY78

    International Nuclear Information System (INIS)

    Polzer, W.L.; Fowler, E.B.; Essington, E.H.

    1979-04-01

    Soil samples were collected from Beatty, NV, the University of California, Los Angeles/University of California, Berkeley (UCLA/UCB) project, California and Nebraska. Results of waste/soil interaction studies indicate that waste radionuclides can be categorized into three broad forms; filterable (insoluble) and sorbable and nonsorbable (soluble). The relative distribution of the three depends on the storage time of the waste and on the soil which is interacted with the waste. In the filterable (insoluble) fraction the radionuclides are associated with both organic and inorganic particulates. The primary inorganic particulate was identified as calcium carbonate. The soluble nonsorbable waste radionuclides possess a negative charge with the exception of 137 Cs; that species is positively charged. The presence of negatively charged species is attributed to complexing with either carbonate or chelating compounds. Changes in the soluble fraction of waste radionuclides on storage of waste are attributed in part to the dissolution or precipitation of calcium carbonate and perhaps the degradation of organic material or growth of microorganisms in the waste. 11 figures, 31 tables

  16. Computer Calculation of Fire Danger

    Science.gov (United States)

    William A. Main

    1969-01-01

    This paper describes a computer program that calculates National Fire Danger Rating Indexes. fuel moisture, buildup index, and drying factor are also available. The program is written in FORTRAN and is usable on even the smallest compiler.

  17. Endocrine causes of dangerous fever.

    Science.gov (United States)

    Tenner, Andrea G; Halvorson, Karin M

    2013-11-01

    This article provides an overview of the pathogenesis and signs and symptoms of dangerous endocrine causes of hyperthermia. Treatment strategies based on specific causes are discussed. Copyright © 2013 Elsevier Inc. All rights reserved.

  18. Evaluation of improved chemical waste disposal and recovery methods for N reactor fuel fabrication operations: 1984 annual report

    International Nuclear Information System (INIS)

    Stewart, T.L.; Hartley, J.N.

    1984-12-01

    Pacific Northwest Laboratory personnel identified and evaluated alternative methods for recovery, recycle, and disposal of waste acids produced during N Reactor fuel operations. This work was conducted under a program sponsored by UNC Nuclear Industries, Inc.; the program goals were to reduce the volume of liquid waste by rejuvenating and recycling acid solutions and to generate a residual waste low in nitrates, fluorides, and metals. Disposal methods under consideration included nitric acid reclamation, grout encapsulation of final residual waste, nitrogen fertilizer production, biodenitrifaction, chemical or thermal destruction of NO 3 , and short-term impoundment of liquid NO 3 /SO 4 wastes. Preliminary testing indicated that the most feasible and practicable of these alternatives were (1) nitric acid reclamation followed by grouting of residual waste and (2) nitrogen fertilizer production. This report summarizes the investigations, findings, and recommendations for the 1984 fiscal year

  19. Default-all is dangerous!

    OpenAIRE

    Gatterbauer, Wolfgang; Meliou, Alexandra; Suciu, Dan

    2011-01-01

    We show that the default-all propagation scheme for database annotations is dangerous. Dangerous here means that it can propagate annotations to the query output which are semantically irrelevant to the query the user asked. This is the result of considering all relationally equivalent queries and returning the union of their where-provenance in an attempt to define a propagation scheme that is insensitive to query rewriting. We propose an alternative query-rewrite-insensitive (QRI) where-pro...

  20. Hanford Waste Vitrification Plant dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-10-01

    This report presents engineering drawings of the vitrification plant at Hanford Reservation. Individual sections in the report cover piping and instrumentation, process flow schemes, and material balance tables

  1. The impact of LWR decontaminations on solidification, waste disposal and associated occupational exposure: Annual report, Fiscal year 1987

    International Nuclear Information System (INIS)

    Adams, J.W.; Soo, P.

    1988-06-01

    A study was carried out to determine the extent of corrosion for a range of low-level waste container materials in contact with simulated resin bead decontamination wastes. The materials included metals and high-density polyethylene. Tests were also conducted on mechanical stability of the decontamination resin wastes, solidified in cement and vinyl ester-styrene, during thermal cycling between 60/degree/C and /minus/40/degree/C. 12 refs., 20 figs., 12 tabs

  2. Proceedings of the tenth annual DOE low-level waste management conference: Session 3: Disposal technology and facility development

    Energy Technology Data Exchange (ETDEWEB)

    1988-12-01

    This document contains ten papers on various aspects of low-level radioactive waste management. Topics include: design and construction of a facility; alternatives to shallow land burial; the fate of tritium and carbon 14 released to the environment; defense waste management; engineered sorbent barriers; remedial action status report; and the disposal of mixed waste in Texas. Individual papers were processed separately for the data base. (TEM)

  3. Proceedings of the tenth annual DOE low-level waste management conference: Session 3: Disposal technology and facility development

    International Nuclear Information System (INIS)

    1988-12-01

    This document contains ten papers on various aspects of low-level radioactive waste management. Topics include: design and construction of a facility; alternatives to shallow land burial; the fate of tritium and carbon 14 released to the environment; defense waste management; engineered sorbent barriers; remedial action status report; and the disposal of mixed waste in Texas. Individual papers were processed separately for the data base

  4. 1998 report on Hanford Site land disposal restrictions for mixed waste

    International Nuclear Information System (INIS)

    Black, D.G.

    1998-01-01

    This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-01H. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility. The US Department of Energy, its predecessors, and contractors on the Hanford Facility were involved in the production and purification of nuclear defense materials from the early 1940s to the late 1980s. These production activities have generated large quantities of liquid and solid mixed waste. This waste is regulated under authority of both the Resource Conservation and Recovery Act of l976 and the Atomic Energy Act of 1954. This report covers only mixed waste. The Washington State Department of Ecology, US Environmental Protection Agency, and US Department of Energy have entered into the Tri-Party Agreement to bring the Hanford Facility operations into compliance with dangerous waste regulations. The Tri-Party Agreement required development of the original land disposal restrictions (LDR) plan and its annual updates to comply with LDR requirements for mixed waste. This report is the eighth update of the plan first issued in 1990. The Tri-Party Agreement requires and the baseline plan and annual update reports provide the following information: (1) Waste Characterization Information -- Provides information about characterizing each LDR mixed waste stream. The sampling and analysis methods and protocols, past characterization results, and, where available, a schedule for providing the characterization information are discussed. (2) Storage Data -- Identifies and describes the mixed waste on the Hanford Facility. Storage data include the Resource Conservation and Recovery Act of 1976 dangerous waste codes, generator process knowledge needed to identify the waste and to make LDR determinations, quantities

  5. 1998 report on Hanford Site land disposal restrictions for mixed waste

    Energy Technology Data Exchange (ETDEWEB)

    Black, D.G.

    1998-04-10

    This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-26-01H. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of managing land-disposal-restricted mixed waste at the Hanford Facility. The US Department of Energy, its predecessors, and contractors on the Hanford Facility were involved in the production and purification of nuclear defense materials from the early 1940s to the late 1980s. These production activities have generated large quantities of liquid and solid mixed waste. This waste is regulated under authority of both the Resource Conservation and Recovery Act of l976 and the Atomic Energy Act of 1954. This report covers only mixed waste. The Washington State Department of Ecology, US Environmental Protection Agency, and US Department of Energy have entered into the Tri-Party Agreement to bring the Hanford Facility operations into compliance with dangerous waste regulations. The Tri-Party Agreement required development of the original land disposal restrictions (LDR) plan and its annual updates to comply with LDR requirements for mixed waste. This report is the eighth update of the plan first issued in 1990. The Tri-Party Agreement requires and the baseline plan and annual update reports provide the following information: (1) Waste Characterization Information -- Provides information about characterizing each LDR mixed waste stream. The sampling and analysis methods and protocols, past characterization results, and, where available, a schedule for providing the characterization information are discussed. (2) Storage Data -- Identifies and describes the mixed waste on the Hanford Facility. Storage data include the Resource Conservation and Recovery Act of 1976 dangerous waste codes, generator process knowledge needed to identify the waste and to make LDR determinations, quantities

  6. First annual report RCRA post-closure monitoring and inspections for the U-3fi waste unit. Final report, July 1995--October 1996

    International Nuclear Information System (INIS)

    Emer, D.F.

    1997-01-01

    This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the U-3fi RCRA Unit, located in Area 3 of the Nevada Site (NTS), Nye County, Nevada during the July 1995 to October 1996 period. Inspections of the U-3fi RCRA Unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. The objective of the neutron logging is to monitor the soil moisture conditions along the 420 ft ER3-3 borehole and detect changes that may be indicative of moisture movement in the regulated interval. This is the first annual report on the U-3fi closure and includes the first year baseline monitoring data as well as one quarter of compliance monitoring data

  7. The production of chemicals from food processing wastes using a novel fermenter separator. Annual progress report, January 1993--March 1994

    Energy Technology Data Exchange (ETDEWEB)

    Dale, M.C.; Venkatesh, K.V.; Choi, H.; Salicetti-Piazza, L.; Borgos-Rubio, N.; Okos, M.R.; Wankat, P.C.

    1994-03-15

    The basic objective of this project is to convert waste streams from the food processing industry to usable fuels and chemicals using novel bioreactors. These bioreactors should allow economical utilization of waste (whey, waste sugars, waste starch, bottling wastes, candy wastes, molasses, and cellulosic wastes) by the production of ethanol, acetone/butanol, organic acids (acetic, lactic, and gluconic), yeast diacetyl flavor, and antifungal compounds. Continuous processes incorporating various processing improvements such as simultaneous product separation and immobilized cells are being developed to allow commercial scale utilization of waste stream. The production of ethanol by a continuous reactor-separator is the process closest to commercialization with a 7,500 liter pilot plant presently sited at an Iowa site to convert whey lactose to ethanol. Accomplishments during 1993 include installation and start-up of a 7,500 liter ICRS for ethanol production at an industry site in Iowa; Donation and installation of a 200 liter yeast pilot Plant to the project from Kenyon Enterprises; Modeling and testing of a low energy system for recovery of ethanol from vapor is using a solvent absorption/extractive distillation system; Simultaneous saccharification/fermentation of raw corn grits and starch in a stirred reactor/separator; Testing of the ability of `koji` process to ferment raw corn grits in a `no-cook` process.

  8. Proceedings of the tenth annual DOE low-level waste management conference: Session 2: Site performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    1988-12-01

    This document contains twelve papers on various aspects of low-level radioactive waste management. Topics of this volume include: performance assessment methodology; remedial action alternatives; site selection and site characterization procedures; intruder scenarios; sensitivity analysis procedures; mathematical models for mixed waste environmental transport; and risk assessment methodology. Individual papers were processed separately for the database. (TEM)

  9. Proceedings of the tenth annual DOE low-level waste management conference: Session 2: Site performance assessment

    International Nuclear Information System (INIS)

    1988-12-01

    This document contains twelve papers on various aspects of low-level radioactive waste management. Topics of this volume include: performance assessment methodology; remedial action alternatives; site selection and site characterization procedures; intruder scenarios; sensitivity analysis procedures; mathematical models for mixed waste environmental transport; and risk assessment methodology. Individual papers were processed separately for the database

  10. Proceedings of the tenth annual DOE low-level waste management conference: Session 1: Institutional and regulatory issues

    International Nuclear Information System (INIS)

    1988-12-01

    This document contains eleven papers on various aspects of low-level radioactive waste regulation. Topics include: EPA environmental standards; international exemption principles; the concept of below regulatory concern; envirocare activities in Utah; mixed waste; FUSRAP and the Superfund; and a review of various incentive programs. Individual papers are processed separately for the data base

  11. Annual Progress Report on the Development of Waste Tank Leak Monitoring and Detection and Mitigation Activities in Support of M-45-08

    International Nuclear Information System (INIS)

    DEFIGH PRICE, C.

    2000-01-01

    Milestone M-45-09E of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement or TPA) [TPA 1996] requires submittal of an annual progress report on the development of waste tank leak detection, monitoring, and mitigation (LDMM) activities associated with the retrieval of waste from single-shell tanks (SSTs). This report details progress for fiscal year 2000, building on the current LDMM strategy and including discussion of technologies, applications, cost, schedule, and technical data. The report also includes discussion of demonstrations conducted and recommendations for additional testing. Tri-Party Agreement Milestones M-45-08A and M-45-08B required design and demonstration of LDMM systems for initial retrieval of SST waste. These specific milestones have recently been deleted as part of the M-45-00A change package. Future LDMM development work has been incorporated into specific technology demonstration milestones and SST waste retrieval milestones in the M-45-03 and M-45-05 milestone series

  12. 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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-12-31

    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.

