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Sample records for radionuclide national emission

  1. National Emission Standards for Hazardous Air Pollutants—Calendar Year 2010 INL Report for Radionuclides (2011)

    Energy Technology Data Exchange (ETDEWEB)

    Mark Verdoorn; Tom Haney

    2011-06-01

    This report documents the calendar Year 2010 radionuclide air emissions and resulting effective dose equivalent to the maximally exposed individual member of the public from operations at the Department of Energy's Idaho National Laboratory Site. This report was prepared in accordance with the Code of Federal Regulations, Title 40, 'Protection of the Environment,' Part 61, 'National Emission Standards for Hazardous Air Pollutants,' Subpart H, 'National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.'

  2. Pacific Northwest National Laboratory Facility Radionuclide Emission Points and Sampling Systems

    International Nuclear Information System (INIS)

    Barfuss, Brad C.; Barnett, J. M.; Ballinger, Marcel Y.

    2009-01-01

    Battelle-Pacific Northwest Division operates numerous research and development laboratories in Richland, Washington, including those associated with the Pacific Northwest National Laboratory (PNNL) on the Department of Energy's Hanford Site that have the potential for radionuclide air emissions. The National Emission Standard for Hazardous Air Pollutants (NESHAP 40 CFR 61, Subparts H and I) requires an assessment of all effluent release points that have the potential for radionuclide emissions. Potential emissions are assessed annually. Sampling, monitoring, and other regulatory compliance requirements are designated based upon the potential-to-emit dose criteria found in the regulations. The purpose of this document is to describe the facility radionuclide air emission sampling program and provide current and historical facility emission point system performance, operation, and design information. A description of the buildings, exhaust points, control technologies, and sample extraction details is provided for each registered or deregistered facility emission point. Additionally, applicable stack sampler configuration drawings, figures, and photographs are provided

  3. Pacific Northwest National Laboratory Facility Radionuclide Emission Points and Sampling Systems

    Energy Technology Data Exchange (ETDEWEB)

    Barfuss, Brad C.; Barnett, J. Matthew; Ballinger, Marcel Y.

    2009-04-08

    Battelle—Pacific Northwest Division operates numerous research and development laboratories in Richland, Washington, including those associated with the Pacific Northwest National Laboratory (PNNL) on the Department of Energy’s Hanford Site that have the potential for radionuclide air emissions. The National Emission Standard for Hazardous Air Pollutants (NESHAP 40 CFR 61, Subparts H and I) requires an assessment of all effluent release points that have the potential for radionuclide emissions. Potential emissions are assessed annually. Sampling, monitoring, and other regulatory compliance requirements are designated based upon the potential-to-emit dose criteria found in the regulations. The purpose of this document is to describe the facility radionuclide air emission sampling program and provide current and historical facility emission point system performance, operation, and design information. A description of the buildings, exhaust points, control technologies, and sample extraction details is provided for each registered or deregistered facility emission point. Additionally, applicable stack sampler configuration drawings, figures, and photographs are provided.

  4. National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions, Calendar Year 2010

    International Nuclear Information System (INIS)

    2011-01-01

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office operates the Nevada National Security Site (NNSS, formerly the Nevada Test Site) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NNSS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NNSS activities has been monitored since the initiation of atmospheric testing. Limitation to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NNSS. After nuclear testing ended in 1992, NNSS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of tritium are also emitted to air at the NLVF, an NNSS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations (CFR) Part 61 Subpart H) (CFR, 2010a) limits the release of radioactivity from a U.S. Department of Energy (DOE) facility to that which would cause 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation unrelated to NNSS activities. Unrelated doses could come from naturally occurring radioactive elements, from sources such as medically or commercially used radionuclides, or from sources outside of the United States, such as those from the damaged Fukushima nuclear power plant in Japan. Because this report is intended to discuss radioactive air emissions during calendar year 2010, data on radionuclides in air from the 2011 Fukushima nuclear power plant releases are not presented but will be included in the report for calendar year 2011. The NNSS demonstrates compliance with the NESHAP

  5. National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions, Calendar Year 2011

    International Nuclear Information System (INIS)

    2012-01-01

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office operates the Nevada National Security Site (NNSS) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NNSS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NNSS activities has been monitored since the initiation of atmospheric testing. Limitation to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NNSS. After nuclear testing ended in 1992, NNSS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of legacy-related tritium are also emitted to air at the NLVF, an NNSS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations (CFR) Part 61 Subpart H) limits the release of radioactivity from a U.S. Department of Energy (DOE) facility to that which would cause 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation unrelated to NNSS activities. Unrelated doses could come from naturally occurring radioactive elements, from sources such as medically or commercially used radionuclides, or from sources outside of the United States, such as the damaged Fukushima nuclear power plant in Japan. Radionuclides from the Fukushima nuclear power plant were detected at the NNSS in March 2011 and are discussed further in Section III. The NNSS demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations. This method was approved by the EPA for use on the

  6. National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions Calendar Year 2009

    International Nuclear Information System (INIS)

    2010-01-01

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office operates the Nevada Test Site (NTS) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NTS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NTS activities has been monitored since the initiation of atmospheric testing. Limitation to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NTS. After nuclear testing ended in 1992, NTS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of tritium were also emitted to air at the NLVF, an NTS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations (CFR) Part 61 Subpart H) limits the release of radioactivity from a U.S. Department of Energy facility to 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation not related to NTS activities. Unrelated doses could come from naturally occurring radioactive elements or from sources such as medically or commercially used radionuclides. The NTS demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations. This method was approved by the U.S. Environmental Protection Agency for use on the NTS in 2001 and has been the sole method used since 2005. Six locations on the NTS have been established to act as critical receptor locations to demonstrate compliance with the NESHAP limit. These locations are actually pseudo-critical receptor stations, because no

  7. National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions Calendar Year 2012

    Energy Technology Data Exchange (ETDEWEB)

    Warren, R.

    2013-06-10

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) operates the Nevada National Security Site (NNSS) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NNSS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NNSS activities has been monitored since the initiation of atmospheric testing. Limitation to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NNSS. After nuclear testing ended in 1992, NNSS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of legacy-related tritium are also emitted to air at the NLVF, an NNSS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations [CFR] Part 61 Subpart H) (CFR 2010a) limits the release of radioactivity from a U.S. Department of Energy (DOE) facility to that which would cause 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation unrelated to NNSS activities. Unrelated doses could come from naturally occurring radioactive elements, from sources such as medically or commercially used radionuclides, or from sources outside of the United States, such as the damaged Fukushima nuclear power plant in Japan in 2011. NNSA/NFO demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations on the NNSS (U.S. Environmental Protection Agency [EPA] and DOE 1995). This method was approved by the EPA for use on the NNSS in 2001 (EPA 2001a) and has

  8. National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions Calendar Year 2013

    Energy Technology Data Exchange (ETDEWEB)

    Warren, R.

    2014-06-04

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) operates the Nevada National Security Site (NNSS) and North Las Vegas Facility (NLVF). From 1951 through 1992, the NNSS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NNSS activities has been monitored since the initiation of atmospheric testing. Limitations to underground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NNSS. After nuclear testing ended in 1992, NNSS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by wind) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of legacy-related tritium are also emitted to air at the NLVF, an NNSS support complex in North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations [CFR] Part 61 Subpart H) (CFR 2010a) limits the release of radioactivity from a U.S. Department of Energy (DOE) facility to that which would cause 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation unrelated to NNSS activities. Unrelated doses could come from naturally occurring radioactive elements, from sources such as medically or commercially used radionuclides, or from sources outside of the United States, such as the damaged Fukushima nuclear power plant in Japan in 2011. NNSA/NFO demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations on the NNSS (U.S. Environmental Protection Agency [EPA] and DOE 1995). This method was approved by the EPA for use on the NNSS in 2001 (EPA 2001a) and has

  9. Nevada Test Site National Emission Standards for Hazardous Air Pollutants - Radionuclide Emissions Calendar Year 2008

    International Nuclear Information System (INIS)

    Warren, Ronald; Grossman, Robert F.

    2009-01-01

    The Nevada Test Site (NTS) is operated by the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office. From 1951 through 1992, the NTS was the continental testing location for U.S. nuclear weapons. The release of radionuclides from NTS activities has been monitored since the initiation of atmospheric testing. Limitation to under-ground detonations after 1962 greatly reduced radiation exposure to the public surrounding the NTS. After nuclear testing ended in 1992, NTS radiation monitoring focused on detecting airborne radionuclides from historically contaminated soils. These radionuclides are derived from re-suspension of soil (primarily by winds) and emission of tritium-contaminated soil moisture through evapotranspiration. Low amounts of tritium were also emitted to air at the North Las Vegas Facility (NLVF), an NTS support complex in the city of North Las Vegas. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (Title 40 Code of Federal Regulations (CFR) Part 61 Subpart H) (CFR, 2008a) limits the release of radioactivity from a U.S. Department of Energy facility (e.g., the NTS) to 10 millirem per year (mrem/yr) effective dose equivalent to any member of the public. This limit does not include radiation not related to NTS activities. Unrelated doses could come from naturally occurring radioactive elements or from other man-made sources such as medical treatments. The NTS demonstrates compliance with the NESHAP limit by using environmental measurements of radionuclide air concentrations at critical receptor locations. This method was approved by the U.S. Environmental Protection Agency for use on the NTS in 2001 and has been the sole method used since 2005. Six locations on the NTS have been established to act as critical receptor locations to demonstrate compliance with the NESHAP limit. These locations are actually pseudo

  10. Pacific Northwest National Laboratory Site Radionuclide Air Emissions Report for Calendar Year 2012

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Sandra F.; Barnett, J. Matthew; Bisping, Lynn E.

    2013-06-06

    This report documents radionuclide air emissions that result in the highest effective dose equivalent (EDE) to a member of the public, referred to as the maximally exposed individual (MEI). The report has been prepared in compliance with the Code of Federal Regulations (CFR), Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (NESHAP), Subpart H, National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities and Washington Administrative Code (WAC) Chapter 246-247, Radiation Protection Air Emissions. The dose to the PNNL Site MEI due to routine major and minor point source emissions in 2012 from PNNL Site sources is 9E-06 mrem (9E-08 mSv) EDE. The dose from fugitive emissions (i.e., unmonitored sources) is 1E-7 mrem (1E-9 mSv) EDE. The dose from radon emissions is 2E-6 mrem (2E-08 mSv) EDE. No nonroutine emissions occurred in 2012. The total radiological dose for 2012 to the MEI from all PNNL Site radionuclide emissions, including fugitive emissions and radon, is 1E-5 mrem (1E-7 mSv) EDE, or 100,000 times smaller than the federal and state standard of 10 mrem/yr, to which the PNNL Site is in compliance.

  11. Pacific Northwest National Laboratory Campus Radionuclide Air Emissions Report for Calendar Year 2013

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Sandra F.; Barnett, J. Matthew; Bisping, Lynn E.

    2014-06-01

    This report documents radionuclide air emissions that result in the highest effective dose equivalent (EDE) to a member of the public, referred to as the maximally exposed individual (MEI). The report has been prepared in compliance with the Code of Federal Regulations (CFR), Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (NESHAP), Subpart H, National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities and Washington Administrative Code (WAC) Chapter 246-247, Radiation Protection Air Emissions. The dose to the PNNL Site MEI due to routine major and minor point source emissions in 2013 from PNNL Site sources is 2E-05 mrem (2E-07 mSv) EDE. The dose from fugitive emissions (i.e., unmonitored sources) is 2E-6 mrem (2E-8 mSv) EDE. The dose from radon emissions is 1E-11 mrem (1E-13 mSv) EDE. No nonroutine emissions occurred in 2013. The total radiological dose for 2013 to the MEI from all PNNL Site radionuclide emissions, including fugitive emissions and radon, is 2E-5 mrem (2E-7 mSv) EDE, or 100,000 times smaller than the federal and state standard of 10 mrem/yr, to which the PNNL Site is in compliance

  12. Pacific Northwest National Laboratory Campus Radionuclide Air Emissions Report for Calendar Year 2014

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Sandra F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Barnett, J. Matthew [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bisping, Lynn E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-06-01

    This report documents radionuclide air emissions that result in the 2014 highest effective dose equivalent (EDE) to an offsite member of the public, referred to as the maximally exposed individual (MEI). The report has been prepared in compliance with the Code of Federal Regulations (CFR), Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (NESHAP), Subpart H, “National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities” and Washington Administrative Code (WAC) Chapter 246-247, “Radiation Protection–Air Emissions.” The dose to the PNNL Campus MEI due to routine major and minor point source emissions in 2014 from PNNL Campus sources is 2E 05 mrem (2E-07 mSv) EDE. The dose from all fugitive sources is 3E-6 mrem (3E-8 mSv) EDE. The dose from radon emissions is 1E-6 mrem (1E-8 mSv) EDE. No nonroutine emissions occurred in 2014. The total radiological dose for 2014 to the MEI from all PNNL Campus radionuclide emissions, including fugitive emissions and radon, is 3E-5 mrem (3E-7 mSv) EDE, or more than 100,000 times smaller than the federal and state standard of 10 mrem/yr, to which the PNNL Campus is in compliance.

  13. Pacific Northwest National Laboratory Campus Radionuclide Air Emissions Report for Calendar Year 2015

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Sandra F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Barnett, J. Matthew [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Bisping, Lynn E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-06-01

    This report documents radionuclide air emissions that result in the 2015 highest effective dose equivalent (EDE) to an offsite member of the public, referred to as the maximally exposed individual (MEI). The report has been prepared in compliance with the Code of Federal Regulations (CFR), Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (NESHAP), Subpart H, “National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities” and Washington Administrative Code (WAC) Chapter 246-247, “Radiation Protection–Air Emissions.” The dose to the PNNL Campus MEI from routine major and minor point source emissions in 2015 from PNNL Campus sources is 2.6E-4 mrem (2.6E-6 mSv) EDE. The dose from all fugitive sources is 1.8E-6 mrem (1.8E-8 mSv) EDE. The dose from radon emissions is 4.4E-8 mrem (4.4E-10 mSv) EDE. No nonroutine emissions occurred in 2015. The total radiological dose to the MEI from all PNNL Campus radionuclide emissions, including fugitive emissions and radon, is 2.6E-4 mrem (2.6E-6 mSv) EDE, or more than 10,000 times less than the federal and state standard of 10 mrem/yr, with which the PNNL Campus is in compliance.

  14. National Emission Standards for Hazardous Air Pollutants—Calendar Year 2011 INL Report for Radionuclides (2012)

    Energy Technology Data Exchange (ETDEWEB)

    Mark Verdoorn; Tom Haney

    2012-06-01

    This report documents the calendar year 2011 radionuclide air emissions and resulting effective dose equivalent to the maximally exposed individual member of the public from operations at the Department of Energy's Idaho National Laboratory Site. This report was prepared in accordance with the Code of Federal Regulations, Title 40, 'Protection of the Environment,' Part 61, 'National Emission Standards for Hazardous Air Pollutants,' Subpart H, 'National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.' The effective dose equivalent to the maximally exposed individual member of the public was 4.58E-02 mrem per year, 0.46 percent of the 10 mrem standard.

  15. National Emission Standards for Hazardous Air Pollutants. Calendar Year 2013 INL Report for Radionuclides [2014

    Energy Technology Data Exchange (ETDEWEB)

    Verdoorn, Mark; Haney, Tom

    2014-06-01

    This report documents the calendar year 2013 radionuclide air emissions and resulting effective dose equivalent to the maximally exposed individual member of the public from operations at the Department of Energy’s Idaho National Laboratory Site. This report was prepared in accordance with the Code of Federal Regulations, Title 40, ''Protection of the Environment,'' Part 61, ''National Emission Standards for Hazardous Air Pollutants,'' Subpart H, ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.'' The effective dose equivalent to the maximally exposed individual member of the public was 3.02 E-02 mrem per year, 0.30 percent of the 10 mrem standard.

  16. National Emission Standards for Hazardous Air Pollutants. Calendar Year 2012 INL Report for Radionuclides (2013)

    Energy Technology Data Exchange (ETDEWEB)

    Verdoorn, Mark; Haney, Tom

    2013-06-01

    This report documents the calendar year 2011 radionuclide air emissions and resulting effective dose equivalent to the maximally exposed individual member of the public from operations at the Department of Energy’s Idaho National Laboratory Site. This report was prepared in accordance with the Code of Federal Regulations, Title 40, ''Protection of the Environment,'' Part 61, ''National Emission Standards for Hazardous Air Pollutants,'' Subpart H, ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.'' The effective dose equivalent to the maximally exposed individual member of the public was 4.58E-02 mrem per year, 0.46 percent of the 10 mrem standard.

  17. Pacific Northwest National Laboratory Facility Radionuclide Emissions Units and Sampling Systems

    Energy Technology Data Exchange (ETDEWEB)

    Barnett, J. Matthew; Brown, Jason H.; Walker, Brian A.

    2012-04-01

    Battelle–Pacific Northwest Division operates numerous research and development (R&D) laboratories in Richland, WA, including those associated with Pacific Northwest National Laboratory (PNNL) on the U.S. Department of Energy (DOE)’s Hanford Site and PNNL Site that have the potential for radionuclide air emissions. The National Emission Standard for Hazardous Air Pollutants (NESHAP 40 CFR 61, Subparts H and I) requires an assessment of all emission units that have the potential for radionuclide air emissions. Potential emissions are assessed annually by PNNL staff members. Sampling, monitoring, and other regulatory compliance requirements are designated based upon the potential-to-emit dose criteria found in the regulations. The purpose of this document is to describe the facility radionuclide air emission sampling program and provide current and historical facility emission unit system performance, operation, and design information. For sampled systems, a description of the buildings, exhaust units, control technologies, and sample extraction details is provided for each registered emission unit. Additionally, applicable stack sampler configuration drawings, figures, and photographs are provided. Deregistered emission unit details are provided as necessary for up to 5 years post closure.

  18. 77 FR 16547 - Radionuclide National Emission Standards for Hazardous Air Pollutants; Notice of Construction...

    Science.gov (United States)

    2012-03-21

    ... Construction Approval to Energy Fuels for Tailings Cell A and the Phase I Evaporation Ponds at the proposed Pi[ntilde]on Ridge Uranium Mill. Tailings Cell A and the Phase I Evaporation Ponds are regulated under 40... ENVIRONMENTAL PROTECTION AGENCY [FRL-9649-9] Radionuclide National Emission Standards for...

  19. Pacific Northwest National Laboratory Site Radionuclide Air Emissions Report for Calendar Year 2011

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Sandra F.; Barnett, J. Matthew; Bisping, Lynn E.

    2012-06-12

    This report documents radionuclide air emissions that result in the highest effective dose equivalent (EDE) to a member of the public, referred to as the maximally exposed individual (MEI). The report has been prepared in compliance with the Code of Federal Regulations (CFR), Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (NESHAP), Subpart H, National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities and Washington Administrative Code (WAC) Chapter 246-247, Radiation ProtectionAir Emissions. The EDE to the PNNL Site MEI due to routine emissions in 2011 from PNNL Site sources was 1.7E 05 mrem (1.7E-7 mSv) EDE. No nonroutine emissions occurred in 2011. The total radiological dose for 2011 to the MEI from all PNNL Site radionuclide emissions was more than 10,000 times smaller than the federal and state standard of 10 mrem/yr, to which the PNNL Site is in compliance.

  20. 1995 Idaho National Engineering Laboratory (INEL) National Emission Standards for Hazardous Air Pollutants (NESHAPs): Radionuclides. Annual report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    Under Section 61.94 of 40 CFR 61, Subpart H (National Emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities), each DOE facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at INEL for CY 1995. For that year, airborne radionuclide emissions from INEL operations were calculated to result in a maximum individual dose to a member of the public of 1.80E-02 mrem (1.80E-07 Sievert), well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year).

  1. 1995 Idaho National Engineering Laboratory (INEL) National Emission Standards for Hazardous Air Pollutants (NESHAPs): Radionuclides. Annual report

    International Nuclear Information System (INIS)

    1996-06-01

    Under Section 61.94 of 40 CFR 61, Subpart H (National Emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities), each DOE facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at INEL for CY 1995. For that year, airborne radionuclide emissions from INEL operations were calculated to result in a maximum individual dose to a member of the public of 1.80E-02 mrem (1.80E-07 Sievert), well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year)

  2. Savannah River Site radionuclide air emissions annual report for national emission standards for hazardous air pollutants

    International Nuclear Information System (INIS)

    Sullivan, I.K.

    1993-01-01

    The radiological air emission sources at the SRS have been divided into three categories, Point, Grouped and Non-Point, for this report. Point sources, analyzed individually, are listed with a listing of the control devices, and the control device efficiency. The sources listed have been grouped together either for security reasons or where individual samples are composited for analytical purposes. For grouped sources the listed control devices may not be on all sources within a group. Point sources that did not have continuous effluent monitoring/sampling in 1993 are noted. The emissions from these sources was determined from Health Protection smear data, facility radionuclide content or other calculational methods, including process knowledge, utilizing existing analytical data. This report also contain sections on facility descriptions, dose assessment, and supplemental information

  3. 1996 Idaho National Engineering and Environmental Laboratory (INEEL) National Emissions Standards for Hazardous Air Pollutants (NESHAPs) -- Radionuclides. Annual report

    International Nuclear Information System (INIS)

    1997-06-01

    Under Section 61.94 of Title 40, Code of Federal Regulations (CFR), Part 61, Subpart H, ''National Emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities,'' each Department of Energy (DOE) facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at the Idaho National Engineering and Environmental Laboratory (INEEL) for calendar year (CY) 1996. The Idaho Operations Office of the DOE is the primary contact concerning compliance with the National Emission Standards for Hazardous Air Pollutants (NESHAPs) at the INEEL. For calendar year 1996, airborne radionuclide emissions from the INEEL operations were calculated to result in a maximum individual dose to a member of the public of 3.14E-02 mrem (3.14E-07 Sievert). This effective dose equivalent (EDE) is well below the 40 CFR 61, Subpart H, regulatory standard of 10 mrem per year (1.0E-04 Sievert per year)

  4. 1997 Idaho National Engineering and Environmental Laboratory (INEEL) National Emission Standard for Hazardous Air Pollutants - Radionuclides. Annual report

    International Nuclear Information System (INIS)

    1998-06-01

    Under Section 61.94 of Title 40, Code of Federal Regulations (CFR), Part 61, Subpart H, National Emission Standards for Emissions of Radionuclides Other Than Radon From Department of Energy Facilities, each Department of Energy (DOE) facility must submit an annual report documenting compliance. This report addresses the Section 61.94 reporting requirements for operations at the Idaho National Engineering and Environmental Laboratory (INEEL) for calendar year (CY) 1997. Section 1 of this report provides an overview of the INEEL facilities and a brief description of the radioactive materials and processes at the facilities. Section 2 identifies radioactive air effluent release points and diffuse sources at the INEEL and actual releases during 1997. Section 2 also describes the effluent control systems for each potential release point. Section 3 provides the methodology and EDE calculations for 1997 INEEL radioactive emissions

  5. 2008 LANL radionuclide air emissions report

    Energy Technology Data Exchange (ETDEWEB)

    Fuehne, David P.

    2009-06-01

    The emissions of radionuclides from Department of Energy Facilities such as Los Alamos National Laboratory (LANL) are regulated by the Amendments to the Clean Air Act of 1990, National Emissions Standards for Hazardous Air Pollutants (40 CFR 61 Subpart H). These regulations established an annual dose limit of 10 mrem to the maximally exposed member of the public attributable to emissions of radionuclides. This document describes the emissions of radionuclides from LANL and the dose calculations resulting from these emissions for calendar year 2008. This report meets the reporting requirements established in the regulations.

  6. 2010 LANL radionuclide air emissions report /

    Energy Technology Data Exchange (ETDEWEB)

    Fuehne, David P.

    2011-06-01

    The emissions of radionuclides from Department of Energy Facilities such as Los Alamos National Laboratory (LANL) are regulated by the Amendments to the Clean Air Act of 1990, National Emissions Standards for Hazardous Air Pollutants (40 CFR 61 Subpart H). These regulations established an annual dose limit of 10 mrem to the maximally exposed member of the public attributable to emissions of radionuclides. This document describes the emissions of radionuclides from LANL and the dose calculations resulting from these emissions for calendar year 2010. This report meets the reporting requirements established in the regulations.

  7. Hanford Site radionuclide national emission standards for hazardous air pollutants unregistered stack (power exhaust) source assessment

    International Nuclear Information System (INIS)

    Davis, W.E.

    1994-01-01

    On February 3, 1993, the US Department of Energy, Richland Operations Office received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency, Region 10. The Compliance Order requires the Richland Operations Office to evaluate all radionuclide emission points at the Hanford Site to determine which are subject to continuous emission measurement requirements in 40 Code of Federal Regulations (CFR) 61, Subpart H, and to continuously measure radionuclide emissions in accordance with 40 CFR 61.93. This evaluation provides an assessment of the 39 unregistered stacks, under Westinghouse Hanford Company's management, and their potential radionuclide emissions, i.e., emissions with no control devices in place. The evaluation also determined if the effective dose equivalent from any of these stack emissions exceeded 0.1 mrem/yr, which will require the stack to have continuous monitoring. The result of this assessment identified three stacks, 107-N, 296-P-26 and 296-P-28, as having potential emissions that would cause an effective dose equivalent greater than 0.1 mrem/yr. These stacks, as noted by 40 CFR 61.93, would require continuous monitoring

  8. Hanford Site radionuclide national emission standards for hazardous air pollutants unregistered stack (power exhaust) source assessment

    Energy Technology Data Exchange (ETDEWEB)

    Davis, W.E.

    1994-08-04

    On February 3, 1993, the US Department of Energy, Richland Operations Office received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency, Region 10. The Compliance Order requires the Richland Operations Office to evaluate all radionuclide emission points at the Hanford Site to determine which are subject to continuous emission measurement requirements in 40 Code of Federal Regulations (CFR) 61, Subpart H, and to continuously measure radionuclide emissions in accordance with 40 CFR 61.93. This evaluation provides an assessment of the 39 unregistered stacks, under Westinghouse Hanford Company`s management, and their potential radionuclide emissions, i.e., emissions with no control devices in place. The evaluation also determined if the effective dose equivalent from any of these stack emissions exceeded 0.1 mrem/yr, which will require the stack to have continuous monitoring. The result of this assessment identified three stacks, 107-N, 296-P-26 and 296-P-28, as having potential emissions that would cause an effective dose equivalent greater than 0.1 mrem/yr. These stacks, as noted by 40 CFR 61.93, would require continuous monitoring.