  13. ANDRA - National Radioactive Waste Management Agency. Annual sustainable development and activity report 2012. Management report and financial statements 2012

    International Nuclear Information System (INIS)

    2013-01-01

    Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity and Sustainable Development Report, with the management and financial statements report, of the Andra for the year 2012

  14. ANDRA - National Radioactive Waste Management Agency. Annual sustainable development and activity report 2011. Management report and financial statements 2011

    International Nuclear Information System (INIS)

    2012-01-01

    Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity and Sustainable Development Report, with the management and financial statements report, of the Andra for the year 2011

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

    International Nuclear Information System (INIS)

    1993-01-01

    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

  16. 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.

  17. 2014 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, Mike [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (WRU-I-0160-01, formerly LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2013 through October 31, 2014. The report contains the following information; Facility and system description; Permit required effluent monitoring data and loading rates; Groundwater monitoring data; Status of special compliance conditions; Noncompliance issues; and Discussion of the facility’s environmental impacts During the 2014 reporting year, an estimated 10.11 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 17 million gallons per year. The concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the applicable Idaho Department of Environmental Quality’s groundwater quality standard levels.

  18. 2012 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    Energy Technology Data Exchange (ETDEWEB)

    Mike Lewis

    2013-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (WRU-I-0160-01, formerly LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2011 through October 31, 2012. The report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Groundwater monitoring data • Status of special compliance conditions • Discussion of the facility’s environmental impacts During the 2012 reporting year, an estimated 11.84 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 17 million gallons per year. The concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the Ground Water Quality Rule Primary and Secondary Constituent Standards.

  19. 2011 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    Energy Technology Data Exchange (ETDEWEB)

    David Frederick

    2012-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (LA-000160-01), for the wastewater reuse site at the Idaho National Laboratory Site's Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2010 through October 31, 2011. The report contains the following information: (1) Facility and system description; (2) Permit required effluent monitoring data and loading rates; (3) Groundwater monitoring data; (4) Status of special compliance conditions; and (5) Discussion of the facility's environmental impacts. During the 2011 reporting year, an estimated 6.99 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 13 million gallons per year. Using the dissolved iron data, the concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the Ground Water Quality Rule Primary and Secondary Constituent Standards.

  20. Annual report -- 1992: Environmental surveillance for EG & G Idaho Waste Management Facilities at the Idaho National Engineering Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Wilhelmsen, R.N.; Wright, K.C.; McBride, D.W.

    1993-08-01

    This report describes the 1992 environmental surveillance activities of the Environmental Monitoring Unit of EG&G Idaho, Inc., at EG&G Idaho-operated Waste Management facilities at the Idaho National Engineering Laboratory (INEL). The major facilities monitored include the Radioactive Waste Management Complex, the Waste Experimental Reduction Facility, the Mixed Waste Storage Facility, and two surplus facilities. Included are some results of the sampling performed by the Radiological and Environmental Sciences Laboratory and the United States Geological Survey. The primary purposes of monitoring are to evaluate environmental conditions, to provide and interpret data, to ensure compliance with applicable regulations or standards, and to ensure protection of human health and the environment. This report compares 1992 environmental surveillance data with DOE derived concentration guides, and with data from previous years.

  1. Annual technology assessment and progress report for the Buried Transuranic Waste Program at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Low, J.O.

    1985-12-01

    An improved-confinement technology as applied to the Idaho National Engineering Laboratory (INEL) shallow-land-buried transuranic (TRU) waste is being investigated. An improved-confinement technology, in situ grouting, is being demonstrated in a 2-year engineering feasibility test at the INEL. Grout formulation and development were completed by Oak Ridge National Laboratory in Tennessee to support the in situ grouting test. Three grout formulations have been adapted to the arid, unsaturated soil conditions at the INEL: ordinary particulate grout; microfine penetration grout; soil grout. Three test trenches were constructed north of the INEL's Subsurface Disposal Area (SDA). Nonradioactive waste forms closely resembling TRU waste buried at the INEL have been fabricated and are ready for emplacement into these test trenches. A literature search for a simulated (analog) TRU tracer was completed as well as a chemical characterization of the INEL soil. Data developed from the chemistry characterization and literature search have been inputed into the selection and laboratory testing of the TRU analog tracers. Simulated TRU tracers will be loaded into waste forms prior to emplacement into the test trenches. Test trench data acquisition instrumentation will be installed during waste form emplacement. Instrumentation will monitor for moisture movement and tracer detection. Plans for test completion in FY-1986 are also shown. Various buried waste improved-confinement technologies performed by other Department of Energy sites were assessed for applicability to the INEL buried TRU waste. Primary demonstrations were performed at the Hanford site in Washington and at ORNL. This report also includes information on accomplishments of related activities at the INEL such as the program for Environmental Surveillance of the Radioactive Waste Management complex as well as the Subsurface Migration Studies. 18 refs., 11 figs., 12 tabs

  2. Are low radiation doses Dangerous?

    International Nuclear Information System (INIS)

    Garcia Lima, O.; Cornejo, N.

    1996-01-01

    In the last few years the answers to this questions has been affirmative as well as negative from a radiation protection point of view low doses of ionizing radiation potentially constitute an agent causing stochasting effects. A lineal relation without threshold is assumed between dose and probability of occurrence of these effects . Arguments against the danger of probability of occurrence of these effects. Arguments again the danger of low dose radiation are reflected in concepts such as Hormesis and adaptive response, which are phenomena that being studied at present

  3. Carbon dioxide dangers demonstration model

    Science.gov (United States)

    Venezky, Dina; Wessells, Stephen

    2010-01-01

    Carbon dioxide is a dangerous volcanic gas. When carbon dioxide seeps from the ground, it normally mixes with the air and dissipates rapidly. However, because carbon dioxide gas is heavier than air, it can collect in snowbanks, depressions, and poorly ventilated enclosures posing a potential danger to people and other living things. In this experiment we show how carbon dioxide gas displaces oxygen as it collects in low-lying areas. When carbon dioxide, created by mixing vinegar and baking soda, is added to a bowl with candles of different heights, the flames are extinguished as if by magic.

  4. Annual Report RCRA Post-Closure Monitoring and Inspections for CAU 112: Area 23 Hazardous Waste Trenches, Nevada Test Site, Nevada, for the Period October 1999-October 2000

    Energy Technology Data Exchange (ETDEWEB)

    D. F. Emer

    2001-03-01

    This annual Neutron Soil Moisture Monitoring report provides an analysis and summary for site inspections, meteorological information, and neutron soil moisture monitoring data obtained at the Area 23 Hazardous Waste Trenches Resource Conservation and Recovery Act (RCRA) unit, located in Area 23 of the Nevada Test Site, Nye County, Nevada, during the October 1999-October 2000 period. Inspections of the Area 23 Hazardous Waste Trenches RCRA unit are conducted to determine and document the physical condition of the covers, facilities, and any unusual conditions that could impact the proper operation of the waste unit closure. Physical inspections of the closure were completed quarterly and indicated that the site is in good condition with no significant findings noted. An annual subsidence survey of the elevation markers was conducted in August 2000. There has been no subsidence at any of the markers since monitoring began seven years ago. The objective of the neutron logging program is to monitor the soil moisture conditions along 30 neutron access tubes and detect changes that maybe indicative of moisture movement at a point located directly beneath each trench. Precipitation for the period October 1999 through October 2000 was 10.44 centimeters (cm) (4.11 inches [in.]) (U.S. National Weather Service, 2000). The prior year annual rainfall (January 1999 through December 1999) was 10.13cm (3.99 in.). The highest 30-day cumulative rainfall occurred on March 8, 2000, with a total of 6.63 cm (2.61 in.). The heaviest daily precipitation occurred on February 23,2000, with a total of 1.70 cm (0.67 in.) falling in that 24-hour period. The recorded average annual rainfall for this site, from 1972 to January 1999, is 15.06 cm (5.93 in.). All monitored access tubes are within the compliance criteria of less than 5 percent residual volumetric moisture content at the compliance point directly beneath each respective trench. Soil conditions remain dry and stable underneath the

  5. A dangerous movie? Hollywood does psychoanalysis.

    Science.gov (United States)

    Ferrell, Donald R; Silverman, Martin A

    2014-12-01

    After the appearance of David Cronenberg's film A Dangerous Method in 2011, dealing with the relationships of Sigmund Freud, C. G. Jung and Sabina Spielrein, Dr. Donald Ferrell published: A Dangerous Method, A Film Directed by David Cronenberg: An Extended Review (Ferrell 2012) in the Journal of Religion and Health. Upon its publication, Dr. Ferrell's article was nominated for a Gradiva Award by the National Association for the Advancement of Psychoanalysis. On November 1, 2013, the Association for the Psychoanalysis of Culture and Society held its annual conference at Rutgers University, New Brunswick, NJ. Dr. Billie Pivnick, a member at large of the Board of Directors of the APCS and also on the Editorial Board of the Journal of Religion and Health, persuaded the 2013 Conference Program Committee that Cronenberg's film would make an interesting subject for discussion for conference participants. To that end, Dr. Pivnick invited Dr. Ferrell, C. G. Jung Institute of New York, Dr. Steven Reisner, Coalition for an Ethical Psychology, and Dr. Martin Silverman, Training and Supervising Analyst and Supervising Child Analyst at the Institute for Psychoanalytic Education, NYU College of Medicine, Training and Supervising Analyst at the Center for Psychotherapy and Psychoanalysis of New Jersey, and Associate Editor of The Psychoanalytic Quarterly to serve as panel members to discuss: A Dangerous Movie? Hollywood does Psychoanalysis. Presentations on Cronenberg's film and the early history of psychoanalysis were given by Drs. Ferrell and Reisner, followed by a response to their presentations by Dr. Silverman. Dr. Pivnick chaired the session. The articles presented here were given originally at the APCS conference by Dr. Ferrell and Dr. Silverman. Dr. Reisner declined the invitation to submit his presentation for publication. Dr. Silverman's remarks were based not only on the presentation given by Dr. Ferrell at the session on A Dangerous Movie?, but also on his close and

  6. An analysis of the annual probability of failure of the waste hoist brake system at the Waste Isolation Pilot Plant (WIPP)

    Energy Technology Data Exchange (ETDEWEB)

    Greenfield, M.A. [Univ. of California, Los Angeles, CA (United States); Sargent, T.J.

    1995-11-01

    The Environmental Evaluation Group (EEG) previously analyzed the probability of a catastrophic accident in the waste hoist of the Waste Isolation Pilot Plant (WIPP) and published the results in Greenfield (1990; EEG-44) and Greenfield and Sargent (1993; EEG-53). The most significant safety element in the waste hoist is the hydraulic brake system, whose possible failure was identified in these studies as the most important contributor in accident scenarios. Westinghouse Electric Corporation, Waste Isolation Division has calculated the probability of an accident involving the brake system based on studies utilizing extensive fault tree analyses. This analysis conducted for the U.S. Department of Energy (DOE) used point estimates to describe the probability of failure and includes failure rates for the various components comprising the brake system. An additional controlling factor in the DOE calculations is the mode of operation of the brake system. This factor enters for the following reason. The basic failure rate per annum of any individual element is called the Event Probability (EP), and is expressed as the probability of failure per annum. The EP in turn is the product of two factors. One is the {open_quotes}reported{close_quotes} failure rate, usually expressed as the probability of failure per hour and the other is the expected number of hours that the element is in use, called the {open_quotes}mission time{close_quotes}. In many instances the {open_quotes}mission time{close_quotes} will be the number of operating hours of the brake system per annum. However since the operation of the waste hoist system includes regular {open_quotes}reoperational check{close_quotes} tests, the {open_quotes}mission time{close_quotes} for standby components is reduced in accordance with the specifics of the operational time table.

  7. An analysis of the annual probability of failure of the waste hoist brake system at the Waste Isolation Pilot Plant (WIPP)

    International Nuclear Information System (INIS)

    Greenfield, M.A.; Sargent, T.J.

    1995-11-01

    The Environmental Evaluation Group (EEG) previously analyzed the probability of a catastrophic accident in the waste hoist of the Waste Isolation Pilot Plant (WIPP) and published the results in Greenfield (1990; EEG-44) and Greenfield and Sargent (1993; EEG-53). The most significant safety element in the waste hoist is the hydraulic brake system, whose possible failure was identified in these studies as the most important contributor in accident scenarios. Westinghouse Electric Corporation, Waste Isolation Division has calculated the probability of an accident involving the brake system based on studies utilizing extensive fault tree analyses. This analysis conducted for the U.S. Department of Energy (DOE) used point estimates to describe the probability of failure and includes failure rates for the various components comprising the brake system. An additional controlling factor in the DOE calculations is the mode of operation of the brake system. This factor enters for the following reason. The basic failure rate per annum of any individual element is called the Event Probability (EP), and is expressed as the probability of failure per annum. The EP in turn is the product of two factors. One is the open-quotes reportedclose quotes failure rate, usually expressed as the probability of failure per hour and the other is the expected number of hours that the element is in use, called the open-quotes mission timeclose quotes. In many instances the open-quotes mission timeclose quotes will be the number of operating hours of the brake system per annum. However since the operation of the waste hoist system includes regular open-quotes reoperational checkclose quotes tests, the open-quotes mission timeclose quotes for standby components is reduced in accordance with the specifics of the operational time table

  8. ANL technical support program for DOE Environmental Restoration and Waste Management. Annual report, October 1991--September 1992

    Energy Technology Data Exchange (ETDEWEB)

    Bates, J.K.; Bradley, C.R.; Buck, E.C.; Cunnane, J.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Gerding, T.J.; Gong, M.; Hoh, J.C.; Mazer, J.J.; Wronkiewicz, D.J. [Argonne National Lab., IL (United States); Bourcier, W.L.; Morgan, L.E.; Newton, L.; Nielsen, J.K.; Phillips, B.L. [Lawrence Livermore National Lab., CA (United States); Ewing, R.C.; Wang, L. [Univ. of New Mexico, Albuquerque, NM (United States); Li, H.; Tomozawa, M. [Rensselaer Polytechnic Inst., Troy, NY (United States)

    1993-05-01

    A program was established for DOE Environmental Restoration and Waste Management (EM) to evaluate factors that are anticipated to affect waste glass reaction during repository disposal, especially in an unsaturated environment typical of what may be expected for the proposed Yucca Mountain repository site. This report covers progress in FY 1992 on the following tasks: 1. A compendium of the characteristics of high-level nuclear waste borosilicate glass has been written. 2. A critical review of important parameters that affect the reactivity of glass in an unsaturated environment is being prepared. 3. A series of tests has been started to evaluate the reactivity of fully radioactive glasses in a high-level waste repository environment and compare it to the reactivity of synthetic, nonradioactive glasses of similar composition. 4. The effect of radiation upon the durability of waste glasses at a high glass surface area-to-liquid volume (SA/V) ratio and a high gas-to-liquid volume ratio will be assessed. These tests address both vapor and high SA/V liquid conditions. 5. A series of tests is being performed to compare the extent of reaction of nuclear waste glasses at various SAN ratios. Such differences in the SAN ratio may significantly affect glass durability. 6. A series of natural analogue tests is being analyzed to demonstrate a meaningful relationship between experimental and natural alteration conditions. 7. Analytical electron microscopy (AEM), infrared spectroscopys and nuclear resonant profiling are being used to assess the glass/water reaction pathway by identifying intermediate phases that appear on the reacting glass. Additionally, colloids from the leach solutions are being studied using AEM. 8. A technical review of AEM results is being provided. 9. A study of water diffusion involving nuclear waste glasses is being performed. 10. A mechanistically based model is being developed to predict the performance of glass over repository-relevant time periods.

  9. 2007 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2008-01-01

    This report summarizes the results of an annual review of conditions affecting the operation of the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) and a determination of the continuing adequacy of the performance assessments (PAs) and composite analyses (CAs). The Area 5 RWMS PA documentation consists of the original PA (Shott et al., 1998), referred to as the 1998 Area 5 RWMS PA and supporting addenda (Bechtel Nevada [BN], 2001b; 2006a). The Area 5 RWMS CA was issued as a single document (BN, 2001a) and has a single addendum (BN, 2001c). The Area 3 PA and CA were issued in a single document (Shott et al., 2000). The Maintenance Plan for the PAs and CAs (National Security Technologies, LLC [NSTec], 2006) and the Disposal Authorization Statements (DASs) for the Area 3 and 5 RWMSs (U.S. Department of Energy [DOE], 2000; 2002) require preparation of an annual summary and a determination of the continuing adequacy of the PAs and CAs. The annual summary report is submitted to DOE Headquarters. Following the annual report format in the DOE PA/CA Maintenance Guide (DOE, 1999), this report presents the annual summary for the PAs in Section 2.0 and the CAs in Section 3.0. The annual summary for the PAs includes the following: Section 2.1 summarizes changes in waste disposal operations; Section 2.1.5 provides an evaluation of the new estimates of the closure inventories derived from the actual disposals through fiscal year (FY) 2007; Section 2.2 summarizes the results of the monitoring conducted under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's (NNSA/NSO's) Integrated Closure and Monitoring Plan for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (BN, 2005), and the research and development (R&D) activities; Section 2.4 is a summary of changes in facility design, operation, or expected future conditions; monitoring and R&D activities; and the maintenance program; and

  10. 2007 Annual Summary Report for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site, Nye County, Nevada

    International Nuclear Information System (INIS)

    NSTec Environmental Management

    2008-01-01

    This report summarizes the results of an annual review of conditions affecting the operation of the Area 3 and Area 5 Radioactive Waste Management Sites (RWMSs) and a determination of the continuing adequacy of the performance assessments (PAs) and composite analyses (CAs). The Area 5 RWMS PA documentation consists of the original PA (Shott et al., 1998), referred to as the 1998 Area 5 RWMS PA and supporting addenda (Bechtel Nevada [BN], 2001b; 2006a). The Area 5 RWMS CA was issued as a single document (BN, 2001a) and has a single addendum (BN, 2001c). The Area 3 PA and CA were issued in a single document (Shott et al., 2000). The Maintenance Plan for the PAs and CAs (National Security Technologies, LLC [NSTec], 2006) and the Disposal Authorization Statements (DASs) for the Area 3 and 5 RWMSs (U.S. Department of Energy [DOE], 2000; 2002) require preparation of an annual summary and a determination of the continuing adequacy of the PAs and CAs. The annual summary report is submitted to DOE Headquarters. Following the annual report format in the DOE PA/CA Maintenance Guide (DOE, 1999), this report presents the annual summary for the PAs in Section 2.0 and the CAs in Section 3.0. The annual summary for the PAs includes the following: Section 2.1 summarizes changes in waste disposal operations; Section 2.1.5 provides an evaluation of the new estimates of the closure inventories derived from the actual disposals through fiscal year (FY) 2007; Section 2.2 summarizes the results of the monitoring conducted under the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office's (NNSA/NSO's) Integrated Closure and Monitoring Plan for the Area 3 and Area 5 Radioactive Waste Management Sites at the Nevada Test Site (BN, 2005), and the research and development (R and D) activities; Section 2.4 is a summary of changes in facility design, operation, or expected future conditions; monitoring and R and D activities; and the maintenance program; and

  11. The Clinical Prediction of Dangerousness.

    Science.gov (United States)

    1985-05-01

    psychopathic subgroup of personality disorders. Sociopathic , psychopathic and antisocial disorders are generally accepted as equivalent terms. Cleckley (1964...of Factors Influencing the Decision to Hospitalize ............................... 48 Table 3. Frequency of Differences between Dangerousness and...53 Table 6. Examination for Different Responses to Questionnaire Items by those Subjects with Vignette A and those with Vignette

  12. 2010 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond

    International Nuclear Information System (INIS)

    Lewis, Mike

    2011-01-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (LA 000161 01, Modification B), for the wastewater land application site at the Idaho National Laboratory Site's Advanced Test Reactor Complex Cold Waste Pond from November 1, 2009 through October 31, 2010. The report contains the following information: (1) Facility and system description; (2) Permit required effluent monitoring data and loading rates; (3) Groundwater monitoring data; (4) Status of compliance activities; and (5) Discussion of the facility's environmental impacts. During the 2010 permit year, approximately 164 million gallons of wastewater were discharged to the Cold Waste Pond. As shown by the groundwater sampling data, sulfate and total dissolved solids concentrations are highest near the Cold Waste Pond and decrease rapidly as the distance from the Cold Waste Pond increases. Although concentrations of sulfate and total dissolved solids are elevated near the Cold Waste Pond, both parameters were below the Ground Water Quality Rule Secondary Constituent Standards in the down gradient monitoring wells.

  13. Microstructural properties of high level waste concentrates and gels with raman and infrared spectroscopies. 1997 annual progress report

    International Nuclear Information System (INIS)

    Agnew, S.F.; Coarbin, R.A.; Johnston, C.T.

    1997-01-01

    'Monosodium aluminate, the phase of aluminate found in waste tanks, is only stable over a fairly narrow range of water vapor pressure (22% relative humidity at 22 C). As a result, aluminate solids are stable at Hanford (seasonal average RH ∼20%) but are not be stable at Savannah River (seasonal average RH ∼40%). Monosodium aluminate (MSA) releases water upon precipitation from solution. In contrast, trisodium aluminate (TSA) consumes water upon precipitation. As a result, MSA precipitates gradually over time while TSA undergoes rapid accelerated precipitation, often gelling its solution. Raman spectra reported for first time for monosodium and trisodium aluminate solids. Ternary phase diagrams can be useful for showing effects of water removal, even with concentrated waste. Kinetics of monosodium aluminate precipitation are extremely slow (several months) at room temperature but quite fast (several hours) at 60 C. As a result, all waste simulants that contain aluminate need several days of cooking at 60 C in order to truly represent the equilibrium state of aluminate. The high level waste (HLW) slurries that have been created at the Hanford and Savannah River Sites over that last fifty years constitute a large fraction of the remaining HLW volumes at both sites. In spite of the preponderance of these wastes, very little quantitative information is available about their physical and chemical properties other than elemental analyses.'

  14. Is There a Link Between Actual and Perceived Wildfire Danger?

    OpenAIRE

    Kaval, Pamela

    2008-01-01

    Over the last 20 years, costs for wildfire initial attack in the U.S. have increased significantly. The increased cost relates to wildfire suppression practices as well as the growing number of wildland urban interface (WUI) homes. Requiring WUI residents to pay an annual tax for their wildfire risk would lower costs to the general taxpayer. Willingness-to-pay (WTP) for wildfire prevention, in relation to both perceived and actual wildfire danger, was the focus of this study. Colorado WUI res...

  15. Superconducting open-gradient magnetic separation for the pretreatment of radioactive or mixed waste vitrification feeds. 1998 annual progress report

    International Nuclear Information System (INIS)

    Crawford, C.; Doctor, R.D.; Landsberger, S.; Nunez, L.; Ritter, J.

    1998-01-01

    'The objective is to reduce the volume and cost of high-level waste glass produced during US DOE remediation activities by demonstrating that magnetic separation can separate crystalline, amorphous, and colloidal constituents in vitrification feed streams known to be deleterious to the production of borosilicate glass. Magnetic separation will add neither chemicals nor generate secondary waste streams. The project includes the systematic study of magnetic interactions of waste constituents under controlled physical and chemical conditions (e.g., hydration, oxidation, temperature) to identify mechanisms that control the magnetic properties. Partitioning of radionuclides to determine their sorption mechanisms is also being studied. The identification of fundamental magnetic properties within the microscopic chemical environment in combination with hydrodynamic and electrodynamic models provides insights into the design of a system for optimal separation. Following this, experimental studies using superconducting open-gradient magnetic separation (OGMS) will be conducted to validate its effectiveness as a pretreatment technique.'

  16. Buried Transuranic Waste Studies Program at the Idaho National Engineering Laboratory: Annual technology assessment and progress report

    International Nuclear Information System (INIS)

    Low, J.O.; Allman, D.W.; Shaw, P.G.; Sill, C.W.