  9. NATIONAL EMISSION STANDARDS FOR HAZARDOUS AIR POLLUTANTS (NESHAP) SUBPART H RADIONUCLIDES POTENTIAL TO EMIT CALCULATIONS

    Energy Technology Data Exchange (ETDEWEB)

    EARLEY JN

    2008-07-23

    This document provides an update of the status of stacks on the Hanford Site and the potential radionuclide emissions, i.e., emissions that could occur with no control devices in place. This review shows the calculations that determined whether the total effective dose equivalent (TEDE) received by the maximum public receptor as a result of potential emissions from any one of these stacks would exceed 0.1 millirem/year. Such stacks require continuous monitoring of the effluent, or other monitoring, to meet the requirements of Washington Administrative code (WAC) 246-247-035(1)(a)(ii) and WAC 246-247-075(1), -(2), and -(6). This revised update reviews the potential-to-emit (PTE) calculations of 31 stacks for Fluor Hanford, Inc. Of those 31 stacks, 11 have the potential to cause a TEDE greater than 0.1 mrem/year.

  10. NATIONAL EMISSION STANDARDS FOR HAZARDOUS AIR POLLUTANTS (NESHAP) SUBPART H; RADIONUCLIDES POTENTIAL-TO-EMIT CALCULATIONS

    International Nuclear Information System (INIS)

    EARLEY JN

    2008-01-01

    This document provides an update of the status of stacks on the Hanford Site and the potential radionuclide emissions, i.e., emissions that could occur with no control devices in place. This review shows the calculations that determined whether the total effective dose equivalent (TEDE) received by the maximum public receptor as a result of potential emissions from any one of these stacks would exceed 0.1 millirem/year. Such stacks require continuous monitoring of the effluent, or other monitoring, to meet the requirements of Washington Administrative code (WAC) 246-247-035(1)(a)(ii) and WAC 246-247-075(1), -(2), and -(6). This revised update reviews the potential-to-emit (PTE) calculations of 31 stacks for Fluor Hanford, Inc. Of those 31 stacks, 11 have the potential to cause a TEDE greater than 0.1 mrem/year

  11. Hanford Site radionuclide national emission standards for hazardous air pollutants registered stack source assessment

    Energy Technology Data Exchange (ETDEWEB)

    Davis, W.E.; Barnett, J.M.

    1994-07-01

    On February 3, 1993, the US Department of Energy, Richland Operations Office received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency,, Region 10. The Compliance Order requires the Richland Operations Office to evaluate all radionuclide emission points at the Hanford Site . The evaluation also determined if the effective dose equivalent from any of these stack emissions exceeded 0.1 mrem/yr, which will require the stack to have continuous monitoring. The result of this assessment identified a total of 16 stacks as having potential emissions that,would cause an effective dose equivalent greater than 0.1 mrem/yr.

  12. Hanford Site radionuclide national emission standards for hazardous air pollutants registered stack source assessment

    International Nuclear Information System (INIS)

    Davis, W.E.; Barnett, J.M.

    1994-01-01

    On February 3, 1993, the US Department of Energy, Richland Operations Office received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency,, Region 10. The Compliance Order requires the Richland Operations Office to evaluate all radionuclide emission points at the Hanford Site . The evaluation also determined if the effective dose equivalent from any of these stack emissions exceeded 0.1 mrem/yr, which will require the stack to have continuous monitoring. The result of this assessment identified a total of 16 stacks as having potential emissions that,would cause an effective dose equivalent greater than 0.1 mrem/yr

  13. 2014 LANL Radionuclide Air Emissions Report

    Energy Technology Data Exchange (ETDEWEB)

    Fuehne, David Patrick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-07-21

    This report describes the emissions of airborne radionuclides from operations at Los Alamos National Laboratory (LANL) for calendar year 2014, and the resulting off-site dose from these emissions. This document fulfills the requirements established by the National Emissions Standards for Hazardous Air Pollutants in 40 CFR 61, Subpart H – Emissions of Radionuclides other than Radon from Department of Energy Facilities, commonly referred to as the Radionuclide NESHAP or Rad-NESHAP. Compliance with this regulation and preparation of this document is the responsibility of LANL’s RadNESHAP compliance program, which is part of the Environmental Protection Division. The information in this report is required under the Clean Air Act and is being submitted to the U.S. Environmental Protection Agency (EPA) Region 6.

  14. Environmental Management Department Quality Assurance Project Plan for Radionuclide Emission Measurements Project for compliance with National Emission Standards for Hazardous Air Pollutants (NESHAP)

    Energy Technology Data Exchange (ETDEWEB)

    Poole, D A

    1992-06-01

    This Quality Assurance Project Plan (QAPP) satisfies the quality assurance (QA) requirements in 40 CFR Part 61, Method 114, for ensuring that the radionuclide air emission measurements from the Y-12 Plant are representative; of a known precision and accuracy; and include administrative controls to ensure prompt response when emission measurements indicate an increase over normal radionuclide emissions. The QAPP ensures the quality of the Y-12 Plant radionuclide emission measurements data from the continuous samplers, breakthrough monitors, and minor radionuclide release points. The plan specifies the procedures for the management of the activities affecting the quality of the data for the Y-12 Plant Environmental Management Department (EMD) within the Health, Safety, Environment, and Accountability Division (HSEA).

  15. Environmental Management Department Quality Assurance Project Plan for Radionuclide Emission Measurements Project for compliance with National Emission Standards for Hazardous Air Pollutants (NESHAP)

    International Nuclear Information System (INIS)

    Poole, D.A.

    1992-06-01

    This Quality Assurance Project Plan (QAPP) satisfies the quality assurance (QA) requirements in 40 CFR Part 61, Method 114, for ensuring that the radionuclide air emission measurements from the Y-12 Plant are representative; of a known precision and accuracy; and include administrative controls to ensure prompt response when emission measurements indicate an increase over normal radionuclide emissions. The QAPP ensures the quality of the Y-12 Plant radionuclide emission measurements data from the continuous samplers, breakthrough monitors, and minor radionuclide release points. The plan specifies the procedures for the management of the activities affecting the quality of the data for the Y-12 Plant Environmental Management Department (EMD) within the Health, Safety, Environment, and Accountability Division (HSEA)

  16. 2006 LANL Radionuclide Air Emissions Report

    Energy Technology Data Exchange (ETDEWEB)

    David P. Fuehne

    2007-06-30

    This report describes the impacts from emissions of radionuclides at Los Alamos National Laboratory (LANL) for calendar year 2006. This report fulfills the requirements established by the Radionuclide National Emissions Standards for Hazardous Air Pollutants (Rad-NESHAP). This report is prepared by LANL's Rad-NESHAP compliance team, part of the Environmental Protection Division. The information in this report is required under the Clean Air Act and is being reported to the U.S. Environmental Protection Agency (EPA). The highest effective dose equivalent (EDE) to an off-site member of the public was calculated using procedures specified by the EPA and described in this report. LANL's EDE was 0.47 mrem for 2006. The annual limit established by the EPA is 10 mrem per year. During calendar year 2006, LANL continuously monitored radionuclide emissions at 28 release points, or stacks. The Laboratory estimates emissions from an additional 58 release points using radionuclide usage source terms. Also, LANL uses a network of air samplers around the Laboratory perimeter to monitor ambient airborne levels of radionuclides. To provide data for dispersion modeling and dose assessment, LANL maintains and operates meteorological monitoring systems. From these measurement systems, a comprehensive evaluation is conducted to calculate the EDE for the Laboratory. The EDE is evaluated as any member of the public at any off-site location where there is a residence, school, business, or office. In 2006, this location was the Los Alamos Airport Terminal. The majority of this dose is due to ambient air sampling of plutonium emitted from 2006 clean-up activities at an environmental restoration site (73-002-99; ash pile). Doses reported to the EPA for the past 10 years are shown in Table E1.

  17. Radionuclide air emissions report for the Hanford Site

    International Nuclear Information System (INIS)

    Rokkan, D.J.; Diediker, L.P.; Manley, C.L.

    1992-06-01

    This report documents the radionuclide air emissions from the Hanford Site in 1991 and the resulting effective dose equivalent to any member of the public. The report is submitted in compliance with reporting requirements in the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, ''National Emissions Standards for Hazardous Air Pollutants.''

  18. U.S. DOE 2004 LANL Radionuclide Air Emissions

    International Nuclear Information System (INIS)

    K.W. Jacobson

    2005-01-01

    Amendments to the Clean Air Act, which added radionuclides to the National Emissions Standards for Hazardous Air Pollutants (NESHAP), went into effect in 1990. Specifically, a subpart (H) of 40 CFR 61 established an annual limit on the impact to the public attributable to emissions of radionuclides from U.S. Department of Energy facilities, such as the Los Alamos National Laboratory (LANL). As part of the new NESHAP regulations, LANL must submit an annual report to the U.S. Environmental Protection Agency headquarters and the regional office in Dallas by June 30. This report includes results of monitoring at LANL and the dose calculations for the calendar year 2004

  19. Radionuclide Air Emissions Report for 2012

    Energy Technology Data Exchange (ETDEWEB)

    Wahl, Linnea [Ernest Orlando Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States)

    2013-05-01

    Berkeley Lab operates facilities where radionuclides are produced, handled, store d, and potentially emitted . These facilities are subject to the EPA radioactive air emission regulations in 40 CFR 61, Subpart H (EPA 1989a). Radionuclides may be emitted from stacks or vents on buildings where radionuclide production or use is authorized or they may be emitted as diffuse sources. In 2012, all Berkeley Lab sources were minor sources of radionuclides (sources resulting in a potential dose of less than 0.1 mrem/yr [0.001 mSv/yr]) . These minor sources include d about 140 stack sources and no diffuse sources . T here were no unplanned airborne radionuclide emissions from Berkeley Lab operations . Emissions from minor sources were measured by sampling or monitoring or were calculated based on quantities used, received for use, or produced during the year. Using measured and calculated emissions, and building- specific and common parameters, Laboratory personnel applied the EPA -approved computer code s, CAP88-PC and COMPLY , to calculate doses to the maximally exposed individual (MEI) at any offsite point where there is a residence, school, business, or office. Because radionuclides are used at three noncontiguous locations (the main site, Berkeley West Bio center, and Joint BioEnergy Institute), three different MEIs were identified.

  20. Radionuclide air emissions report for the Hanford Site, calendar year 1992

    International Nuclear Information System (INIS)

    Diediker, L.P.; Johnson, A.R.; Rhoads, K.; Klages, D.L.; Soldat, J.K.; Rokkan, D.J.

    1993-06-01

    This report documents radionuclide air emissions from the Hanford Site in 1992 and the resulting effective dose equivalent to an member of the public. The report has been prepared and will be submitted in accordance with reporting requirements in the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, ''National Emissions Standards for Hazardous Air Pollutants,'' Subpart H, ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.''

  1. Radionuclide Air Emission Report for 2009

    Energy Technology Data Exchange (ETDEWEB)

    Wahl, Linnea

    2010-06-01

    Berkeley Lab operates facilities where radionuclides are handled and stored. These facilities are subject to the EPA radioactive air emission regulations in 40CFR61, Subpart H (EPA 1989). Radionuclides may be emitted from stacks or vents on buildings where radionuclide production or use is authorized or they may be emitted as diffuse sources. In 2009, all Berkeley Lab sources were minor sources of radionuclides (sources resulting in a potential dose of less than 0.1 mrem/yr [0.001 mSv/yr]). These minor sources included more than 100 stack sources and one source of diffuse emissions. There were no unplanned emissions from the Berkeley Lab site. Emissions from minor sources (stacks and diffuse emissions) either were measured by sampling or monitoring or were calculated based on quantities used, received for use, or produced during the year. Using measured and calculated emissions, and building-specific and common parameters, Laboratory personnel applied the EPA-approved computer code, CAP88-PC, to calculate the effective dose equivalent to the maximally exposed individual (MEI). The effective dose equivalent from all sources at Berkeley Lab in 2009 is 7.0 x 10{sup -3} mrem/yr (7.0 x 10{sup -5} mSv/yr) to the MEI, well below the 10 mrem/yr (0.1 mSv/yr) dose standard. The location of the MEI is at the University of California (UC) Lawrence Hall of Science, a public science museum about 1500 ft (460 m) east of Berkeley Lab's Building 56. The estimated collective effective dose equivalent to persons living within 50 mi (80 km) of Berkeley Lab is 1.5 x 10{sup -1} person-rem (1.5 x 10{sup -3} person-Sv) attributable to the Lab's airborne emissions in 2009.

  2. RADIONUCLIDE AIR EMISSIONS REPORT FOR THE HANFORD SITE CY2003

    International Nuclear Information System (INIS)

    ROKKAN, D.J.

    2004-01-01

    This report documents radionuclide air emissions from the US Department of Energy (DOE) Hanford Site in 2003 and the resulting effective dose equivalent (EDE) to the maximally exposed individual (MEI) member of the public. The report has been prepared in accordance with the Code of Federal Regulations (CFR), Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants, Subpart H, ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities''; Washington Administrative Code (WAC) Chapter 246-247, ''Radiation Protection-Air Emissions''; 10 CFR 830.120, Quality Assurance; DOE Order 414.1B, Quality Assurance; NQA-1, Quality Assurance Requirements for Nuclear Facility Application; EPA QA/R-2, EPA Requirements for Quality Management Plans; and EPA QA/R-5, Requirements for Quality Assurance Project Plans. The federal regulations in Subpart H of 40 CFR 61 require the measurement and reporting of radionuclides emitted from DOE facilities and the resulting public dose from those emissions. A standard of 10 mrem/yr EDE is not to be exceeded. The EDE to the MEI due to routine and nonroutine emissions in 2003 from Hanford Site point sources was 0.022 mrem (0.00022 mSv), or 0.22 percent of the federal standard. The portions of the Hanford Site MEI dose attributable to individual point sources as listed in Section 2.0 are appropriate for use in demonstrating the compliance of abated stack emissions with applicable terms of the Hanford Site Air Operating Permit and of Notices of Construction. The state has adopted the 40 CFR 61 standard of 10 mrem/yr EDE into their regulations, yet further requires that the EDE to the MEI be calculated not only from point source emissions but also from diffuse and fugitive sources of emissions. WAC 246-247 also requires the reporting of radionuclide emissions from all Hanford Site sources during routine as well as nonroutine operations. The EDE from

  3. Air emission inventory for the Idaho National Engineering Laboratory: 1994 emissions report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    This report Presents the 1994 update of the Air Emission inventory for the Idaho National Engineering Laboratory (INEL). The INEL Air Emission Inventory documents sources and emissions of non-radionuclide pollutants from operations at the INEL. The report describes the emission inventory process and all of the sources at the INEL, and provides non-radionuclide emissions estimates for stationary sources.