    1987-01-01

    In-situ grouting, an improved-confinement technology that could be applied to the Idaho National Engineering Laboratory (INEL) shallow-land-buried transuranic (TRU) waste, is being investigated by EG and G Idaho, Inc. In situ grouting has been demonstrated as the culmination of a two-year engineering feasibility test at the INEL. In situ stabilization and hydrologic isolation of a simulated buried TRU waste trench at an arid site were performed using an experimental dynamic compaction in situ grouting process developed by Rockwell Hanford Operations (RHO). A series of laboratory evaluations relative to the grout permeation characteristics of microfine particulate cements with INEL-type soil was performed prior to the grouting operations. In addition, an extensive pre-grouting hydrologic assessment of the test trench was performed to support the performance assessment analysis. Laboratory testing of various chemical materials yielded a suitable hydrologic tracer for use in the hydrologic monitoring phase of the experiment. Various plutonium transport laboratory evaluations were performed to assess the plutonium retention capabilities of a microfine grout/INEL-soil waste product similar to that expected to result if the grout is injected in situ into the INEL test trench. The test trench will be hydrologically assessed in FY 1987 to determine if the RHO grouting system attained the performance acceptance criteria of the experiment. The report includes a technology assessment of buried waste technologies developed by other DOE sites. Field demonstrations at ORNL and Hanford are reported under this technology assessment. Also included is information on activities related to buried waste management at the INEL. These include environmental surveillance of the Radioactive Waste Management Complex and the Subsurface Migration Studies Program

  17. 2013 Annual Industrial Wastewater Reuse Report for the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond

    Energy Technology Data Exchange (ETDEWEB)

    Mike Lewis

    2014-02-01

    This report describes conditions, as required by the state of Idaho Industrial Wastewater Reuse Permit (WRU-I-0160-01, formerly LA 000160 01), for the wastewater reuse site at the Idaho National Laboratory Site’s Materials and Fuels Complex Industrial Waste Ditch and Industrial Waste Pond from November 1, 2012 through October 31, 2013. The report contains the following information: • Facility and system description • Permit required effluent monitoring data and loading rates • Groundwater monitoring data • Status of special compliance conditions • Discussion of the facility’s environmental impacts During the 2013 reporting year, an estimated 9.64 million gallons of wastewater were discharged to the Industrial Waste Ditch and Pond which is well below the permit limit of 17 million gallons per year. The concentrations of all permit-required analytes in the samples from the down gradient monitoring wells were below the applicable Idaho Department of Environmental Quality’s groundwater quality standard levels.

  18. Proceedings of the Fifth Annual Participants' Information Meeting: DOE Low-Level Waste Management Program

    Energy Technology Data Exchange (ETDEWEB)

    1983-12-01

    The meeting consisted of the following six sessions: (1) plenary session I; (2) disposal technology; (3) characteristics and treatment of low-level waste; (4) environmental aspects and performance prediction; (5) overall summary sessions; and (6) plenary session II. Fifty two papers of the papers presented were processed for inclusion in the Energy Data Base. (ATT)

  19. Annual Status Report (FY2015) Composite Analysis for Low Level Waste Disposal in the Central Plateau of the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Nichols, W. E. [CH2M Hill Plateau Remediation Company, Richland, WA (United States)

    2016-03-24

    In accordance with U.S. Department of Energy (DOE) requirements in DOE O 435.1, and as implemented by DOE/RL-2000-29, the DOE Richland Operations Office has prepared this annual summary of the Hanford Site Composite Analysis for fiscal year 2015.

  20. Annual Status Report (FY2013 Composite Analysis of Low Level Waste Disposal in the Central Plateau at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Nichols, W. E. [CH2M HILL Plateau Remediation Company, Richland, WA (United States)

    2014-03-25

    In accordance with U.S. Department of Energy (DOE) requirements in DOE O 435.1, 3 Chg. 11, and as implemented by DOE/RL-2000-29, Rev. 22, the DOE Richland Operations 4 Office (DOE-RL) has prepared this annual summary of the Hanford Site Composite Analysis 5 for fiscal year (FY) 2013.

  1. Annual Status Report (FY 2017): Composite Analysis for Low Level Waste Disposal in the Central Plateau of the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Weber, M. C.; Nichols, W. E.; Lehman, L. L.

    2018-04-05

    In accordance with U.S. Department of Energy (DOE) requirements in DOE M 435.1 Chg. 1, and as implemented by DOE/RL-2009-29, the DOE Richland Operations Office has prepared this annual summary of the Hanford Site Composite Analysis for fiscal year 2017.

  2. Annual Status Report (FY2016) Composite Analysis for Low Level Waste Disposal in the Central Plateau of the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Weber, M. C. [INTERA, Inc., Austin, TX (United States); Nichols, W. E. [CH2M Hill Plateau Remediation Company, Richland, WA (United States)

    2017-03-14

    In accordance with U.S. Department of Energy (DOE) requirements in DOE O 435.1 and as implemented by DOE/RL-2009-29, the DOE Richland Operations Office has prepared this annual summary of the Hanford Site Composite Analysis for fiscal year 2016.

  3. Potential microbial impact on transuranic wastes under conditions expected in the Waste Isolation Pilot Plant (WIPP). Annual report, October 1, 1978-September 30, 1979

    International Nuclear Information System (INIS)

    Barnhart, B.J.; Campbell, E.W.; Martinez, E.; Caldwell, D.E.; Hallett, R.

    1980-07-01

    Previous results were confirmed showing elevated frequencies of radiation-resistant bacteria in microorganisms isolated from shallow transuranic (TRU) burial soil that exhibits nanocurie levels of beta and gamma radioactivity. Research to determine whether plutonium could be methylated by the microbially produced methyl donor, methylcobalamine, was terminated when literature and consulting radiochemists confirmed that other alkylated transuranic elements are extremely short-lived in the presence of oxygen. Emphasis was placed on investigation of the dissolution of plutonium dioxide by complex formation between plutonium and a polyhydroxamate chelate similar to that produced by microorganisms. New chromatographic and spectrophotometric evidence supports previous results showing enhanced dissolution of alpha radioactivity when 239 Pu dioxide was mixed with the chelate Desferol. Microbial degradation studies of citrate, ethylenediamine tetraacetate (EDTA), and nitrilo triacetate (NTA) chelates of europium are in progress. Current results are summarized. All of the chelates were found to degrade. The average half-life for citrate, NTA, and EDTA was 3.2, 8.0, and 28 years, respectively. Microbial CO 2 generation is also in progress in 72 tests on several waste matrices under potential WIPP isolation conditions. The mean rate of gas generation was 5.97 μg CO 2 /g waste/day. Increasing temperature increased rates of microbial gas generation across treatments of brine, varying water content, nutrient additions, and anaerobic conditions. No microbial growth was detected in experiments to enumerate and identify the microorganisms in rocksalt cores from the proposed WIPP site. This report contains the year's research results and recommendations derived for the design of safe storage of TRU wastes under geologic repository conditions

  4. Xylitol and Your Dog: Danger, Paws Off

    Science.gov (United States)

    ... Home For Consumers Consumer Updates Xylitol and Your Dog: Danger, Paws Off Share Tweet Linkedin Pin it ... vitamins mouthwash toothpaste Why is Xylitol Dangerous to Dogs, but Not People? In both people and dogs, ...

  5. ANL Technical Support Program for DOE Environmental Restoration and Waste Management. Annual report, October 1992--September 1993

    International Nuclear Information System (INIS)

    Bates, J.K.; Bourcier, W.L.; Bradley, C.R.

    1994-06-01

    This report is an overview of the progress during FY 1993 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defense Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are anticipated to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: reviewing and evaluating available data on parameters that will be important in establishing the long-term performance of glass in a repository environment; performing tests to further quantify the effects of important variables where there are deficiencies in the available data; and initiating long-term tests to determine glass performance under a range of conditions applicable to repository disposal

  6. ANL Technical Support Program for DOE Environmental Restoration and Waste Management; Annual report, October 1992--September 1993

    Energy Technology Data Exchange (ETDEWEB)

    Bates, J.K.; Bourcier, W.L.; Bradley, C.R. [and others

    1994-06-01

    This report is an overview of the progress during FY 1993 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defense Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are anticipated to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: reviewing and evaluating available data on parameters that will be important in establishing the long-term performance of glass in a repository environment; performing tests to further quantify the effects of important variables where there are deficiencies in the available data; and initiating long-term tests to determine glass performance under a range of conditions applicable to repository disposal.

  7. Field lysimeter investigations: Low-level waste data base development program for fiscal year 1996. Annual report; Volume 9

    International Nuclear Information System (INIS)

    McConnell, J.W. Jr.; Rogers, R.D.; Larsen, I.L.; Sanford, W.E.; Sullivan, T.M.; Fuhrmann, M.

    1997-08-01

    A data base development program, funded by the US Nuclear Regulatory Commission, is (a) studying the degradation effects in organic ion-exchange resins caused by radiation, (b) examining the adequacy of test procedures recommended in the Branch Technical Position on Waste Form to meet the requirements of 10 CFR 61 using solidified ion-exchange resins, (c) obtaining performance information on solidified ion-exchange resins in a disposal environment, and (d) determining the condition of liners used to dispose the ion-exchange resins. During the field testing experiments, both portland type 1--2 cement and Dow vinyl ester-styrene waste form samples were tested in lysimeter arrays located at Argonne National Laboratory-East (ANL-E) in Illinois and at Oak Ridge National Laboratory (ORNL). The study was designed to provide continuous data on nuclide release and movement, as well as environmental conditions, over an extended period. Those experiments have been shut down and are to be exhumed. This report discusses the plans for removal, sampling, and analysis of waste form and soil cores from the lysimeters. Results of partition coefficient determinations are presented, as well as application of a source term computer code using those coefficients to predict the lysimeter results. A study of radionuclide-containing colloids associated with the leachate waters removed from these lysimeters is described. An update of upward migration of radionuclides in the sand-filled lysimeter at ORNL is included

  8. Annual Hanford Site environmental permitting status report

    Energy Technology Data Exchange (ETDEWEB)

    Sonnichsen, J.C.

    1998-09-17

    The information contained and/or referenced in this Annual Hanford Site Environmental Permitting Status Report (Status Report) addresses the State Environmental Policy Act (SEPA) of 1971 and Condition II.W. of the Resource Conservation and Recovery Act (RCRA) of 1976 Permit, Dangerous Waste Portion (DW Portion). Condition II.W. of the RCRA Permit specifies the Permittees are responsible for all other applicable federal, state, and local permits for the development and operation of the Hanford Facility. Condition II.W. of the RCRA Permit specifies that the Permittees are to use their best efforts to obtain such permits. For the purposes of permit condition, `best efforts` means submittal of documentation and/or approval(s) in accordance with schedules specified in applicable regulations, or as determined through negotiations with the applicable regulatory agencies. This Status Report includes information on all existing and anticipated environmental permitting. Environmental permitting required by RCRA, the Hazardous and Solid Waste Amendments (HSWA) of 1984, and non-RCRA permitting (solid waste handling, Clean Air Act Amendments of 1990, Clean Water Act Amendments of 1987, Washington State waste discharge, and onsite sewage system) is addressed. Information on RCRA and non-RCRA is current as of July 31, 1998. For the purposes of RCRA and the State of Washington Hazardous Waste Management Act of 1976 [as administered through the Dangerous Waste Regulations, Washington Active Code (WAC) 173-303], the Hanford Facility is considered a single facility. As such, the Hanford Facility has been issued one US Environmental Protection Agency (EPA)/State Identification Number (WA7890008967). This EPA/State identification number encompasses over 60 treatment, storage, and/or disposal (TSD) units. The Washington State Department of Ecology (Ecology) has been delegated authority by the EPA to administer the RCRA, including mixed waste authority. The RCRA permitting approach for

  9. Annual Hanford Site environmental permitting status report

    International Nuclear Information System (INIS)

    Sonnichsen, J.C.

    1998-01-01

    The information contained and/or referenced in this Annual Hanford Site Environmental Permitting Status Report (Status Report) addresses the State Environmental Policy Act (SEPA) of 1971 and Condition II.W. of the Resource Conservation and Recovery Act (RCRA) of 1976 Permit, Dangerous Waste Portion (DW Portion). Condition II.W. of the RCRA Permit specifies the Permittees are responsible for all other applicable federal, state, and local permits for the development and operation of the Hanford Facility. Condition II.W. of the RCRA Permit specifies that the Permittees are to use their best efforts to obtain such permits. For the purposes of permit condition, 'best efforts' means submittal of documentation and/or approval(s) in accordance with schedules specified in applicable regulations, or as determined through negotiations with the applicable regulatory agencies. This Status Report includes information on all existing and anticipated environmental permitting. Environmental permitting required by RCRA, the Hazardous and Solid Waste Amendments (HSWA) of 1984, and non-RCRA permitting (solid waste handling, Clean Air Act Amendments of 1990, Clean Water Act Amendments of 1987, Washington State waste discharge, and onsite sewage system) is addressed. Information on RCRA and non-RCRA is current as of July 31, 1998. For the purposes of RCRA and the State of Washington Hazardous Waste Management Act of 1976 [as administered through the Dangerous Waste Regulations, Washington Active Code (WAC) 173-303], the Hanford Facility is considered a single facility. As such, the Hanford Facility has been issued one US Environmental Protection Agency (EPA)/State Identification Number (WA7890008967). This EPA/State identification number encompasses over 60 treatment, storage, and/or disposal (TSD) units. The Washington State Department of Ecology (Ecology) has been delegated authority by the EPA to administer the RCRA, including mixed waste authority. The RCRA permitting approach for

  10. Seasonal fire danger forecasts for the USA

    Science.gov (United States)

    J. Roads; F. Fujioka; S. Chen; R. Burgan

    2005-01-01

    The Scripps Experimental Climate Prediction Center has been making experimental, near-real-time, weekly to seasonal fire danger forecasts for the past 5 years. US fire danger forecasts and validations are based on standard indices from the National Fire Danger Rating System (DFDRS), which include the ignition component (IC), energy release component (ER), burning...

  11. Dangerous people or dangerous situations? Some further thoughts.

    Science.gov (United States)

    Prins, H

    1991-01-01

    The author enlarges upon and develops some observations upon the assessment of dangerousness which appeared in this journal a decade ago. In the present contribution, particular attention is paid to identifying the type of person at risk of committing further acts of serious personal harm to persons and or property and to the factors or circumstances that may be conducive to this. Finally, the author puts forward some views on why cues and clues may be missed and how these omissions might be overcome. 'Between the acting of a dreadful thing And the first motion, all the interim is Like a phantasma, or a hideous dream' Julius Caesar, Act II Scene 1.

  12. 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.

  13. 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

    International Nuclear Information System (INIS)

    2009-01-01

    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 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 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.

  14. Radiation effects on materials in the near-field of nuclear waste repository. 1998 annual progress report

    International Nuclear Information System (INIS)

    Ewing, R.C.; Wang, L.M.

    1998-01-01

    'Site restoration activities at DOE facilities and the permanent disposal of nuclear waste generated at DOE facilities involve working with and within various types and levels of radiation fields. Once the nuclear waste is incorporated into a final form, radioactive decay will decrease the radiation field over geologic time scales, but the alpha-decay dose for these solids will still reach values as high as 10 18 alpha-decay events/gm in periods as short as 1,000 years. This dose is well within the range for which important chemical (e.g., increased leach rate) and physical (e.g., volume expansion) changes may occur in crystalline ceramics. Release and sorption of long-lived actinides (e.g., 237 Np) can provide a radiation exposure to backfill materials, and changes in important properties (e.g., cation exchange capacity) may occur. The objective of this research program is to evaluate the long term radiation effects in the materials in the near-field of a nuclear waste repository with accelerated experiments in the laboratory using energetic particles (electrons, ions and neutrons). Experiments on the microstructural evolution during irradiation of two important groups of materials, sheet silicates (e.g., clays) and zeolites (analcime), have been conducted; and studies of radiation-induced changes in chemical properties (e.g. cation exchange capacity) are underway. As of the mid-2nd year of the 3-year project, experiments on the microstructural evolution during irradiation of two important group of materials, sheet silicates (mica) and zeolites (analcime), have been conducted; and studies of radiation-induced changes in chemical properties (e.g., cation exchange capacity) are underway.'

  15. 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)

    Daly, M.J.; Minton, K.W.; Wackett, L.P.

    1998-01-01

    '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.'

  16. 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)

    2010-01-01

    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.

  17. Waste Area Group 10, Operable Unit 10-08, Annual Monitoring Status Report for Fiscal Year 2009

    Energy Technology Data Exchange (ETDEWEB)

    Howard Forsythe

    2010-02-04

    This report documents the status of Fiscal Year 2009 groundwater monitoring performed in Waste Area Group 10 at the U.S. Department of Energy Idaho National Laboratory Site, as identified in the Groundwater Monitoring and Field Sampling Plan for Operable Unit 10-08. Twelve of the fourteen required wells were sampled, and all ten required intervals from the Westbay wells were sampled. Two wells were not sampled because they were in the process of being converted into multiple-sample-interval Westbay wells by the U.S. Geological Survey. Groundwater samples were analyzed for volatile organic compounds identified on the Contract Laboratory Program target analyte list as well as metals (filtered), anions, and radionuclides (i.e., I-129, tritium, Tc-99, gross alpha, gross beta, and Sr-90). No contaminant exceeded maximum contaminant levels in wells along the southern boundary of the Idaho National Laboratory Site or in guard wells. Iron was above its secondary maximum contaminant level of 300 ug/L in one well. The cause of the elevated iron concentration is uncertain. Lead was detected just below its action level. However, the zinc concentration was also elevated in these wells, and the source of the lead is probably galvanized riser pipe in the wells. Once the galvanized pipe is replaced, both lead and zinc concentrations should decline, as has been observed at other Waste Area Group 10 wells.

  18. Waste Area Group 10, Operable Unit 10-08, Annual Monitoring Status Report for Fiscal Year 2009

    International Nuclear Information System (INIS)

    Forsythe, Howard

    2010-01-01

    This report documents the status of Fiscal Year 2009 groundwater monitoring performed in Waste Area Group 10 at the U.S. Department of Energy Idaho National Laboratory Site, as identified in the Groundwater Monitoring and Field Sampling Plan for Operable Unit 10-08. Twelve of the fourteen required wells were sampled, and all ten required intervals from the Westbay wells were sampled. Two wells were not sampled because they were in the process of being converted into multiple-sample-interval Westbay wells by the U.S. Geological Survey. Groundwater samples were analyzed for volatile organic compounds identified on the Contract Laboratory Program target analyte list as well as metals (filtered), anions, and radionuclides (i.e., I-129, tritium, Tc-99, gross alpha, gross beta, and Sr-90). No contaminant exceeded maximum contaminant levels in wells along the southern boundary of the Idaho National Laboratory Site or in guard wells. Iron was above its secondary maximum contaminant level of 300 ug/L in one well. The cause of the elevated iron concentration is uncertain. Lead was detected just below its action level. However, the zinc concentration was also elevated in these wells, and the source of the lead is probably galvanized riser pipe in the wells. Once the galvanized pipe is replaced, both lead and zinc concentrations should decline, as has been observed at other Waste Area Group 10 wells.

  19. Corrosion behaviour of container materials for geological disposal of high-level waste. Joint annual progress report 1983

    International Nuclear Information System (INIS)

    1985-01-01

    Within the framework of the Community R and D programme on management and storage of radioactive waste (shared-cost action), a research activity is aiming at the assessment of corrosion behaviour of potential container materials for geological disposal of vitrified high-level wastes. In this report, the results obtained during the year 1983 are described. Research performed at the Studiecentrum voor Kernenergie/Centre d'Etudes de l'Energie Nucleaire (SCK/CEN) at Mol (B), concerns the corrosion behaviour in clay environments. The behaviour in salt is tested by the Kernforschungszentrum (KfK) at Karlsruhe (D). Corrosion behaviour in granitic environments is being examined by the Commissariat a l'Energie Atomique (CEA) at Fontenay-aux-Roses (F) and the Atomic Energy Research Establishment (AERE) at Harwell (UK); the first is concentrating on corrosion-resistant materials and the latter on corrosion-allowance materials. Finally, the Centre National de la Recherche Scientifique (CNRS) at Vitry (F) is examining the formation and behaviour of passive layers on the metal alloys in the various environments

  20. Annual report, spring 2015. Alternative chemical cleaning methods for high level waste tanks-corrosion test results

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-07-06

    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 when interacted with the chemical cleaning solution composed of 0.18 M nitric acid and 0.5 wt. % oxalic acid. This solution has been proposed as a dissolution solution that would be used to remove the remaining hard heel portion of the sludge in the waste tanks. This solution was combined with the HM and PUREX simulated sludge with dilution ratios that represent the bulk oxalic cleaning process (20:1 ratio, acid solution to simulant) and the cumulative volume associated with multiple acid strikes (50:1 ratio). The testing was conducted over 28 days at 50°C and deployed two methods to invest the corrosion conditions; passive weight loss coupon and an active electrochemical probe were used to collect data on the corrosion rate and material performance. In addition to investigating the chemical cleaning solutions, electrochemical corrosion testing was performed on acidic and basic solutions containing sodium permanganate at room temperature to explore the corrosion impacts if these solutions were to be implemented to retrieve remaining actinides that are currently in the sludge of the tank.

  1. Research and development on radioactive waste management and storage: Third annual progress report (1982) of the European Community programme 1980-1984

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    This book examines the European Community's program for nuclear waste management and storage. Topics considered include the characterization of conditioned low and medium activity waste forms, conditioning of high activity solid waste, treatment and conditioning processes for low and medium activity liquid waste, processing of alpha-contaminated waste, testing and evaluation of solidified high activity waste forms, immobilization and storage of gaseous waste, shallow land burial of solid low activity waste, storage and disposal in geological formations, and the performance and safety evaluation of radioactive waste disposed in geological formations

  2. Dangerousness and mental health policy.

    Science.gov (United States)

    Hewitt, J L

    2008-04-01

    Mental health policy development in the UK has become increasingly dominated by the assumed need to prevent violence and alleviate public concerns about the dangers of the mentally ill living in the community. Risk management has become the expected focus of contemporary mental health services, and responsibility has increasingly been devolved to individual service professionals when systems fail to prevent violence. This paper analyses the development of mental health legislation and its impact on services users and mental health professionals at the micro level of service delivery. Historical precedence, media influence and public opinion are explored, and the reification of risk is questioned in practical and ethical terms. The government's newest proposals for compulsory treatment in the community are discussed in terms of practical efficacy and therapeutic impact. Dangerousness is far from being an objectively observable phenomenon arising from clinical pathology, but is a formulation of what is partially knowable through social analysis and unknowable by virtue of its situation in individual psychic motivation. Risk assessment can therefore never be completely accurate, and the solution of a 'better safe than sorry' approach to mental health policy is ethically and pragmatically flawed.

  3. The Historically Black Colleges and Universities/Minority Institutions Environmental Technology and Waste Management Consortium annual report, 1990--1991

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-12-31

    The HBCU/MI Environmental Technology and Waste Management Consortium was established in January 1990, through a Memorandum of Understanding (MOU) among the member institutions. This group of research-oriented Historically Black Colleges and Universities and Minority Institutions (HBCU/MI) agreed to work together to initiate research, technology development and education programs to address the nation`s critical environmental problems. As a group the HBCU/MI Consortium is uniquely positioned to reach women and the minority populations of African Americans, Hispanics and American Indians. As part of their initial work, they developed the Research, Education, and Technology Transfer (RETT) Plan to actualize the Consortium`s guiding principles. In addition to developing a comprehensive research agenda, four major programs were begun to meet these goals. This report summarizes the 1990--1991 progress.

  4. Semi-annual report of the Department of Energy, Office of Environmental Restoration and Waste Management, Quality Assessment Program

    International Nuclear Information System (INIS)

    Sanderson, C.G.; Scarpitta, S.C.

    1992-01-01

    This report presents the results from the analysis of the 36th set of environmental quality assessment samples (QAP 36) that were received on or before January 2, 1992. This Quality Assessment Program (QAP) is designed to test the quality of the environmental measurements being reported to the Department of Energy by its contractors. Since 1976, real or synthetic environmental samples that have been prepared and thoroughly analyzed at the Environmental Measurements Laboratory (EML) have been distributed at first quarterly and then semi-annually to these contractors. Their results, which are returned to EML within 90 days, are complied with EML's results and are reported back to the participating contractors 30 days later. A summary of the reported results is available to the participants 3 days after the reporting deadline via a modem-telephone connection to the EML computer

  5. Semi-annual report of the Department of Energy, Office of Environmental Restoration and Waste Management, Quality Assessment Program

    International Nuclear Information System (INIS)

    Sanderson, C.G.; Klusek, C.S.

    1993-01-01

    This Quality Assessment Program (QAP) is designed to test the quality of the environmental measurements being reported to the Department of Energy by its contractors. Since 1976, real or synthetic environmental samples that have been prepared and thoroughly analyzed at the Environmental Measurements Laboratory (EML) have been distributed at first quarterly and then semi-annually to these contractors. Their results, which are returned to EML within 90 days, are compiled with EML's results and are reported back to the participating contractors 30 days later. A summary of the reported results is available to the participants 3 days after the reporting deadline via a modem-telephone connection to the EML computer. This report presents the results from the analysis of the 38th set of environmental quality assessment samples (QAP XXXVIII) that were received on or before June 2, 1993

  6. The dangers of sports journalism

    DEFF Research Database (Denmark)

    Sparre, Kirsten

    2017-01-01

    According to The Committee to Protect Journalists, 2 per cent of all journalists killed since 1992 worked on the sports beat. However, at present there is little understanding of the specific dangers faced by sports journalists. This chapter presents findings from exploratory research on 78 reports...... about violations of the media freedom or personal safety of sports journalists. Threats to media freedom include being banned from press conferences or events, the seizure of passports or denial of accreditation.The personal safety of sports journalists is compromised through verbal abuse, assaults......, attacks, personal and social media harrassment, detention, legal pressure, and killings. The key perpetrators identified in the sample were fans, athletes and coaches, owners and officials of sports clubs and national associations, international sports federations, and authorities in authoritarian regimes...