  4. Air emission inventory for the Idaho National Engineering Laboratory: 1994 emissions report

    International Nuclear Information System (INIS)

    1995-07-01

    This report Presents the 1994 update of the Air Emission inventory for the Idaho National Engineering Laboratory (INEL). The INEL Air Emission Inventory documents sources and emissions of non-radionuclide pollutants from operations at the INEL. The report describes the emission inventory process and all of the sources at the INEL, and provides non-radionuclide emissions estimates for stationary sources

  5. Sequim Site Radionuclide Air Emissions Report for Calendar Year 2012

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Sandra F.; Barnett, J. Matthew; Gervais, Todd L.

    2013-04-01

    This report is prepared to document compliance with the Code of Federal Regulations (CFR), Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (NESHAP), Subpart H, National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities and ashington Administrative Code (WAC) Chapter 246-247, Radiation Protection Air Emissions. This report meets the calendar year 2012 Sequim Site annual reporting requirement for its operations as a privately-owned facility as well as its federally-contracted status that began in October 2012. Compliance is indicated by comparing the estimated dose to the maximally exposed individual (MEI) with the 10 mrem/yr Environmental Protection Agency (EPA) standard. The MSL contains only sources classified as fugitive emissions. Despite the fact that the regulations are intended for application to point source emissions, fugitive emissions are included with regard to complying with the EPA standard. The dose to the Sequim Site MEI due to routine operations in 2012 was 9E-06 mrem (9E-08 mSv). No non-routine emissions occurred in 2012. The MSL is in compliance with the federal and state 10 mrem/yr standard.

  6. Radionuclide air emission report for the Hanford Site Calendar Year 1993

    International Nuclear Information System (INIS)

    Diediker, L.P.; Curn, B.L.; Rhoads, K.; Damberg, E.G.; Soldat, J.K.; Jette, S.J.

    1994-01-01

    This report documents radionuclide air emissions from the Hanford Site in 1993 and the resulting effective dose equivalent to any member of the public. The report has been prepared and will be submitted in accordance with reporting requirements in the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, open-quotes National Emissions Standards for Hazardous Air Pollutants,close quotes Subpart H, open-quotes National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities.close quotes

  7. Volcanic emission of radionuclides and magma dynamics

    International Nuclear Information System (INIS)

    Lambert, G.; Le Cloarec, M.F.; Ardouin, B.; Le Roulley, J.C.

    1985-01-01

    210 Pb, 210 Bi and 210 Po, the last decay products of the 238 U series, are highly enriched in volcanic plumes, relative to the magma composition. Moreover this enrichment varies over time and from volcano to volcano. A model is proposed to describe 8 years of measurements of Mt. Etna gaseous emissions. The lead and bismuth coefficients of partition between gaseous and condensated phases in the magma are determined by comparing their concentrations in lava flows and condensated volatiles. In the case of volatile radionuclides, an escaping time is calculated which appears to be related to the volcanic activity. Finally, it is shown that that magma which is degassing can already be partly degassed; it should be considered as a mixture of a few to 50% of deep non-degassed magma with a well degassed superficial magma cell. (orig.)

  8. National Emission Inventory

    Data.gov (United States)

    U.S. Environmental Protection Agency — The National Emission Inventory contains measured, modeled, and estimated data for emissions of all known source categories in the US (stationary sources, fires,...

  9. National Emission Information System

    International Nuclear Information System (INIS)

    Sajtakova, E.; Spisakova, K.

    2005-01-01

    In this presentation the Slovak National Emission Information System (NEIS) is presented. The NEIS represents hierarchical oriented modular system of acquisition, verification, saving and reporting of data about annual emissions and payments for pollution of atmosphere

  10. Air emissions inventory for the Idaho National Engineering Laboratory -- 1995 emissions report

    International Nuclear Information System (INIS)

    1996-06-01

    This report presents the 1995 update of the Air Emission Inventory for the Idaho National Engineering Laboratory (INEL). The INEL Air Emission Inventory documents sources and emissions of non-radionuclide pollutants from operations at the INEL. The report describes the emission inventory process and all of the sources at the INEL, and provides non-radionuclide emissions estimates for stationary sources. The air contaminants reported include nitrogen oxides, sulfur oxides, carbon monoxide, volatile organic compounds, particulates, and hazardous air pollutants (HAPs)

  11. Air emissions inventory for the Idaho National Engineering Laboratory -- 1995 emissions report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    This report presents the 1995 update of the Air Emission Inventory for the Idaho National Engineering Laboratory (INEL). The INEL Air Emission Inventory documents sources and emissions of non-radionuclide pollutants from operations at the INEL. The report describes the emission inventory process and all of the sources at the INEL, and provides non-radionuclide emissions estimates for stationary sources. The air contaminants reported include nitrogen oxides, sulfur oxides, carbon monoxide, volatile organic compounds, particulates, and hazardous air pollutants (HAPs).

  12. National Emission Inventory (NEI)

    Data.gov (United States)

    U.S. Environmental Protection Agency — This data exchange allows states to submit data to the US Environmental Protection Agency's National Emissions Inventory (NEI). NEI is a national database of air...

  13. U.S. Department of Energy Report, 2005 LANL Radionuclide Air Emissions

    Energy Technology Data Exchange (ETDEWEB)

    Keith W. Jacobson, David P. Fuehne

    2006-09-01

    Amendments to the Clean Air Act, which added radionuclides to the National Emissions Standards for Hazardous Air Pollutants (NESHAP), went into effect in 1990. Specifically, a subpart (H) of 40 CFR 61 established an annual limit on the impact to the public attributable to emissions of radionuclides from U.S. Department of Energy facilities, such as the Los Alamos National Laboratory (LANL). As part of the new NESHAP regulations, LANL must submit an annual report to the U.S. Environmental Protection Agency headquarters and the regional office in Dallas by June 30. This report includes results of monitoring at LANL and the dose calculations for the calendar year 2006.

  14. Radionuclide Air Emissions Report for the Hanford Site Calendar Year 1999

    Energy Technology Data Exchange (ETDEWEB)

    ROKKAN, D.J.

    2000-06-01

    This report documents radionuclide air emissions from the US. Department of Energy (DOE) Hanford Site in 1999 and the resulting effective dose equivalent to the maximally exposed individual (MEI) member of the public. The report has been prepared in accordance with the Code of Federal Regulations (CFR). Title 40, Protection of the Environment, Part 61. National Emission Standards for Hazardous Air Pollutants, Subpart H, ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities'', and with the Washington Administrative Code (WAC) Chapter 246-247. Radiation Protection-Air Emissions. The federal regulations in Subpart H of 40 CFR 61 require the measurement and reporting of radionuclides emitted from US. Department of Energy (DOE) facilities and the resulting offsite dose from those emissions. A standard of 10 mrem/yr effective dose equivalent (EDE) is imposed on them. The EDE to the MEI due to routine emissions in 1999 from Hanford Site point sources was 0.029 mrem (2.9 E-04 mSv), which is less than 0.3 percent of the federal standard. WAC 246-247 requires the reporting of radionuclide emissions from all Hanford Site sources, during routine as well as nonroutine operations. The state has adopted the 40 CFR 61 standard of 10 mrem/yr EDE into their regulations. The state further requires that the EDE to the MEI be calculated not only from point source emissions but also from diffuse and fugitive sources of emissions. The EDE from diffuse and fugitive emissions at the Hanford Site in 1999 was 0.039 mrem (3.9 E-04 mSv) EDE. The total dose from point sources and from diffuse and fugitive sources of radionuclide emissions during all operating conditions in 1999 was 0.068 mrem (6.8 E-04 mSv) EDE, which is less than 0.7 percent of the state standard.

  15. Radionuclide Air Emissions Report for the Hanford Site Calendar Year 1999

    International Nuclear Information System (INIS)

    ROKKAN, D.J.

    2000-01-01

    This report documents radionuclide air emissions from the US. Department of Energy (DOE) Hanford Site in 1999 and the resulting effective dose equivalent to the maximally exposed individual (MEI) member of the public. The report has been prepared in accordance with the Code of Federal Regulations (CFR). Title 40, Protection of the Environment, Part 61. National Emission Standards for Hazardous Air Pollutants, Subpart H, ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities'', and with the Washington Administrative Code (WAC) Chapter 246-247. Radiation Protection-Air Emissions. The federal regulations in Subpart H of 40 CFR 61 require the measurement and reporting of radionuclides emitted from US. Department of Energy (DOE) facilities and the resulting offsite dose from those emissions. A standard of 10 mrem/yr effective dose equivalent (EDE) is imposed on them. The EDE to the MEI due to routine emissions in 1999 from Hanford Site point sources was 0.029 mrem (2.9 E-04 mSv), which is less than 0.3 percent of the federal standard. WAC 246-247 requires the reporting of radionuclide emissions from all Hanford Site sources, during routine as well as nonroutine operations. The state has adopted the 40 CFR 61 standard of 10 mrem/yr EDE into their regulations. The state further requires that the EDE to the MEI be calculated not only from point source emissions but also from diffuse and fugitive sources of emissions. The EDE from diffuse and fugitive emissions at the Hanford Site in 1999 was 0.039 mrem (3.9 E-04 mSv) EDE. The total dose from point sources and from diffuse and fugitive sources of radionuclide emissions during all operating conditions in 1999 was 0.068 mrem (6.8 E-04 mSv) EDE, which is less than 0.7 percent of the state standard

  16. Risk-assessments Environmental Impact Statement. NESHAPs (National Emission Standards for Hazardous Air Pollutants) for radionuclides. Background information document. Volume 2

    International Nuclear Information System (INIS)

    1989-09-01

    The publication contains a chapter on each radionuclide source category studied. The chapters include an introduction, category description, process description, control technology, health impact assessment, supplemental control technology, and cost. It has an appendix which contains the inputs to all the computer runs used to generate the risk assessment

  17. Emissions of the corrosion radionuclides in an atmosphere

    International Nuclear Information System (INIS)

    Vardanyan, M.

    2010-01-01

    In area of Armenian nuclear power plant location, in atmospheric air in majority of cases log two technogenic radionuclides: l 37 C s and 9 0 S r. Presence of these radionuclides basically is caused by global fall out (consequences of tests of the nuclear weapon and Chernobyl NPP accident), whose contribution to the contents of these radionuclides in atmosphere is incomparably greater, than emissions from the NPP. However there are some cases when in an atmosphere are registered the technogenic radionuclides, caused by emissions from NPP. In the present work such case is considered. Gas-aerosol releases of NPP in the atmosphere are carefully purified by means of various high-efficiency filters and gas-cleaning systems. Nevertheless, one should forecast and measure, the possible impact of these releases on the environment in the regions surrounding the NPP. Radioactive releases of the Armenian NPP (ANPP) contain the set of radionuclides characteristic for NPPs of this type. They may be divided into three groups: 1 31 I , 1 37 C s, 1 34 C s, 9 0 S r and 8 9 S r fission fragments, isotopes of noble gases krypton and xenon and other radionuclides; corrosion originated radionuclides: 6 0 C o, 1 10m A g, 5 4 M n, 5 l C r and others; activation products of the heat-transfer agent itself. It should be noted that the amount of radioactive materials released in the environment by the ANPP during the whole period of its operation was much lower than the admissible quantities specified in the corresponding legal documents (RSN, NPPSP) acting in Armenia, which are practically identical to the internationally accepted norms. The amounts of releases and their radionuclides composition for the ANPP are given

  18. National Low-Level Waste Management Program Radionuclide Report Series

    International Nuclear Information System (INIS)

    Rudin, M.J.; Garcia, R.S.

    1992-02-01

    This volume serves as an introduction to the National Low-Level Radioactive Waste Management Program Radionuclide Report Series. This report includes discussions of radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha-emitting transuranics with half-lives greater than five years). Each report includes information regarding radiological and chemical characteristics of specific radionuclides. Information is also included discussing waste streams and waste forms that may contain each radionuclide, and radionuclide behavior in the environment and in the human body. Not all radionuclides commonly found at low-level radioactive waste sites are included in this report. The discussion in this volume explains the rationale of the radionuclide selection process

  19. Marine Sciences Laboratory Radionuclide Air Emissions Report for Calendar Year 2014

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Sandra F.; Barnett, J. Matthew

    2015-05-04

    The U.S. Department of Energy Office of Science (DOE-SC) Pacific Northwest Site Office (PNSO) has oversight and stewardship duties associated with the Pacific Northwest National Laboratory (PNNL) Marine Sciences Laboratory (MSL) located on Battelle Land – Sequim.This report is prepared to document compliance with the Code of Federal Regulations (CFR), Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (NESHAP), Subpart H, ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities” and Washington Administrative Code (WAC) Chapter 246-247, “Radiation Protection–Air Emissions.'' The EDE to the MSL MEI due to routine operations in 2014 was 9E-05 mrem (9E-07 mSv). No non-routine emissions occurred in 2014. The MSL is in compliance with the federal and state 10 mrem/yr standard.

  20. Marine Sciences Laboratory Radionuclide Air Emissions Report for Calendar Year 2013

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Sandra F.; Barnett, J. Matthew; Ballinger, Marcel Y.

    2014-05-01

    The U.S. Department of Energy Office of Science (DOE-SC) Pacific Northwest Site Office (PNSO) has oversight and stewardship duties associated with the Pacific Northwest National Laboratory (PNNL) Marine Sciences Laboratory (MSL) located on Battelle Land – Sequim (Sequim). This report is prepared to document compliance with the Code of Federal Regulations (CFR), Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (NESHAP), Subpart H, “National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities” and Washington Administrative Code (WAC) Chapter 246-247, “Radiation Protection–Air Emissions.” The EDE to the Sequim MEI due to routine operations in 2013 was 5E-05 mrem (5E-07 mSv). No non-routine emissions occurred in 2013. The MSL is in compliance with the federal and state 10 mrem/yr standard.

  1. Implementation of sum-peak method for standardization of positron emission radionuclides

    International Nuclear Information System (INIS)

    Fragoso, Maria da Conceicao de Farias; Oliveira, Mercia Liane de; Lima, Fernando Roberto de Andrade

    2015-01-01

    Positron Emission Tomography (PET) is being increasingly recognized as an important quantitative imaging tool for diagnosis and assessing response to therapy. As correct dose administration plays a crucial part in nuclear medicine, it is important that the instruments used to assay the activity of the short-lived radionuclides are calibrated accurately, with traceability to the national or international standards. The sum-peak method has been widely used for radionuclide standardization. The purpose of this study was to implement the methodology for standardization of PET radiopharmaceuticals at the Regional Center for Nuclear Sciences of the Northeast (CRCN-NE). (author)

  2. National Greenhouse Gas Emission Inventory

    Data.gov (United States)

    U.S. Environmental Protection Agency — The National Greenhouse Gas Emission Inventory contains information on direct emissions of greenhouse gases as well as indirect or potential emissions of greenhouse...

  3. Radionuclide Air Emissions Report for the Hanford Site Calendar year 1998

    Energy Technology Data Exchange (ETDEWEB)

    DIEDIKER, L.P.

    1999-06-15

    This report documents radionuclide air emissions from the Hanford Site in I998 and the resulting effective dose equivalent to the maximally exposed individual (MEI) member of the public. The report has been prepared in accordance with the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, National Emission Standards for Hazardous Air Pollutants (40 CFR SI), Subpart H, ''National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities,'' and with the Washington Administrative Code Chapter 246-247, Radiation Protection--Air Emissions. The federal regulations in 40 CFR 61, Subpart H; require the measurement and reporting of radionuclides emitted from Department of Energy facilities and the resulting offsite dose from those emissions. A standard of 10 mrem/yr effective dose equivalent (EDE) is imposed on them. The EDE to the MEI due to routine emissions in 1998 from Hanford Site point sources was 1.3 E-02 mrem (1.3 E-04 mSv), which is 0.13 percent of the federal standard. Chapter 246-247 of the Washington Administrative Code (WAC) requires the reporting of radionuclide emissions from all Department of Energy Hanford Site sources. The state has adopted into these regulations the 40 CFR 61 standard of 10 mrem/yr EDE. The EDE to the MEI attributable to diffuse and fugitive radionuclide air emissions from the Hanford Site in 1998 was 2.5 E-02 mrem (2.5 E-04 mSv). This dose added to the dose from point sources gives a total for all sources of 3.8 E-02 mrem/yr (3.8 E-04 mSv) EDE, which is 0.38 percent of the 10 mrem/yr standard. An unplanned release on August 26, 1998, in the 300 Area of the Hanford Site resulted in a potential dose of 4.1 E-02 mrem to a hypothetical individual at the nearest point of public access to that area. This hypothetical individual was not the MEI since the wind direction on the day of the release was away from the MEI residence. The potential dose from

  4. 1990 INEL national emission standards for hazardous air pollutants

    International Nuclear Information System (INIS)

    1990-05-01

    The Environmental Protection Agency issued on December 15, 1989 final rules governing air emissions of radionuclides. Requirements concerning radionuclide emissions from Department of Energy Facilities are addressed under Title 40, Code Federal Regulations (CFR) 61, Subpart H, ''National Emission Standards for Emissions of Radionuclides other Than Radon From Department of Energy Facilities.'' Section 61.94 of the regulations require that each DOE facility submit on an annual basis a report documenting compliance with the Subpart H requirements. This report addresses the section 61.94 reporting requirements for operations at the Idaho National Engineering Laboratory (INEL) for calendar year 1990. The Idaho Operations Office of the Department of Energy is the primary contact concerning NESHAPs compliance at the INEL

  5. Radionuclide air emissions at Department of Energy facilities

    Energy Technology Data Exchange (ETDEWEB)

    Duvall, K. [Department of Energy, Washington, DC (United States)

    1995-02-01

    Facilities operated by the U.S. Department of Energy (DOE) handle and process radioactive materials in conjunction with their research, nuclear materials production, remediation and waste disposal activities. Radionuclide emissions to the atmosphere from DOE facilities are regulated by the Environmental Protection Agency (EPA) under 40 CFR Part 61, Subpart H for emissions other than radon. Subpart H requires DOE to monitor emissions from stacks and calculate a potential offsite dose to an individual using EPA approved methods and procedures. DOE has applied to EPA for approval to use alternative methods for some of the EPA requirements for continuous monitoring. The use of alternative methods such as single-point sampling with a shrouded probe will have an impact at several major DOE facilities. These facilities are identified.

  6. Radionuclide air emissions report for the Hanford Site -- calendar year 1997

    Energy Technology Data Exchange (ETDEWEB)

    Gleckler, B.P.; Rhoads, K.

    1998-06-17

    This report documents radionuclide air emission from the Hanford Site in 1997, and the resulting effective dose equivalent to the maximally exposed member of the public, referred to as the MEI. The report has been prepared in accordance with reporting requirements in the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, National Emissions Standards for Hazardous Air Pollutants, Subpart H, National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities. This report has also been prepared in accordance with the reporting requirements of the Washington Administrative Code Chapter 246-247, Radiation Protection-Air Emissions. The effective dose equivalent to the MEI from the Hanford Site`s 1997 point source emissions was 1.2 E-03 mrem (1.2 E-05 mSv), which is well below the 40 CFR 61 Subpart H regulatory limit of 10 mrem/yr. Radon and thoron emissions, exempted from 40 CFR 61 Subpart H, resulted in an effective dose equivalent to the MEI of 2.5 E-03 mrem (2.5 E-05 mSv). The effective dose equivalent to the MEI attributable to diffuse and fugitive emissions was 2.2 E-02 mrem (2.2 E-04 mSv). The total effective dose equivalent from all of the Hanford Site`s air emissions was 2.6 E-02 mrem (2.6 E-04 mSv). The effective dose equivalent from all of the Hanford Site`s air emissions is well below the Washington Administrative Code, Chapter 246-247, regulatory limit of 10 mrem/yr.

  7. Radionuclide air emissions report for the Hanford Site. Calendar year 1997

    International Nuclear Information System (INIS)

    Gleckler, B.P.; Rhoads, K.

    1998-01-01

    This report documents radionuclide air emission from the Hanford Site in 1997, and the resulting effective dose equivalent to the maximally exposed member of the public, referred to as the MEI. The report has been prepared in accordance with reporting requirements in the Code of Federal Regulations, Title 40, Protection of the Environment, Part 61, National Emissions Standards for Hazardous Air Pollutants, Subpart H, National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities. This report has also been prepared in accordance with the reporting requirements of the Washington Administrative Code Chapter 246-247, Radiation Protection-Air Emissions. The effective dose equivalent to the MEI from the Hanford Site's 1997 point source emissions was 1.2 E-03 mrem (1.2 E-05 mSv), which is well below the 40 CFR 61 Subpart H regulatory limit of 10 mrem/yr. Radon and thoron emissions, exempted from 40 CFR 61 Subpart H, resulted in an effective dose equivalent to the MEI of 2.5 E-03 mrem (2.5 E-05 mSv). The effective dose equivalent to the MEI attributable to diffuse and fugitive emissions was 2.2 E-02 mrem (2.2 E-04 mSv). The total effective dose equivalent from all of the Hanford Site's air emissions was 2.6 E-02 mrem (2.6 E-04 mSv). The effective dose equivalent from all of the Hanford Site's air emissions is well below the Washington Administrative Code, Chapter 246-247, regulatory limit of 10 mrem/yr

  8. Marine Sciences Laboratory Radionuclide Air Emissions Report for Calendar Year 2015

    Energy Technology Data Exchange (ETDEWEB)

    Snyder, Sandra F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Barnett, J. Matthew [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-05-05

    The U.S. Department of Energy Office of Science (DOE-SC) Pacific Northwest Site Office has oversight and stewardship duties associated with the Pacific Northwest National Laboratory Marine Sciences Laboratory located on Battelle Land – Sequim. This report is prepared to document compliance with the 40 CFR Part 61, Subpart H, “National Emission Standards for Emissions of Radionuclides Other than Radon from Department of Energy Facilities” and Washington Administrative Code . The EDE to the MSL MEI due to routine operations in 2015 was 1.1E-04 mrem (1.1E-06 mSv). No non-routine emissions occurred in 2015. The MSL is in compliance with the federal and state 10 mrem/yr standard.

  9. National Low-Level Waste Management Program Radionuclide Report Series

    International Nuclear Information System (INIS)

    Rudin, M.J.; Stanton, C.; Patterson, R.G.; Garcia, R.S.

    1992-02-01

    This report, Volume 2 of the National Low-Level Radioactive Waste Management Program Radionuclide Report Series, discusses radiological and chemical characteristics of technetium-99. This report also includes discussions about waste streams in which technetium-99 can be found, waste forms that contain technetium-99, and technetium-99's behavior in the environment and in the human body

  10. National Low-Level Waste Management Program Radionuclide Report Series

    International Nuclear Information System (INIS)

    Rudin, M.J.; Garcia, R.S.

    1992-02-01

    This report, Volume 3 of the National Low-Level Radioactive Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of carbon-14. The report also discusses waste streams that contain carbon-14, waste forms that contain carbon-14, and carbon-14 behavior in the environment and in the human body

  11. Radionuclide emissions from a coal-fired power plant

    International Nuclear Information System (INIS)

    Amin, Y.M.; Uddin Khandaker, Mayeen; Shyen, A.K.S.; Mahat, R.H.; Nor, R.M.; Bradley, D.A.

    2013-01-01

    Current study concerns measurement of radioactivity levels in areas surrounding a 2420 MW thermal power plant fueled predominantly by bituminous coal. The concentrations of 226 Ra, 232 Th and 40 K in onsite bottom-ash were found to be 139 Bq/kg, 108 Bq/kg and 291 Bq/kg, respectively, the levels for these radiolnuclides in soil decreasing with distance from the power plant. At the plant perimeter the respective radionuclide concentrations were 87 Bq/kg, 74 Bq/kg and 297 Bq/kg. In a nearby town, the corresponding concentrations were 104 Bq/kg, 52 Bq/kg and 358 Bq/kg, suggestive of use of TENORM affected soils. The mean radium equivalent activities (Ra eq ) in soil and ash sample in the town were 205 Bq/kg and 316 Bq/kg, respectively. The Kapar plant ash/slag appears to contain a higher level of TENORM than the world average. The degree of contamination is much higher inside the town where slag has been mixed with topsoil as landfill or as simple domestic waste. For the prevailing levels of exposure and a worst case senario, the predicted committed effective dose due to ingestion and inhalation for intake durations of 1- and 30 years would be 4.2 μSv and 220 μSv, respectively. - Highlights: • Detailed studies on naturally occuring radionuclide emissions due to a 2420 MW coal-fired power plant in Malaysia. • Assessment of radiation exposures to the public around the power plant due to an intake of the radionuclides. • The Kapar plant ash/slag appears to contain a higher level of TENORM than the world average. • The degree of contamination is much higher inside the town where slag has been mixed with topsoil as landfill or as simple domestic waste

  12. Determining Original Inventory Amount of Radioactive Substances from Unmonitored Radionuclide Emissions

    International Nuclear Information System (INIS)

    Hamilton, J.T.; Blunt, B.C.

    1999-01-01

    The purpose of this document is to determine the air emissions inventory of the Savannah River Site. To satisfy regulatory requirements, a new equation has been developed to determine original inventory amounts from unmonitored radionuclide emissions

  13. National Emission Standards for Hazardous Air Pollutants submittal - 1997

    International Nuclear Information System (INIS)

    Townsend, Y.E.; Black, S.C.