  7. [Purple drank: A dangerous cocktail].

    Science.gov (United States)

    Garcin, L; Le Roch, M; Agbessi, C-A; Lobut, J-B; Lecoeur, A; Benoist, G

    2016-11-01

    "Purple drank" is a dangerous hallucinogenic cocktail commonly used by teenagers, made popular by American rappers and social networks. It combines codeine-based cough syrup, antihistamines such as promethazine, and soda. Unknown by caregivers, it may be responsible for serious neuropsychological complications. We report the effects of this new risky behavior in three patients: a 14-year-old girl and her boyfriend, both found in an initial state of drowsiness, followed by hallucinations and anticholinergic toxidrome; and another teenager whose chronic use led to addiction with increasing doses. It is important to identify signs of such intoxication and to inform patients about the risks of respiratory depression, drowsiness, and delirium linked to acute medication misuse. Copyright © 2016 Elsevier Masson SAS. All rights reserved.

  8. Solid waste generation in reprocessing nuclear fuel

    International Nuclear Information System (INIS)

    North, E.D.

    1975-01-01

    Estimates are made of the solid wastes generated annually from a 750-ton/year plant (such as the NFS West Valley plant): high-level waste, hulls, intermediate level waste, failed equipment, HEPA filters, spent solvent, alpha contaminated combustible waste, and low specific activity waste. The annual volume of each category is plotted versus the activity level

  9. Ecological studies related to construction of the Defense Waste Processing Facility on the Savannah River Site. Annual report, FY 1993

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-11-01

    Construction of the Defense Waste Processing Facility (DWPF) on the Savannah River Site (SRS) began during FY-1984. The Savannah River Ecology Laboratory (SREL) has completed 15 years of ecological studies related to the construction of the DWPF complex. Prior to construction, the 600-acre site (S-Area) contained a Carolina bay and the headwaters of a stream. Through the long-term census taking of biota at the DWPF site and Rainbow Bay, SREL has been evaluating the impact of construction on the biota and the effectiveness of mitigation efforts. similarly, the effects of erosion from the DWPF site on the water quality of S-Area peripheral streams are being assessed. This research provides supporting data relevant to the National Environmental Policy Act (NEPA) of 1969, the Endangered Species Act of 1973, Executive orders 11988 (Floodplain Management) and 11990 (Protection of Wetlands), and United States Department of Energy (DOE) Guidelines for Compliance with Floodplain/Wetland Environmental Review Requirements (10 CFR 1022).

  10. The Control of Pollution (Special Waste) Regulations 1980 SI 1980 No. 1709

    International Nuclear Information System (INIS)

    1980-01-01

    These Regulations give effect to certain provisions of Community Legislation in Council Directive No. 78/319/EEC concerned with toxic and dangerous waste which will be special waste. Regulation 3 deals with radioactive waste which will be special waste if it has dangerous properties other than radioactivity. Precautions against radioactivity are dealt with under the Radioactive Substances Act 1960. (NEA) [fr

  11. Genetic engineering of a radiation-resistant bacterium for biodegradation of ixed wastes. 1998 annual progress report

    Energy Technology Data Exchange (ETDEWEB)

    Lidstrom, M.E.

    1998-06-01

    'Because of their tolerance to very high levels of ionizing radiation, members of the genus Deinococcus have received considerable attention over the past years. The type species of the genus, Deinococcus radiodurans, has been studied extensively in several labs. Although researchers are only beginning to understand the mechanisms by which this Gram-positive bacterium is able to repair massive DNA damage after radiation dosages as high as 5 Mrad, it has become evident that its recombination machinery has several unique characteristics (1--4). The aim of the present studies is to engineer D. radiodurans into a detoxifier for bioremediation of complex waste mixtures, containing heavy metals, halo-organics and radionuclides, making use of its ability to be biologically active in environments where they will be exposed to high levels of radiation. For that purpose, the authors aim to clone and express several broad spectrum oxygenases and heavy metal resistance determinants, and test survival and activities of these strains in artificial mixtures of contaminants, designed to simulate DOE mixed waste streams. This report summarizes work after 0.5 year of a 3-year project. The initial studies have focused on the development of an insertional expression system for D. radiodurans R1. This effort has involved two parts, namely: (1) promoter analysis, and (2) development of insertion systems. Several studies have shown that the expression signals used by D. radiodurans differ considerably from those found in other bacteria. Although D. radiodurans contains a typical eubacterial RNA polymerase core enzyme (based on TBLASTN searches on the genome sequence), Escherichia coli promoters are not recognized in D. radiodurans and vice versa (5). To expand the basic understanding of the requirements for transcription, and to optimize expression of (heterologous) genes, they will follow two strategies. First, a promoter-probe vector is being developed for the selection of

  12. Chemical decomposition of high-level nuclear waste storage/disposal glasses under irradiation. 1997 annual progress report

    International Nuclear Information System (INIS)

    Griscom, D.L.; Merzbacher, C.I.

    1997-01-01

    'The objective of this research is to use the sensitive technique of electron spin resonance (ESR) to look for evidence of radiation-induced chemical decomposition of vitreous forms contemplated for immobilization of plutonium and/or high-level nuclear wastes, to interpret this evidence in terms of existing knowledge of glass structure, and to recommend certain materials for further study by other techniques, particularly electron microscopy and measurements of gas evolution by high-vacuum mass spectroscopy. Previous ESR studies had demonstrated that an effect of y rays on a simple binary potassium silicate glass was to induce superoxide (O 2 - ) and ozonide (O 3 - ) as relatively stable product of long-term irradiation Accordingly, some of the first experiments performed as a part of the present effort involved repeating this work. A glass of composition 44 K 2 O: 56 SiO 2 was prepared from reagent grade K 2 CO3 and SiO 2 powders melted in a Pt crucible in air at 1,200 C for 1.5 hr. A sample irradiated to a dose of 1 MGy (1 MGy = 10 8 rad) indeed yielded the same ESR results as before. To test the notion that the complex oxygen ions detected may be harbingers of radiation-induced phase separation or bubble formation, a small-angle neutron scattering (SANS) experiment was performed. SANS is theoretically capable of detecting voids or bubbles as small as 10 305 in diameter. A preliminary experiment was carried out with the collaboration of Dr. John Barker (NIST). The SANS spectra for the irradiated and unirradiated samples were indistiguishable. A relatively high incoherent background (probably due to the presence of protons) may obscure scattering from small gas bubbles and therefore decrease the effective resolution of this technique. No further SANS experiments are planned at this time.'

  13. First annual report of the Radioactive Waste Management Advisory Committee to the Secretaries of State for the Environment, Scotland and Wales

    International Nuclear Information System (INIS)

    Wilkinson, D.

    1980-05-01

    The report is in sections, entitled: summary; introduction; current radioactive waste management practices; research into radioactive waste management; high level waste conditioning and disposal; A Nuclear Waste Disposal Corporation; and future work. Annexes cover the following: membership of Radioactive Waste Management Advisory Committee; terms of reference of other bodies; objectives of radioactive waste management; diagram of radiation exposure of the population of the United Kingdom; the categorisation of wastes; deep sea dumping; and geological research programme (text of the Committee's letter to the Secretary of State for the Environment). (U.K.)

  14. Dangerous Spaces, Dangerous Memories, Dangerous Emotions: Informal Education and Heteronormativity--A Manchester UK Youth Work Vignette

    Science.gov (United States)

    Batsleer, Janet

    2012-01-01

    This article makes a connection between youth work spaces, emotions and some elements of memory, exploring the construction of spaces dangerous for social justice in both meanings of the term "dangerous for". It investigates the contribution to social justice of lesbian and gay youth work and other non-heteronormative youth work in a…

  15. 1987 annual report on low-level radioactive waste management progress: Report to Congress in response to Public Law 99-240

    International Nuclear Information System (INIS)

    1988-08-01

    In response to Section 7(b) of the Low-Level Radioactive Waste Policy Amendments Act of 1985 (Public Law 99-240), this report summarizes the progress of states and low-level radioactive waste compacts in 1987 in establishing new low-level waste disposal facilities. It also reports the volume of low-level waste received for disposal in 1987 by commercially operated low-level waste disposal facilities

  16. 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

    Energy Technology Data Exchange (ETDEWEB)

    NSTec Environmental Management

    2010-03-15

    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 Wate 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&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.

  17. 1993 report on Hanford Site land disposal restrictions for mixed wastes

    Energy Technology Data Exchange (ETDEWEB)

    Black, D.

    1993-04-01

    Since the early 1940s, the contractors at the Hanford Site have been involved in the production and purification of nuclear defense materials. These production activities have resulted in the generation of large quantities of liquid and solid radioactive mixed waste (RMW). This waste is subject to regulation under authority of both the Resource Conservation and Recovery Act of 1976{sup 2}(RCRA) and Atomic Energy Act{sup 3}. This report covers mixed waste only. Hazardous waste that is not contaminated with radionuclides is not addressed in this report. The Washington State Department of Ecology, US Environmental Protection Agency, and US Department of Energy have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order{sup 1} (commonly referred to as the Tri-Party Agreement) to bring the Hanford Site operations into compliance with dangerous waste regulations. The Tri-Party Agreement required development of the original land disposal restrictions (LDR) plan and its annual updates to comply with LDR requirements for RMW. This report is the third update of the plan first issued in 1990. The Tri-Party Agreement requires, and the baseline plan and annual update reports provide, the information that follows: Waste characterization information; storage data; treatment information; waste reduction information; schedule; and progress.

  18. Annual report on the cost and the quality of the wastes disposal utility; Rapport annuel sur le prix et la qualite du service public d'elimination des dechets

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-07-01

    In the framework of the Barnier law in favor of the environment protection, each EPCI (public enterprise of inter communal cooperation) has to present an annual report on the cost and the quality of the domestic waste disposal utility. This guideline aims to help this document redaction. The first and the second parts present respectively the technical and the financial indicators, illustrated by examples and opinions. (A.L.B.)

  19. Community Violent Crime Rates and School Danger.

    Science.gov (United States)

    Bowen, Gary L.; Van Dorn, Richard A.

    2002-01-01

    This study investigated the association between community violent crime rates and middle school students' (N=857) perceptions of school danger. Findings indicate that community crime rates are associated with male middle school students' reports of school danger but not female students' reports. Discusses community- and school-based prevention…

  20. The Dangers of Educated Girls and Women

    Science.gov (United States)

    John, Vaughn M.

    2016-01-01

    Why do educated girls and women constitute a danger in some societies and for this face extreme danger in their educational endeavours? This article argues that historical and contemporary educational discrimination of girls and women is the hallmark of a violently patriarchal society, and this stubborn injustice is exacerbated under conditions of…

  1. [Dangerous sharks in tropical seas].

    Science.gov (United States)

    Maslin, J; Menard, G; Drouin, C; Pollet, L

    2000-01-01

    Sightseeing travel in tropical zones is a growing industry. The risks incurred by travelers depend on the destination, duration of stay, individual behavior, and type of leisure activity. Water sports expose visitors to encounters with dangerous marine animals. Shark attacks are rare but always serious occurrences. Divers should handle any shark, regardless of size, with due precaution. Prevention of shark attack depends on avoiding encounters by not attracting the attention of the shark and knowing the proper attitude to adopt in case an encounter should occur. Active and passive protection can be used, but each method has advantages and disadvantages depending on the situation. Rescue operations are difficult due to the gravity of injuries and their occurrence in a marine environment. This along with the nature of the aggressor explain that many attacks are immediately fatal. Wounds are often deep with involvement of bone, blood vessels, and nerves. A possible source of complication in survivors is infection, which can involve uncommon microorganisms associated with bacteria in sharks mouth or marine environment.

  2. Cleanups In My Community (CIMC) - Hazardous Waste Corrective Actions, National Layer

    Data.gov (United States)

    U.S. Environmental Protection Agency — This data layer provides access to Hazardous Waste Corrective Action sites as part of the CIMC web service. Hazardous waste is waste that is dangerous or potentially...

  3. Considerations for Net Zero Waste Installations: Treatment of Municipal Solid Waste

    Science.gov (United States)

    2015-09-01

    solid waste start with reducing the amount of waste generated, re-purposing waste , maximizing recycling ...Occupational Health Network and Information Exchange (DENIX). 2012. SWARWeb – Solid waste annual reporting. Solid Waste Recycling . Web page. Washington...USEPA, http://epa.gov/climatechange/wycd/ waste /SWMGHGreport.html#documentation ------------. 2011. Municipal Solid Waste Generation, Recycling

  4. Consuming Danger, Signifying Danger: Postnuclear Monuments, museums and Gardens

    Directory of Open Access Journals (Sweden)

    Mira Engler

    2004-06-01

    Full Text Available Marked by the scientific discovery of atomic energy, the nuclear age, which spans the twentieth century, has changed the nature of culture as well as the landscape. Despite recent talks on nuclear disarmament, the dread of nuclear arms production, proliferation, and waste storage is pervasive at both global and local levels, haunting governments, communities, and individuals alike. Nuclear sites concern not only scientists and politicians but also environmental designers. The need to evoke a cultural discourse, protect future generations, reveal or conceal radioactive burial sites, and recycle retired installations engenders the participation of artists and designers. How do designers intersect with these hellish places? Do we have a potent role in addressing this conundrum? In what follows, I confront the consumption and design of today’s most daunting places - the landscapes of nuclear and radioactive material production, processing, testing, and burial.

  5. 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.

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

    International Nuclear Information System (INIS)

    1991-09-01

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

  7. Radioactive Waste Management

    International Nuclear Information System (INIS)

    Paulikas, V.

    2006-01-01

    After the Law of the Republic of Lithuania was passed on Radioactive Waste Management on May 20, 1999, much more attention is being given to the disposal of this kind of waste in our country and especially at Ignalina NPP, the facility that generates most of it. The key principle of radioactive waste management is to manage it in such a manner that it would pose no danger to the public and the environment, and would not become an additional burden to future generations. This principle is followed in managing radioactive waste in Lithuania too. (author)

  8. Reducing Future International Chemical and Biological Dangers.

    Energy Technology Data Exchange (ETDEWEB)

    Haddal, Chad [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Bull, Diana L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hernandez, Patricia Marie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Foley, John T. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-12-01

    The International Biological and Chemical Threat Reduction Program at Sandia National Laboratories is developing a 15 - year technology road map in support the United States Government efforts to reduce international chemical and biological dangers . In 2017, the program leadership chartered an analysis team to explore dangers in the future international chemical and biological landscape through engagements with national security experts within and beyond Sandia to gain a multidisciplinary perspective on the future . This report offers a hi gh level landscape of future chemical and biological dangers based upon analysis of those engagements and provides support for further technology road map development.

  9. Dendritic Cells as Danger-Recognizing Biosensors

    Directory of Open Access Journals (Sweden)

    Seokmann Hong

    2009-08-01

    Full Text Available Dendritic cells (DCs are antigen presenting cells that are characterized by a potent capacity to initiate immune responses. DCs comprise several subsets with distinct phenotypes. After sensing any danger(s to the host via their innate immune receptors such as Toll-like receptors, DCs become mature and subsequently present antigens to CD4+ T cells. Since DCs possess the intrinsic capacity to polarize CD4+ helper cells, it is critical to understand the immunological roles of DCs for clinical applications. Here, we review the different DC subsets, their danger-sensing receptors and immunological functions. Furthermore, the cytokine reporter mouse model for studying DC activation is introduced.

  10. 40 CFR 262.56 - Annual reports.

    Science.gov (United States)

    2010-07-01

    ... used, the total amount of waste shipped and number of shipments pursuant to each notification; (5... Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID WASTES (CONTINUED) STANDARDS APPLICABLE TO GENERATORS OF HAZARDOUS WASTE Exports of Hazardous Waste § 262.56 Annual reports. (a) Primary...

  11. Rock & Roll : Waste seperation

    NARCIS (Netherlands)

    Beunder, L.; Rem, P.C.; Van Den Berg, R.

    2000-01-01

    Five hundred tonnes of glass, 1 million tonnes of plastic,14 million tonnes of building and demolition waste, 7 million tonnes of household waste, 3 million tonnes of packaging, 3.5 million tonnes of paper and board, and 300,000 old cars. All part of the annual harvest of waste materials in the

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

    International Nuclear Information System (INIS)

    Albert, R.

    1992-01-01

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

  13. Teens and Steroids: A Dangerous Combo

    Science.gov (United States)

    ... FDA Consumer Health Information Español The abuse of anabolic steroids can cause both temporary and permanent injury to ... the dangers of steroid use. Q: What are anabolic steroids and how many teens use them? A: They ...

  14. A fire danger rating system for Hawaii

    Science.gov (United States)

    Robert E. Burgan; Francis M. Fujioka; George H. Hirata

    1974-01-01

    Extremes in rainfall on the Hawaiian Islands make it difficult to judge forest fire danger conditions. The use of an automatic data collection and computer processing system helps to monitor the problem.

  15. Managing danger in oral historical fieldwork

    OpenAIRE

    Jessee, Erin

    2017-01-01

    This article offers an overview of the literature on anticipating and managing danger in qualitative fieldwork as it pertains to the practice of oral history in various settings. It offers an alternative perspective to the widespread assumption that oral history is an inherently positive endeavor that results in good relationships and positive outcomes. This article explores some of the circumstances through which danger can emerge in the course of oral historical fieldwork, both in relativel...

  16. How Dangerous are 'Dirty Bombs'?

    International Nuclear Information System (INIS)

    Franic, Z.

    2003-01-01

    dangerous, contrary to the 'threshold' model, according to which small or even moderate increases in background radiation may be safe. b) National and international radiation-safety organizations set differing safety levels. c) The bigger the conventional bomb that distributes the radioactive material, the better it will disperse. Thus, for a given amount of a particular isotope, a smaller explosion will expose a few people to a higher dose. A larger explosion will expose more people to a lower dose. d) A steady wind will carry the radiation in one direction. A changing wind will spread it more widely, increasing the affected area and population, but reducing the individual dose. e) The higher the radiation in the bomb, the better the chance it will be detected before detonation. Many relatively low cost practical steps can be taken to reduce risks from radiological weapons and minimize the effects if an attack should occur. The first step is ensuring that the radioactive materials are safe, secure and out of reach of possible terrorists. The coherent response plan should be prepared in advance. Ability to detect lost and stolen materials should be developed. Radiation detection devices should be installed on key points such as frontier passages, airports etc. Training of population and experts should be continuously implemented etc. (author)

  17. Annual report 2009

    International Nuclear Information System (INIS)

    Ammann, M.

    2010-04-01

    This annual report issued by the Swiss National Co-operative for the Disposal of Radioactive Waste reviews the co-operative's activities in the year 2009 and presents an overview of developments in legislation, planning procedures and funding plans. The selection of sites for the disposal of radioactive wastes in Switzerland is discussed, as is regional participation in the site selection procedures. Various technical questions are briefly addressed and work being carried out in the rock laboratories in the Swiss Alps and Jura mountains is discussed. International co-operation is reviewed and public relations issues are discussed. International collaboration in the area of radioactive waste disposal is discussed. Finally, organisational structures are described and the financial details for the year 2009 are presented. The report is completed with an appendix containing waste inventories, predicted waste volumes and listings of publications, addresses and a short glossary

  18. Investigations of natural groundwater hazards at the proposed Yucca Mountain high level nuclear waste repository. Part A: Geology at Yucca Mountain. Part B: Modeling of hydro-tectonic phenomena relevant to Yucca Mountain. Annual report - Nevada

    International Nuclear Information System (INIS)

    Szymanski, J.S.; Schluter, C.M.; Livingston, D.E.

    1993-05-01

    This document is an annual report describing investigations of natural groundwater hazards at the proposed Yucca Mountain, Nevada High-Level Nuclear Waste Repository.This document describes research studies of the origin of near surface calcite/silica deposits at Yucca Mountain. The origin of these deposits is controversial and the authors have extended and strengthened the basis of their arguments for epigenetic, metasomatic alteration of the tuffs at Yucca Mountain. This report includes stratigraphic, mineralogical, and geochronological information along with geochemical data to support the conclusions described by Livingston and Szymanski, and others. As part of their first annual report, they take this opportunity to clarify the technical basis of their concerns and summarize the critical geological field evidence and related information. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

  19. Investigations of natural groundwater hazards at the proposed Yucca Mountain high level nuclear waste repository. Part A: Geology at Yucca Mountain. Part B: Modeling of hydro-tectonic phenomena relevant to Yucca Mountain. Annual report - Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Szymanski, J.S.; Schluter, C.M.; Livingston, D.E. [and others

    1993-05-01

    This document is an annual report describing investigations of natural groundwater hazards at the proposed Yucca Mountain, Nevada High-Level Nuclear Waste Repository.This document describes research studies of the origin of near surface calcite/silica deposits at Yucca Mountain. The origin of these deposits is controversial and the authors have extended and strengthened the basis of their arguments for epigenetic, metasomatic alteration of the tuffs at Yucca Mountain. This report includes stratigraphic, mineralogical, and geochronological information along with geochemical data to support the conclusions described by Livingston and Szymanski, and others. As part of their first annual report, they take this opportunity to clarify the technical basis of their concerns and summarize the critical geological field evidence and related information. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  20. Emissions and waste in The Netherlands. Annual report 1997 and estimations for 1998; Emissies en afval in Nederland. Jaarrapport 1997 en ramingen 1998

    Energy Technology Data Exchange (ETDEWEB)

    Van Harmelen, A.K.; Draaijers, G.P.J.; Coenen, P.W.H.G.; Leneman, H.; Nagelhout, D.; Rood, G.A.; De Vries, D.J.; Zonneveld, E.A. [eds.

    1999-12-01

    An overview is given of the most important results of a survey of the emission of polluting materials into the air, water and soil in the Netherlands in 1997. Next to estimates of emissions for 1998, data on waste production and waste processing are presented. 51 refs.

  1. PTB annual report 1985

    International Nuclear Information System (INIS)

    1986-02-01

    The annual report presents general information on the institution's activities and the various departments, and reports on scientific work in the field of metrology and safety engineering. Brief scientific accounts refer to work in the domains of mechanics and acoustics, electricity, heat, optics, industrial metrology, atomic physics, technical and scientific services, collection and disposal of radioactive waste. (DG) [de

  2. Nuclear energy. Danger only in case of accidents?

    Energy Technology Data Exchange (ETDEWEB)

    Scherb, Hagen; Voigt, Kristina; Kusmierz, Ralf [Helmholtz Zentrum Muenchen, Neuherberg (Germany). Inst. of Computational Biology

    2014-07-01

    The environmental impacts of nuclear energy are highly underestimated. Nuclear weapons, atomic bomb tests, and nuclear accidents are considered a danger for the environment and a human cancer risk. However, childhood leukemia is consistently elevated near nuclear power plants and the Chernobyl accident entailed elevated human birth sex ratios across Europe. We studied the annual sex ratio near nuclear facilities in Germany, France, and Switzerland at the municipality level. We will demonstrate that low doses of ionizing radiation cause effects in human beings. This is shown by strongly consistent spatial-temporal shifts in the human sex ratio trends in the vicinity of nuclear facilities. In the chosen countries complete official data on over 70 million gender specific annual births at the municipality level are available. By Lambert-93 coordinates (France) and GK3 coordinates (Germany, Switzerland) we determined the minimum distances of municipalities from major nuclear facilities. Spatial-temporal trend analyses of the annual sex ratio depending on municipalities' minimum distances from nuclear facilities were carried out. Applying ordinary linear logistic regression (jump or broken-stick functions) and non-linear logistic regression (Rayleigh functions) we demonstrate that the sex ratio at birth shows the influence of mutagenic ionizing radiation on human health. As important environmental chemical contaminants are also mutagenic, the usefulness of the sex ratio at birth as a genetic health indicator can be inferred by analogy.

  3. Nuclear energy. Danger only in case of accidents?

    International Nuclear Information System (INIS)

    Scherb, Hagen; Voigt, Kristina; Kusmierz, Ralf

    2014-01-01

    The environmental impacts of nuclear energy are highly underestimated. Nuclear weapons, atomic bomb tests, and nuclear accidents are considered a danger for the environment and a human cancer risk. However, childhood leukemia is consistently elevated near nuclear power plants and the Chernobyl accident entailed elevated human birth sex ratios across Europe. We studied the annual sex ratio near nuclear facilities in Germany, France, and Switzerland at the municipality level. We will demonstrate that low doses of ionizing radiation cause effects in human beings. This is shown by strongly consistent spatial-temporal shifts in the human sex ratio trends in the vicinity of nuclear facilities. In the chosen countries complete official data on over 70 million gender specific annual births at the municipality level are available. By Lambert-93 coordinates (France) and GK3 coordinates (Germany, Switzerland) we determined the minimum distances of municipalities from major nuclear facilities. Spatial-temporal trend analyses of the annual sex ratio depending on municipalities' minimum distances from nuclear facilities were carried out. Applying ordinary linear logistic regression (jump or broken-stick functions) and non-linear logistic regression (Rayleigh functions) we demonstrate that the sex ratio at birth shows the influence of mutagenic ionizing radiation on human health. As important environmental chemical contaminants are also mutagenic, the usefulness of the sex ratio at birth as a genetic health indicator can be inferred by analogy.