    1998-06-01

    Each potential source of Nevada Test Site (NTS) emissions was characterized by one of the following methods: (1) monitoring methods and procedures previously developed at the NTS; (2) a yearly radionuclide inventory of the source, assuming that volatile radionuclide are released to the environment; (3) the measurement of tritiated water (as HTO or T 2 O) concentration in liquid effluents discharged to containment ponds and assuming all the effluent evaporates over the course of the year to become an air emission; or (4) using a combination of environmental measurements and CAP88-PC to calculate emissions. The emissions for National Emission Standards for Hazardous Air Pollutants (NESHAPs) reporting are listed. They are very conservative and are used in Section 3 to calculate the EDE to the maximally exposed individual offsite. Offsite environmental surveillance data, where available, are used to confirm that calculated emissions are, indeed, conservative

  14. National Survey of Radionuclide Gastric Emptying Studies

    Directory of Open Access Journals (Sweden)

    A House

    1997-01-01

    Full Text Available A survey was mailed to all institutions in Canada licensed to use radiopharmaceuticals. Questions addressed meal type; mode of preparation; and means, ranges and SD of emptying times. Seventy-eight per cent of 222 facilities responded, including all 55 teaching centres. Eighty-five per cent of teaching and 56% of nonteaching centres perform solid phase gastric emptying studies (GES. The majority use 99mTc sulphur colloid (Tc-SC added to eggs before cooking as the standard meal. Twenty-five per cent of teaching and 21% of nonteaching centres perform liquid phase GES. Most use a watery solution of 111In-diethylenetriamine pentaacetic acid. Gastric emptying for solid phase GES, expressed as time for 50% emptying (mean t½, varied from 42 to 105 mins for centres using the Tc-SC egg meal. Twenty-eight per cent of teaching centres used ±2 SD to define their normal range, 26% used ±1 SD, 6% used ±1.5 SD, and 40% did not know the number of SD used. Twenty per cent of non-teaching centres used ±2 SD, 12% used ±1 SD and 68% did not know how many SD were used. For liquid phase GES, mean t½ varied from 20 to 60 mins. Eighteen per cent of centres used healthy volunteers to establish or validate normal ranges. There is substantial variability among the normal ranges for radionuclide solid and liquid phase GES in both teaching and nonteaching centres across Canada. A minority of facilities have established or validated their own normal ranges in healthy volunteers. There is a need for a more standardized protocol and range of normal, with internal validation by each institution.

  15. Deriving cleanup guidelines for radionuclides at Brookhaven National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Meinhold, A.F.; Morris, S.C.; Dionne, B.; Moskowitz, P.D.

    1997-01-01

    Past activities at Brookhaven National Laboratory (BNL) resulted in soil and groundwater contamination. As a result, BNL was designated a Superfund site under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). BNL`s Office of Environmental Restoration (OER) is overseeing environmental restoration activities at the Laboratory. With the exception of radium, there are no regulations or guidelines to establish cleanup guidelines for radionuclides in soils at BNL. BNL must derive radionuclide soil cleanup guidelines for a number of Operable Units (OUs) and Areas of Concern (AOCs). These guidelines are required by DOE under a proposed regulation for radiation protection of public health and the environment as well as to satisfy the requirements of CERCLA. The objective of this report is to propose a standard approach to deriving risk-based cleanup guidelines for radionuclides in soil at BNL. Implementation of the approach is briefly discussed.

  16. Deriving cleanup guidelines for radionuclides at Brookhaven National Laboratory

    International Nuclear Information System (INIS)

    Meinhold, A.F.; Morris, S.C.; Dionne, B.; Moskowitz, P.D.

    1997-01-01

    Past activities at Brookhaven National Laboratory (BNL) resulted in soil and groundwater contamination. As a result, BNL was designated a Superfund site under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). BNL's Office of Environmental Restoration (OER) is overseeing environmental restoration activities at the Laboratory. With the exception of radium, there are no regulations or guidelines to establish cleanup guidelines for radionuclides in soils at BNL. BNL must derive radionuclide soil cleanup guidelines for a number of Operable Units (OUs) and Areas of Concern (AOCs). These guidelines are required by DOE under a proposed regulation for radiation protection of public health and the environment as well as to satisfy the requirements of CERCLA. The objective of this report is to propose a standard approach to deriving risk-based cleanup guidelines for radionuclides in soil at BNL. Implementation of the approach is briefly discussed

  17. National pollutants emission limits

    International Nuclear Information System (INIS)

    Chmielewski, A.G.; Pawelec, A.

    2011-01-01

    Fossil fuels are the main energy sources. Unfortunately the vast quantities of pollutants are emitted to the atmosphere during their combustion. These emissions lead to the environment degradation and affect human health. Therefore most of the countries have introduced the standards concerning emission control. These regulations for some countries are presented in the paper. (author)

  18. National pollutants emission limits

    Energy Technology Data Exchange (ETDEWEB)

    Chmielewski, A. G.; Pawelec, A. [Institute of Nuclear Chemistry and Technology, Warsaw (Poland)

    2011-07-01

    Fossil fuels are the main energy sources. Unfortunately the vast quantities of pollutants are emitted to the atmosphere during their combustion. These emissions lead to the environment degradation and affect human health. Therefore most of the countries have introduced the standards concerning emission control. These regulations for some countries are presented in the paper. (author)

  19. Quality assurance program plan for radionuclide airborne emissions monitoring

    International Nuclear Information System (INIS)

    Boom, R.J.

    1995-03-01

    This Quality Assurance Program Plan identifies quality assurance program requirements and addresses the various Westinghouse Hanford Company organizations and their particular responsibilities in regards to sample and data handling of airborne emissions. The Hanford Site radioactive airborne emissions requirements are defined in National Emissions Standards for Hazardous Air Pollutants (NESHAP), Code of Federal Regulations, Title 40, Part 61, Subpart H (EPA 1991a). Reporting of the emissions to the US Department of Energy is performed in compliance with requirements of US Department of Energy, Richland Operations Office Order 5400.1, General Environmental Protection Program (DOE-RL 1988). This Quality Assurance Program Plan is prepared in accordance with and to the requirements of QAMS-004/80, Guidelines and Specifications for Preparing Quality Assurance Program Plans (EPA 1983). Title 40 CFR Part 61, Appendix B, Method 114, Quality Assurance Methods (EPA 1991b) specifies the quality assurance requirements and that a program plan should be prepared to meet the requirements of this regulation. This Quality Assurance Program Plan identifies NESHAP responsibilities and how the Westinghouse Hanford Company Environmental, Safety, Health, and Quality Assurance Division will verify that the methods are properly implemented

  20. National Emission Standards for Hazardous Air Pollutants submittal -- 1994

    International Nuclear Information System (INIS)

    Townsend, Y.E.; Black, S.C.

    1995-06-01

    This report focuses on air quality at the Nevada Test Site (NTS) for 1994. A general description of the effluent sources are presented. Each potential source of NTS emissions was characterized by one of the following: (1) by monitoring methods and procedures previously developed at NTS; (2) by a yearly radionuclide inventory of the source, assuming that volatile radionuclides are released to the environment; (3) by the measurement of tritiated water concentration in liquid effluents discharged to containment ponds and assuming all the effluent evaporates over the course of the year to become an air emission; or (4) by using a combination of environmental measurements and CAP88-PC to calculate emissions. Appendices A through J describe the methods used to determine the emissions from the sources. These National Emission Standards for Hazardous Air Pollutants (NESHAP) emissions are very conservative, are used to calculate the effective dose equivalent to the Maximally Exposed Individual offsite, and exceed, in some cases, those reported in DOE's Effluent Information System (EIS). The NESHAP's worst-case emissions that exceed the EIS reported emissions are noted. Offsite environmental surveillance data are used to confirm that calculated emissions are, indeed, conservative

  1. Summary of radionuclide air emissions from Department of Energy facilities for CY 1991

    International Nuclear Information System (INIS)

    1992-12-01

    The U. S. Department of Energy (DOE) operates a number of facilities that handle radioactive materials in conjunction with its research and nuclear materials production activities. These include laboratories for research, production facilities for nuclear materials and weapons, and facilities for storage and disposal of radioactive wastes. During normal operations, some of these facilities have the potential to release small quantities of radionuclides to the atmosphere which the U. S. Environmental Protection Agency (EPA) regulates under the authority of Section 112 of the Clean Air Act. The regulations are specifiedin the National Emission Standards for Hazardous Air Pollutants (NESHAP), in 40 CFR Part 61. Subpart H of the NESHAP sets standards for public exposure to airborne radioactive materials (other than radon) released by DOE facilities

  2. US Department of Energy report 1996 LANL radionuclide air emissions

    Energy Technology Data Exchange (ETDEWEB)

    Jacobson, K.W.

    1997-08-01

    Presented is the Laboratory-wide certified report regarding radioactive effluents released into the air by the Los Alamos National Laboratory (LANL) in 1996. This information is required under the Clean Air Act and is being reported to the U.S. Environmental Protection Agency (EPA). The effective dose equivalent (EDE) to a hypothetical maximum exposed individual (MEI) of the public was calculated, using procedures specified by the EPA and described in this report. That dose was 1.93 mrem for 1996. Emissions of {sup 11}C, {sup 13}N, and {sup 15}O from a 1-mA, 800 MeV proton accelerator contributed over 92% of the EDE to LANL`s MEI. Using CAP88, the EPA`s dose assessment model, more than 86% of the total dose received by the MEI was via the air immersion pathway.

  3. A guide for determining compliance with the Clean Air Act Standards for radionuclide emissions from NRC-licensed and non-DOE federal facilities (Rev. 1)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1989-10-01

    The Environmental Protection Agency (EPA) issued standards under Section 112 of the Clean Air Act of February 6, 1985 that limit airborne emissions of radionuclides to the atmosphere. In February 1989 these standards were re proposed , and in November 1989 final standards may be promulgated. This document provides guidance for determining compliance with one of the National Emissions for Hazardous Air Pollutants covering facilities that are licensed by NRC, and federal facilities not operated by the DOE, that could emit radionuclides to the ai00.

  4. Radionuclide air emissions. Annual report for calendar year 1997

    International Nuclear Information System (INIS)

    1997-08-01

    A description is provided of radioactive effluent releases from the Pinellas Plant. The DOE sold the Pinellas Plant in March 1995. A portion of the plant was backed by DOE until September 1997 to facilitate a safe transition to commercial ventures.The plant's radiological processing equipment was cleaned from past DOE operations. Emissions from the cleanup activity were monitored

  5. Quality assurance program plan for radionuclide airborne emissions monitoring

    International Nuclear Information System (INIS)

    Boom, R.J.

    1995-12-01

    This Quality Assurance Program Plan identifies quality assurance program requirements and addresses the various Westinghouse Hanford Company organizations and their particular responsibilities in regards to sample and data handling of radiological airborne emissions. This Quality Assurance Program Plan is prepared in accordance with and to written requirements

  6. Quality Assurance Program Plan for radionuclide airborne emissions monitoring

    International Nuclear Information System (INIS)

    Vance, L.M.

    1993-07-01

    This Quality Assurance Program Plan (QAPP) describes the quality assurance requirements and responsibilities for radioactive airborne emissions measurements activities from regulated stacks are controlled at the Hanford Site. Detailed monitoring requirements apply to stacks exceeding 1% of the standard of 10 mrem annual effective dose equivalent to the maximally exposed individual from operations of the Hanford Site

  7. Quality Assurance Program Plan for radionuclide airborne emissions monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Vance, L.M.

    1993-07-01

    This Quality Assurance Program Plan (QAPP) describes the quality assurance requirements and responsibilities for radioactive airborne emissions measurements activities from regulated stacks are controlled at the Hanford Site. Detailed monitoring requirements apply to stacks exceeding 1% of the standard of 10 mrem annual effective dose equivalent to the maximally exposed individual from operations of the Hanford Site.

  8. Potential radionuclide emissions from stacks on the Hanford site, Part 1: Dose assessment

    Energy Technology Data Exchange (ETDEWEB)

    Davis, W.E.; Barnett, J.M. [Westinghouse Hanford Company, Richland, WA (United States)

    1995-02-01

    On February 3, 1993, the U.S. Department of Energy, Richland Operations Office received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the U.S. Environmental Protection Agency, Region 10. The Compliance Order requires RL to evaluate all radionuclide emission points at the Hanford Site to determine which are subject to continuous emission monitoring requirements in 40 CFR 61, Subpart H, and to continuously monitor radionuclide emissions in accordance with requirements in 40 CFR 61.93. The Information Request required RL to provide a written Compliance Plan to meet the requirements of the Compliance Order. A Compliance Plan was submitted to EPA, Region 10, on April 30, 1993. The Compliance Plan specified that a dose assessment would be performed for 84 Westinghouse Hanford Company stacks registered with the Washington State Department of Health on the Hanford Site. Stacks that have the potential emissions to cause an effective dose equivalent to a maximum exposed individual greater than 0.1 mrem/y must be monitored continuously for radionuclide emissions. Five methods were approved by EPA, Region 10 for performing the assessments: Release Fractions from Appendix D of 40 CFR 61, Back Calculations Using A HEPA Filtration Factor, Nondestructive Assay of HEPA Filters, A Spill Release Fraction, and Upstream of HEPA Filter Air Concentrations. The first two methods were extremely conservative for estimating releases. The third method, which used a state-of-the-art portable gamma spectrometer, yielded surprising results from the distribution of radionuclides on the HEPA filters. All five methods are described. Assessments using a HEPA Filtration Factor for back calculations identified 32 stacks that would have emissions that would cause an EDE to the MEI greater than 0.1 mrem y{sup {minus}1}. The number was reduced to 15 stacks when the other methods were applied. The paper discusses reasons for the overestimates.

  9. National low-level waste management program radionuclide report series, Volume 15: Uranium-238

    International Nuclear Information System (INIS)

    Adams, J.P.