  4. Radiation danger of exclusion zone objects

    International Nuclear Information System (INIS)

    Kholosha, V.I.; Proskura, N.I.; Ivanov, Yu.A.; Kazakov, S.V.; Arkhipov, A.N.

    2001-01-01

    The analysis of radiation danger of the Exclusion Zone objects was made. Here, the Zone is defined as the territory from which the population has been evacuated in 1986 owing to the Chernobyl accident and possible outflow of the contaminated substances out of the borders is potentially dangerous to the Ukraine. In the present work were analyzed such problems as sources of radiation danger in the Zone, ways of radionuclide migration out of the borders of the Zone in normal and emergency situations, the non-radiation (ecological) danger factors of the Zone objects, doses (individual and collective) from various sources and on separate ways of their formation, and the characteristics of radiation danger of the Zone objects. The conclusions are: (1) Radionuclide flows both from technologic and natural sources exceed those from Shelter objects, (2) Under emergency conditions, radionuclide flows and doze loading remain comparable with those from emergency sources, (3) To solve some management tasks in radiation situation, the basic works on the Shelter objects should be oriented to decrease probability of emergency occurrence and to reduce radiation influence (prevention wash-outs during high waters, fire-prevention measures in forests and strengthening of the control behind non-authorized use of objects in the Zone). (S. Ohno)

  5. Annual report, RCRA post-closure monitoring and inspections for the mercury landfill hazardous waste trenches for the period October 1995--October 1996

    International Nuclear Information System (INIS)

    Emer, D.F.; Smith, J.L.

    1997-01-01

    The Area 23 Hazardous Waste Trenches were closed in-place in September 1993. Post-closure monitoring of the Area 23 Hazardous Waste Trenches began in October 1993. The post-closure monitoring program is used to verify that the Area 23 Hazardous Waste Trench covers are performing properly, and that there is no water infiltrating into the waste trenches. The performance of the Area 23 Hazardous Waste Trenches is currently monitored using 30 neutron access tubes positioned on and along the margins of the covers. Soil moisture measurements are obtained in the soils directly beneath the trenches and compared to baseline conditions from the first year of post-closure operation. This report documents the post-closure activities between October 1995 and October 1996

  6. Annual report, RCRA post-closure monitoring and inspections for the mercury landfill hazardous waste trenches for the period October 1995--October 1996

    Energy Technology Data Exchange (ETDEWEB)

    Emer, D.F.; Smith, J.L.

    1997-01-01

    The Area 23 Hazardous Waste Trenches were closed in-place in September 1993. Post-closure monitoring of the Area 23 Hazardous Waste Trenches began in October 1993. The post-closure monitoring program is used to verify that the Area 23 Hazardous Waste Trench covers are performing properly, and that there is no water infiltrating into the waste trenches. The performance of the Area 23 Hazardous Waste Trenches is currently monitored using 30 neutron access tubes positioned on and along the margins of the covers. Soil moisture measurements are obtained in the soils directly beneath the trenches and compared to baseline conditions from the first year of post-closure operation. This report documents the post-closure activities between October 1995 and October 1996.

  7. NAGRA Annual report 2010

    International Nuclear Information System (INIS)

    2011-04-01

    This annual report presents the highlights of the activities carried out by the Swiss National Co-operative for the Disposal of Radioactive Wastes NAGRA during the year 2010. These include reviews by various commissions of the NAGRA co-operative's proposals for possible sites for nuclear waste repositories. Also, the enhancements made concerning information facilities for the general public at the co-operative's rock laboratories are mentioned. The operation of initial satellite-based precision measurement systems for movements in the earth's crust is noted. Organisational aspects and international co-operation are discussed. This annual report also looks at NAGRA's organisational structures and its commercial accounts. Appendices provide details on waste inventories and volumes and publications made in 2010. A selection of relevant internet addresses is also provided

  8. NAGRA Annual report 2010

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-04-15

    This annual report presents the highlights of the activities carried out by the Swiss National Co-operative for the Disposal of Radioactive Wastes NAGRA during the year 2010. These include reviews by various commissions of the NAGRA co-operative's proposals for possible sites for nuclear waste repositories. Also, the enhancements made concerning information facilities for the general public at the co-operative's rock laboratories are mentioned. The operation of initial satellite-based precision measurement systems for movements in the earth's crust is noted. Organisational aspects and international co-operation are discussed. This annual report also looks at NAGRA's organisational structures and its commercial accounts. Appendices provide details on waste inventories and volumes and publications made in 2010. A selection of relevant internet addresses is also provided

  9. The danger signal S100B integrates pathogen- and danger-sensing pathways to restrain inflammation.

    Directory of Open Access Journals (Sweden)

    Guglielmo Sorci

    2011-03-01

    Full Text Available Humans inhale hundreds of Aspergillus conidia without adverse consequences. Powerful protective mechanisms may ensure prompt control of the pathogen and inflammation. Here we reveal a previously unknown mechanism by which the danger molecule S100B integrates pathogen- and danger-sensing pathways to restrain inflammation. Upon forming complexes with TLR2 ligands, S100B inhibited TLR2 via RAGE, through a paracrine epithelial cells/neutrophil circuit that restrained pathogen-induced inflammation. However, upon binding to nucleic acids, S100B activated intracellular TLRs eventually resolve danger-induced inflammation via transcriptional inhibition of S100B. Thus, the spatiotemporal regulation of TLRs and RAGE by S100B provides evidence for an evolving braking circuit in infection whereby an endogenous danger protects against pathogen-induced inflammation and a pathogen-sensing mechanism resolves danger-induced inflammation.

  10. The mythology of waste disposal

    International Nuclear Information System (INIS)

    Beckhofer.

    1981-10-01

    This paper, while making a parallel between the mythology of the dangers of alcohol when the United States adopted a constitutional amendment prohibiting intoxicating liquor and public attitudes towards the dangers of nuclear waste burial, outlines the reason for these attitudes. Poor information of the public, from the start, on such dangers, the trauma of the atomic bomb and certain court decisions on nuclear activities which were in fact repealed by the Supreme Court. The paper also stresses the difficulty of dealing with this problem on a rational basis despite proven technical knowledge and successful experiments. (NEA) [fr

  11. Dangerous arachnids-Fake news or reality?

    Science.gov (United States)

    Hauke, Tobias J; Herzig, Volker

    2017-11-01

    The public perception of spiders and scorpions is skewed towards the potential harm they can inflict in humans, despite recent scientific evidence that arachnid venom components might be useful as bioinsecticides or even human therapeutics. Nevertheless, arachnids are becoming more popular as pets in Europe, America and Asia, raising the question for regulatory agencies in these regions as to whether they need to take measurements to protect their citizens. In order to decide upon the necessary regulatory steps, they first need to determine which arachnids are actually dangerous to humans. This review therefore provides an overview of the current literature on verified bites and stings from spiders and scorpions with the aim of assessing their potential danger for human health. As a guideline, we also provide a list of those arachnid genera that we consider as potentially dangerous, which includes 10 spider and 11 scorpion genera. The arachnid genera classified as dangerous comprise less than a quarter of all extant scorpion species and only 0.5% of all spiders species, with the actual number most likely being much lower than that, as not all species in those genera might turn out to pose an actual threat for humans. In conclusion, we found that only a small percentage of scorpions and a minute percentage of all spiders can be considered as potentially dangerous to humans. While in some countries of origin the high incidence of envenomations by dangerous arachnids can result in a serious problem to the health system, we assessed the risk that the same species pose when kept as pets under controlled maintenance conditions as significantly lower. Copyright © 2017 Elsevier Ltd. All rights reserved.

  12. Cartographies of danger mapping hazards in America

    CERN Document Server

    Monmonier, Mark

    1997-01-01

    No place is perfectly safe, but some places are more dangerous than others. Whether we live on a floodplain or in ""Tornado Alley,"" near a nuclear facility or in a neighborhood poorly lit at night, we all co-exist uneasily with natural and man-made hazards. As Mark Monmonier shows in this entertaining and immensely informative book, maps can tell us a lot about where we can anticipate certain hazards, but they can also be dangerously misleading. California, for example, takes earthquakes seriously, with a comprehensive program of seismic mapping, whereas Washington has been comparatively lax

  13. Waste-Heat-to-Power Market in the U.S., Heat is Power Annual Meeting (Presentation) – August 15, 2012

    Science.gov (United States)

    This presentation provides information about the EPA CHP Partnership, including an overview of the Partnership's tools and resources, and policy support. The presentation also describes the potential of Waste Heat to Power (WHP) systems.

  14. Keep away from danger: Dangerous objects in dynamic and static situations

    Directory of Open Access Journals (Sweden)

    Filomena eAnelli

    2013-07-01

    Full Text Available Behavioral and neuroscience studies have shown that objects observation evokes specific affordances (i.e., action possibilities and motor responses. Recent findings provide evidence that even dangerous objects can modulate the motor system evoking aversive affordances. This sounds intriguing since so far the majority of behavioral, brain imaging, and transcranial magnetic stimulation studies with painful and dangerous stimuli strictly concerned the domain of pain, excepted for evidence suggesting sensitivity to objects’ affordances when neutral objects are located in participants’ peripersonal space. This study investigates whether the observation of a neutral or dangerous object in a static or dynamic situation differently influences motor responses, and the time-course of the dangerous objects’ processing. In three experiments we manipulated: object dangerousness (neutral vs. dangerous; object category (artifact vs. natural; manual response typology (press vs. release a key; object presentation (Experiment 1: dynamic, Experiments 2 and 3: static; object movement direction (Experiment 1: away vs. toward the participant or size (Experiments 2 and 3: big vs. normal vs. small. The task required participants to decide whether the object was an artifact or a natural object, by pressing or releasing one key. Results showed a facilitation for neutral over dangerous objects in the static situation, probably due to an affordance effect. Instead, in the dynamic condition responses were modulated by the object movement direction, with a dynamic affordance effect of neutral objects and an escape-avoidance effect of dangerous objects (neutral objects were processed faster when they moved toward-approached the participant, whereas dangerous objects were processed faster when they moved away from the participant. Moreover, static stimuli influenced the manual response typology. These data indicate the emergence of dynamic affordance and escaping

  15. The wind energy in danger in France

    International Nuclear Information System (INIS)

    2005-03-01

    The law project of march 2005, concerning the energy policy in France is dangerous for the wind power development. The new regulation favor the big installations in order to protect the environment. In fact this decision will limit the wind turbines installations. (A.L.B.)

  16. Securing the dangerous UN convoys in Mali

    DEFF Research Database (Denmark)

    Haugegaard, Rikke; Albrecht, Peter; Ravnkilde, Signe Cold

    2017-01-01

    It has proven particularly challenging for the UN stabilization mission in Mali (MINUSMA) to transport fuel, food and water to military camps in Sector North on the frontline of the mission. Convoy escorts drain the UN mission of resources and is one of its most dangerous tasks, mainly carried out...

  17. (Neuro)predictions, Dangerousness, and Retributivism

    DEFF Research Database (Denmark)

    Petersen, Thomas Søbirk

    2014-01-01

    Through the criminal justice system so-called dangerous offenders are, besides the offence that they are being convicted of and sentenced to, also punished for acts that they have not done but that they are believe to be likely to commit in the future. The aim of this paper is to critically discu...

  18. Augustine on the Dangers of Friendship

    NARCIS (Netherlands)

    Nawar, Tamer

    2015-01-01

    The philosophers of antiquity had much to say about the place of friendship in the good life and its role in helping us live virtuously. Augustine is unusual in giving substantial attention to the dangers of friendship and its potential to serve as an obstacle (rather than an aid) to virtue. Despite

  19. Inherent Dangers in Orogenital Sex During Pregnancy

    African Journals Online (AJOL)

    Coitus and cunnilingus during pregnancy are generally safe; whereas orogenital sex involving vaginal air insufflations can be very dangerous, causing even the death of the women. We carried out a search of case reports and reviews concerning air embolism during pregnancy due to orogenital sex. Physicians ...

  20. The Dangers of Aestheticism in Schooling.

    Science.gov (United States)

    Meager, Ruby

    1981-01-01

    Prompted by Immanuel Kant's analysis of the nature and operations of the imagination in his "Critique of the Aesthetical Judgment," this article points out the danger of encouraging imagination-borne aesthetical judgments and explanatory hypotheses. Concludes that understanding requires submission to more stringent standards of objectivity and to…