    1995-09-01

    This report, Volume 15 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of uranium-238 ( 238 U). The purpose of the National Low-Level Waste Management Program Radionuclide Report Series is to provide information to state representatives and developers of low-level radioactive waste disposal facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the waste disposal facility environment. This report also includes discussions about waste types and forms in which 238 U can be found, and 238 U behavior in the environment and in the human body

  10. Implementation of sum-peak method for standardization of positron emission radionuclides; Implementacao do metodo pico-soma para padronizacao de radionuclideos emissores de positrons

    Energy Technology Data Exchange (ETDEWEB)

    Fragoso, Maria da Conceicao de Farias; Oliveira, Mercia Liane de; Lima, Fernando Roberto de Andrade, E-mail: mcfragoso@cnen.gov.br [Centro Regional de Ciencias Nucleares do Nordeste (CRCN-NE/CNEN-PE), Recife, PE (Brazil)

    2015-07-01

    Positron Emission Tomography (PET) is being increasingly recognized as an important quantitative imaging tool for diagnosis and assessing response to therapy. As correct dose administration plays a crucial part in nuclear medicine, it is important that the instruments used to assay the activity of the short-lived radionuclides are calibrated accurately, with traceability to the national or international standards. The sum-peak method has been widely used for radionuclide standardization. The purpose of this study was to implement the methodology for standardization of PET radiopharmaceuticals at the Regional Center for Nuclear Sciences of the Northeast (CRCN-NE). (author)

  11. Nevada National Security Site Underground Radionuclide Inventory, 1951-1992: Accounting for Radionuclide Decay through September 30, 2012

    Energy Technology Data Exchange (ETDEWEB)

    Finnegan, David Lawrence [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Bowen, Scott Michael [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Thompson, Joseph L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Miller, Charles M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Baca, Phyllis L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Olivas, Loretta F. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Geoffrion, Carmen G. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Smith, David K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Goishi, Wataru [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Esser, Bradley K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Meadows, Jesse W. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Namboodiri, Neil [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Wild, John F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2016-03-16

    This report is an update of report LA-13859-MS (Bowen et al., 2001). In that original report, the underground radionuclide inventory at the Nevada National Security Site (NNSS) was decay corrected to September 23, 1992, the date of the last underground nuclear test at the NNSS. In this report, the inventory is updated to account for the decay of radionuclides over two additional decades (1992-2012) and revised tritium, fission product and actinide inventory figures and tables are presented. The maximum contaminant levels for radionuclides were also updated to Safe Drinking Water Act Maximum Contaminant Levels (MCLs) (CFR, 2013). Also, a number of minor errata found in the original publication were corrected. An inventory of radionuclides produced by 828 underground nuclear tests conducted at the NNSS by the Lawrence Livermore National Laboratory, the Los Alamos National Laboratory, and the Department of the Defense from 1951 to 1992 includes tritium, fission products, actinides, and activation products. The inventory presented in this report provides an estimate of radioactivity remaining underground at the NNSS after nuclear testing. The original test inventory is decayed to September 30, 2012, and predictions of inventory decay over the subsequent 1000 years are presented. For the purposes of summary and publication, the Los Alamos National Laboratory and Lawrence Livermore National Laboratory authors of this report subdivided the inventory into five areas corresponding to the principal geographic test centers at the NNSS. The five areas roughly correspond to Underground Test Area “Corrective Action Units” (CAUs) for remediation of groundwater. In addition, the inventory is further subdivided for the Yucca Flat region by tests where the working point depth is more than 328 feet (100 meters) above the water table and tests that were detonated below that level. Water levels used were those from the U. S. Department of Energy, Nevada Operations Office (1997

  12. Estimating HAPs and radionuclide emissions from a laboratory complex at a nuclear processing site

    International Nuclear Information System (INIS)

    Paul, R.A.; Faugl, T.

    1993-01-01

    A unique methodology was developed for conducting an air emission inventory (AEI) at a DOE nuclear processing facility. This methodology involved the use of computer-assisted design (CAD) drawings to document emission points, computerized process drawings to document industrial processes leading to emissions, and a computerized data base of AEI forms to document emission estimates and related process data. A detailed air emissions inventory for operating years 1985--1991 was recently implemented for the entire site using this methodology. One industrial area at the DOE Site is comprised of laboratory facilities that provide direct support to the nuclear reactor and recovery operations, developmental studies to support reactor and separation operations, and developmental studies to support waste handling and storage. The majority of the functions are conducted in a single large building complex wherein bench scale and pilot scale experiments are carried out involving radionuclides, hazardous air pollutants (HAP), and other chemicals reportable under the Clean Air Act Amendments (CAAA) and Superfund Amendments and Re-authorization Act (SARA) Title 111. The results of the inventory showed that HAP and radionuclide emissions from the laboratory complex were relatively minor

  13. Background information on sources of low-level radionuclide emissions to air

    International Nuclear Information System (INIS)

    Corbit, C.D.; Herrington, W.N.; Higby, D.P.; Stout, L.A.; Corley, J.P.

    1983-09-01

    This report provides a general description and reported emissions for eight low-level radioactive source categories, including facilties that are licensed by the Nuclear Regulatory Commission (NRC) and Agreement States, and non-Department of Energy (DOE) federal facilities. The eight categories of low-level radioactive source facilities covered by this report are: research and test reactors, accelerators, the radiopharmaceutical industry, source manufacturers, medical facilities, laboratories, naval shipyards, and low-level commercial waste disposal sites. Under each category five elements are addressed: a general description, a facility and process description, the emission control systems, a site description, and the radionuclides released to air (from routine operations)

  14. Background information on sources of low-level radionuclide emissions to air

    Energy Technology Data Exchange (ETDEWEB)

    Corbit, C.D.; Herrington, W.N.; Higby, D.P.; Stout, L.A.; Corley, J.P.

    1983-09-01

    This report provides a general description and reported emissions for eight low-level radioactive source categories, including facilties that are licensed by the Nuclear Regulatory Commission (NRC) and Agreement States, and non-Department of Energy (DOE) federal facilities. The eight categories of low-level radioactive source facilities covered by this report are: research and test reactors, accelerators, the radiopharmaceutical industry, source manufacturers, medical facilities, laboratories, naval shipyards, and low-level commercial waste disposal sites. Under each category five elements are addressed: a general description, a facility and process description, the emission control systems, a site description, and the radionuclides released to air (from routine operations).

  15. Monitoring program for evaluating radionuclide emissions from incineration of low-level radioactive waste

    International Nuclear Information System (INIS)

    Wittmer, S.C.; Solomon, H.F.

    1984-01-01

    The implementation of an incineration program for low-level radioactive waste is a complex task, especially in the area of obtaining environmental permits. To provide assurance to the appropriate regulatory agencies involved with environmental permitting and others that an incineration program is properly conducted, emissions monitoring to identify radionuclides and their fate may be needed. An electronic spreadsheet software program Lotus 1-2-3 (Lotus Development Corporation) on an IBM Personal Computer has been used to perform data reduction for test results from such a monitoring program and to present them graphically to facilitate interpretation. The sampling technique includes: (1) the use of an EPA Method 5 stack sampling train modified to exclude the dry-catch filtration assembly with ethanolamine used to scrub incinerator gas at depressed temperatures and (2) a continuous composite liquid sampler for incinerator wet scrubber discharge to the sanitary sewer. Radionuclides in the samples are assayed using scintillation spectrometry

  16. Paving the way to personalized medicine. Production of some theragnostic radionuclides at Brookhaven National Laboratory

    International Nuclear Information System (INIS)

    Srivastava, S.C.

    2011-01-01

    This paper introduces a relatively novel paradigm that involves specific individual radionuclides or radionuclide pairs that have emissions that allow pre-therapy low-dose imaging plus higher-dose therapy in the same patient. We have made an attempt to sort out and organize a number of such theragnostic radionuclides and radionuclide pairs that may potentially bring us closer to the age-long dream of personalized medicine for performing tailored low-dose molecular imaging (SPECT/CT or PET/CT) to provide the necessary pre-therapy information on biodistribution, dosimetry, the limiting or critical organ or tissue, and the maximum tolerated dose (MTD), etc. If the imaging results then warrant it, it would be possible to perform higher-dose targeted molecular therapy in the same patient with the same radiopharmaceutical. A major problem that remains yet to be fully resolved is the lack of availability, in sufficient quantities, of a majority of the best candidate theragnostic radionuclides in a no-carrier-added (NCA) form. A brief description of the recently developed new or modified methods at BNL for the production of four theragnostic radionuclides, whose nuclear, physical, and chemical characteristics seem to show great promise for personalized cancer therapy are described.

  17. Establishing National Carbon Emission Prices for China

    NARCIS (Netherlands)

    C-L. Chang (Chia-Lin); T.K. Mai (Te-Ke); M.J. McAleer (Michael)

    2018-01-01

    textabstractThe purpose of the paper is to establish national carbon emissions prices for the People’s Republic of China, which is one of the world’s largest producers of carbon emissions. Several measures have been undertaken to address climate change in China, including the establishment of a

  18. Methodology for implementation of a national metrology net of radionuclides used in nuclear medicine

    International Nuclear Information System (INIS)

    Santos, Joyra Amaral dos

    2004-01-01

    The National Laboratory for Ionizing Radiation Metrology, of the Institute of Radiation Protection and Dosimetry, of the National Commission on Nuclear Energy (IRD/CNEN), comes leading a comparison program for activity measurements of radiopharmaceuticals administered to patients in the Nuclear Medicine Services (NMS) with the purpose to promote the quality control. This work presents a quality assurance program for the performance of such measurements, evaluated in the comparison runs between hospitals and LNMRI, under the statistic point of view and the compliment of regulatory authority norms. The performance of the radionuclides 67 Ga, 123 I, 131 I, 99m Tc and 210 Tl were evaluated and 201 TI have been standardized by absolute methods. Besides, it was established the traceability of the radioactivity standards used in nuclear medicine and a methodology for implementation of a national metrology net of radionuclides. The comparison results prove that the implementation of a radionuclide metrology net is viable, important and feasible. (author)

  19. Dosimetric characterization of radionuclides for systemic tumor therapy: Influence of particle range, photon emission, and subcellular distribution

    International Nuclear Information System (INIS)

    Uusijaervi, Helena; Bernhardt, Peter; Ericsson, Thomas; Forssell-Aronsson, Eva

    2006-01-01

    Various radionuclides have been proposed for systemic tumor therapy. However, in most dosimetric analysis of proposed radionuclides the charged particles are taken into consideration while the potential photons are ignored. The photons will cause undesirable irradiation of normal tissue, and increase the probability of toxicity in, e.g., the bone marrow. The aim of this study was to investigate the dosimetric properties according to particle range, photon emission, and subcellular radionuclide distribution, of a selection of radionuclides used or proposed for radionuclide therapy, and to investigate the possibility of dividing radionuclides into groups according to their dosimetric properties. The absorbed dose rate to the tumors divided by the absorbed dose rate to the normal tissue (TND) was estimated for different tumor sizes in a mathematical model of the human body. The body was simulated as a 70-kg ellipsoid and the tumors as spheres of different sizes (1 ng-100 g). The radionuclides were either assumed to be uniformly distributed throughout the entire tumor and normal tissue, or located in the nucleus or the cytoplasm of the tumor cells and on the cell membrane of the normal cells. Fifty-nine radionuclides were studied together with monoenergetic electrons, positrons, and alpha particles. The tumor and normal tissue were assumed to be of water density. The activity concentration ratio between the tumor and normal tissue was assumed to be 25. The radionuclides emitting low-energy electrons combined with a low photon contribution, and the alpha emitters showed high TND values for most tumor sizes. Electrons with higher energy gave reduced TND values for small tumors, while a higher photon contribution reduced the TND values for large tumors. Radionuclides with high photon contributions showed low TND value for all tumor sizes studied. The radionuclides studied could be divided into four main groups according to their TND values: beta emitters, Auger electron

  20. Survey of radionuclide emissions from coal-fired power plants and examination of impacts from a proposed circulating fluidized bed boiler power plant

    International Nuclear Information System (INIS)

    Steiner, C.P.; Militana, L.M.; Harvey, K.A.; Kinsey, G.D.

    1995-01-01

    This paper presents the results of a literature survey that examined radionuclide emissions from coal-fired power plants. Literature references from both the US and foreign countries are presented. Emphasis is placed on references from the US because the radionuclide emissions from coal-fired power plants are related to radionuclide concentrations in the coal, which vary widely throughout the world. The radionuclides were identified and quantified for various existing power plants reported in the literature. Applicable radionuclide emissions criteria discovered in the literature search were then applied to a proposed circulating fluidized bed boiler power plant. Based upon the derived radionuclide emission rates applied to the proposed power plant, an air quality modeling analysis was performed. The estimated ambient concentrations were compared to the most relevant existing regulatory ambient levels for radionuclides

  1. Dose assessment from potential radionuclide emissions from stacks on the Hanford Site

    International Nuclear Information System (INIS)

    Davis, W.E.; Barnett, J.M.

    1995-04-01

    On February 3, 1993, the US Department of Energy, Richland Operations Office (RL), received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency (EPA), Region 10. The Compliance Order required RL to (1) evaluate all radionuclide emission points at the Hanford Site to determine which points are subject to the continuous emission sampling requirements of Title 40, Code of Federal Regulations, Part 61 (40 CFR 61), Subpart H, and (2) continuously sample radionuclide emissions in accordance with requirements in 40 CFR 61.93. The Information Request required RL to provide a written Compliance Plan to meet the requirements of the Compliance Order. A Compliance Plan was submitted to EPA, Region 10, on April 30, 1993. The Compliance Plan specified that a dose assessment would be performed for 84 Westinghouse Hanford Company (WHC) stacks registered with the Washington State Department of Health on the Hanford Site. Any stack identified in the assessment as having potential emissions to cause an effective dose equivalent (EDE) to a maximum exposed individual (MEI) greater than 0.1 mrem y -1 must have a compliant sampling system. In addition, a Federal Facility Compliance Agreement (FFCA) was signed on. February 7, 1994. The FFCA required that all unregistered stacks on the Hanford Site be assessed. This requirement increased the number of stacks to be assessed to 123 stacks. Six methods for performing the assessments are described. An initial assessment using only the HEPA filtration factor for back calculations identified 32 stacks that would have emissions which would cause an EDE to the MEI greater than 0.1 mrem y -1 . When the other methods were applied the number was reduced to 20 stacks. The paper discusses reasons for these overestimates

  2. 77 FR 16508 - National Emission Standards for Hazardous Air Pollutant Emissions: Group IV Polymers and Resins...

    Science.gov (United States)

    2012-03-21

    ... National Emission Standards for Hazardous Air Pollutant Emissions: Group IV Polymers and Resins; Pesticide... Hazardous Air Pollutant Emissions: Group IV Polymers and Resins; National Emission Standards for Hazardous... proposed rule titled, National Emission Standards for Hazardous Air Pollutant Emissions: Group IV Polymers...

  3. K and L X-ray emission intensities of some radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Verma, H R; Pal, D [Punjabi Univ., Patiala (India). Dept. of Physics

    1985-01-01

    The K and L x-ray emission intensities per 100 disintegrations have been calculated for some radionuclides using the latest adopted data for gamma-ray intensities, electron capture and internal conversion coefficients for the parent nuclides, fluorescence yield values, Coster-Kronig transition probabilities, average total number of primary L shell vacancies produced in the decay of K shell vacancies and emission rates for various shells and subshells for the daughter nuclei. The results are in good agreement with theoretical and experimental values for the K x-ray intensities. There are no experimental results available to compare with the present calculations for the L x-ray intensities; however, there is a marked discrepancy in the L..cap alpha.. and L..beta.. intensities available on the basis of theoretical estimates.

  4. National Low-Level Waste Management Program Radionuclide Report Series, Volume 17: Plutonium-239

    International Nuclear Information System (INIS)

    Adams, J.P.; Carboneau, M.L.

    1999-01-01

    This report, Volume 17 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of plutonium-239 (Pu-239). This report also discusses waste types and forms in which Pu-239 can be found, waste and disposal information on Pu-239, and Pu-239 behavior in the environment and in the human body

  5. National Low-Level Waste Management Program Radionuclide Report Series, Volume 17: Plutonium-239

    Energy Technology Data Exchange (ETDEWEB)

    J. P. Adams; M. L. Carboneau

    1999-03-01

    This report, Volume 17 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of plutonium-239 (Pu-239). This report also discusses waste types and forms in which Pu-239 can be found, waste and disposal information on Pu-239, and Pu-239 behavior in the environment and in the human body.

  6. National Low-Level Waste Management Program radionuclide report series. Volume 13, Curium-242

    International Nuclear Information System (INIS)

    Adams, J.P.

    1995-08-01

    This report, Volume 13 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of curium-242 ( 242 Cm). This report also includes discussions about waste types and forms in which 242 Cm can be found and 242 Cm behavior in the environment and in the human body

  7. National low-level waste management program radionuclide report series, Volume 14: Americium-241

    International Nuclear Information System (INIS)

    Winberg, M.R.; Garcia, R.S.

    1995-09-01

    This report, Volume 14 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of americium-241 ( 241 Am). This report also includes discussions about waste types and forms in which 241 Am can be found and 241 Am behavior in the environment and in the human body

  8. National Low-Level Waste Management Program radionuclide report series. Volume 13, Curium-242

    Energy Technology Data Exchange (ETDEWEB)

    Adams, J.P.

    1995-08-01

    This report, Volume 13 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of curium-242 ({sup 242}Cm). This report also includes discussions about waste types and forms in which {sup 242}Cm can be found and {sup 242}Cm behavior in the environment and in the human body.

  9. Potential radionuclide emissions from stacks on the Hanford Site. Part 1: Dose assessment

    International Nuclear Information System (INIS)

    Davis, W.E.; Barnett, J.M.

    1994-06-01

    On February 3, 1993, the US Department of Energy, Richland Operations Office (RL) received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency (EPA), Region 10. The Compliance Plan specified that a dose assessment would be performed for 84 Westinghouse Hanford Company (WHC) stacks registered with the Washington State Department of Health (WAC 246-247) on the Hanford Site. Stacks that have the potential emissions to cause an effective dose equivalent (EDE) to a maximum exposed individual (MEI) greater than 0.1 mrem y -1 must be monitored continuously for radionuclide emissions. Five methods were approved by EPA, Region 10 for performing the assessments: Release Fractions from Appendix D of 40 CFR 61, Back Calculations Using A HEPA Filtration Factor, Nondestructive Assay of HEPA Filters, A Spill Release Fraction, and Upstream of HEPA Filter Air Concentrations. The first two methods were extremely conservative for estimating releases. The third method which used a state-of-the-art portable gamma spectrometer, yielded surprising results from the distribution of radionuclides on the HEPA filters. All five methods are described

  10. Contributions by emissions from nuclear installations to concentrations of radionuclides in milk

    CERN Document Server

    Green, N

    1983-01-01

    A year-long study has been carried out to determine whether milk produced near nuclear sites contains concentrations of radionuclides that can be attributed to discharges from the installations, and, as a consequence, whether there is enhanced exposure of those members of the public who consume this milk. Eight creameries were chosen and monthly samples of milk were taken for analysis. The concentrations of caesium-137 and strontium-90 were measured and compared with results from a national survey conducted as part of the Board's environmental radioactivity surveillance programme. No effect attributable to discharges from the nuclear establishments was identified. The activity concentrations ranged between 0.1 and 3 times the national average; the variation relates mainly to rainfall in the area, although other factors may also have an effect. However, milk contributes only a small fraction of the total dietary intake of caesium-137 and strontium-90, and so the exposure of persons consuming the milk varies on...

  11. Biological hazards of radioactivity and the biological consequences of radionuclide emissions from routine operation of nuclear power reactors

    International Nuclear Information System (INIS)

    Stendig-Lindberg, G.

    1978-01-01

    The biological hazards of radioactivity and the biological consequences of radionuclide emissions from the routine operation of nuclear power reactors are reviewed. ICRP and Scandinavian recommendations for the limitation of annual radiation doses are presented. The contribution of environmental conditions to radiation hazard is also discussed. It is concluded that a review of the justification of nuclear power is urgently needed. (H.K.)

  12. Basis to demonstrate compliance with the National Emission Standards for Hazardous Air Pollutants for the Stand-off Experiments Range

    Energy Technology Data Exchange (ETDEWEB)

    Michael Sandvig

    2011-01-01

    The purpose of this report is to provide the basis and the documentation to demonstrate general compliance with the National Emission Standard for Hazardous Air Pollutants (NESHAPS) 40 CFR 61 Subpart H, “National Emission Standards for Emissions of Radionuclides Other Than Radon from Department of Energy Facilities,” (the Standard) for outdoor linear accelerator operations at the Idaho National Laboratory (INL) Stand-off Experiments Range (SOX). The intent of this report is to inform and gain acceptance of this methodology from the governmental bodies regulating the INL.

  13. National Emission Standards for Hazardous Air Pollutants

    International Nuclear Information System (INIS)

    Grossman, Robert F.

    2005-01-01

    The sources of radionuclides include current and previous activities conducted on the NTS. The NTS was the primary location for testing of nuclear explosives in the Continental U.S. between 1951 and 1992. Historical testing has included (1) atmospheric testing in the 1950s and early 1960s, (2) underground testing between 1951 and 1992, and (3) open-air nuclear reactor and rocket engine testing (DOE, 1996a). No nuclear tests have been conducted since September 23,1992 (DOE, 2000), however; radionuclides remaining on the soil surface in many NTS areas after several decades of radioactive decay are re-suspended into the atmosphere at concentrations that can be detected by air sampling. Limited non-nuclear testing includes spills of hazardous materials at the Non-Proliferation Test and Evaluation Complex (formerly called the Hazardous Materials Spill Center), private technology development, aerospace and demilitarization activities, and site remediating activities. Processing of radioactive materials is limited to laboratory analyses; handling, transport, storage, and assembly of nuclear explosive devices or radioactive targets for the Joint Actinide Shock Physics Experimental Research (JASPER) gas gun; and operation of radioactive waste management sites (RWMSs) for low-level radioactive and mixed waste (DOE, 1996a). Monitoring and evaluation of the various activities conducted onsite indicate that the potential sources of offsite radiation exposure in calendar year (CY) 2004 were releases from (1) evaporation of tritiated water (HTO) from containment ponds that receive drainage water from E Tunnel in Area 12 and water pumped from wells used to characterize the aquifers at the sites of past underground nuclear tests, (2) onsite radioanalytical laboratories, (3) the Area 3 and Area 5 RWMS facilities, and (4) diffuse sources of tritium (H 3 ) and re-suspension of plutonium ( 239+240 Pu) and americium ( 241 Am) at the sites of past nuclear tests. The following sections

  14. Radionuclide toxicity

    International Nuclear Information System (INIS)

    Galle, P.

    1982-01-01

    The aim of this symposium was to review the radionuclide toxicity problems. Five topics were discussed: (1) natural and artificial radionuclides (origin, presence or emission in the environment, human irradiation); (2) environmental behaviour of radionuclides and transfer to man; (3) metabolism and toxicity of radionuclides (radioiodine, strontium, rare gas released from nuclear power plants, ruthenium-activation metals, rare earths, tritium, carbon 14, plutonium, americium, curium and einsteinium, neptunium, californium, uranium) cancerogenous effects of radon 222 and of its danghter products; (4) comparison of the hazards of various types of energy; (5) human epidemiology of radionuclide toxicity (bone cancer induction by radium, lung cancer induction by radon daughter products, liver cancer and leukaemia following the use of Thorotrast, thyroid cancer; other site of cancer induction by radionuclides) [fr

  15. Preparation and characterization of radionuclide 64Cu for positron emission tomographic diagnosis and therapy

    International Nuclear Information System (INIS)

    Ometakova, J.

    2013-01-01

    We occupy ourselves with preparation of 64 Cu using cyclotron IBA 18/9. 64 Cu is a starting product for production of radiopharmaceuticals for positron emission tomographic diagnostics and therapy and metrological characterization as well. The use of non-traditional PET radionuclides has been spread in the world recently. Due to the physical properties (T 1/2 =12.7 h, β- 37.1 %, β + 17.9 %), 64 Cu is suitable for therapy (β - ) and diagnosing as well (β+). 64 Cu is suitable radionuclide for labeling of radiopharmaceuticals on the basis of bis-thiosemicarbazone for study of hypoxic tumors. The number and orientation of articles and papers at conferences show a great demand for 64 Cu in the world. It is caused by specific physical properties and possibility of preparation in small biomedical cyclotrons as well. An electrolytic preparation of a target lies in a galvanostatic plating of 64 Ni on a gold target. The target is irradiated by a cyclotron IBA Cyclone 18/9. COSTIS station (Compact Solid Target Irradiation System) is installed at the end of external proton beam. 64 Cu is separated from the target material by ionex Bio-Rad AG1-X8 as [ 64 Cu]CuCl 2 . The target material is recycled by a simple method. A process of 64 Cu preparation is completely automated and runs in a separation module with Plc Simatin S-1200 developed by Biont a.s. The product was measured by an ionization chamber (Curiementor), HPGe detector and LSC method (TDCR). (author)

  16. Preparation and characterization of radionuclide 64Cu for positron emission tomographic diagnosis and therapy

    International Nuclear Information System (INIS)

    Ometakova, J.

    2013-01-01

    We occupy ourselves with preparation of 64 Cu using cyclotron IBA 18/9. 64 Cu is a starting product for production of radiopharmaceuticals for positron emission tomographic diagnostics and therapy and metrological characterization as well. The use of non-traditional PET radionuclides has been spread in the world recently. Due to the physical properties (T 1/2 =12.7 h, β- 37.1 %, β + 17.9 %), 64 Cu is suitable for therapy (β - ) and diagnosing as well (β+). 64 Cu is suitable radionuclide for labeling of radiopharmaceuticals on the basis of bis-thiosemicarbazone for study of hypoxic tumors. The number and orientation of articles and papers at conferences show a great demand for 64 Cu in the world. It is caused by specific physical properties and possibility of preparation in small biomedical cyclotrons as well. An electrolytic preparation of a target lies in a galvanostatic plating of 64 Ni on a gold target. The target is irradiated by a cyclotron IBA Cyclone 18/9. COSTIS station (Compact Solid Target Irradiation System) is installed at the end of external proton beam. 64 Cu is separated from the target material by ionex Bio-Rad AG1-X8 as [ 64 Cu]CuCl 2 . The target material is recycled by a simple method. A process of 64 Cu preparation is completely automated and runs in a separation module with PLC SIMATIC S7-1200 developed by Biont a.s. The product was measured by an ionization chamber (Curiementor), HPGe detector and LSC method (TDCR). (author)

  17. Radionuclide Emission Estimation for the Center for Advanced Energy Studies (CAES)

    International Nuclear Information System (INIS)

    Schrader, Bradley J.

    2010-01-01

    An Radiological Safety Analysis Computer Program (RSAC)-7 model dose assessment was performed to evaluate maximum Center for Advanced Energy Studies (CAES) boundary effective dose equivalent (EDE, in mrem/yr) for potential individual releases of radionuclides from the facility. The CAES is a public/private partnership between the State of Idaho and its academic research institutions, the federal government through the U.S. Department of Energy (DOE), and the Idaho National Laboratory (INL) managed by the Battelle Energy Alliance (BEA). CAES serves to advance energy security for our nation by expanding educational opportunities at Idaho universities in energy-related areas, creating new capabilities within its member institutions, and delivering technological innovations leading to technology-based economic development for the intermountain region. CAES has developed a strategic plan (INL/EXT-07-12950) based on the balanced scorecard approach. At the present time it is unknown exactly what processes will be used in the facility in support of this strategic plan. What is known is that the Idaho State University (ISU) Radioactive Materials License (Nuclear Regulatory Commission (NRC) license 11-27380-01) is the basis for handling radioactive material in the facility. The material in this license is shared between the ISU campus and the CAES facility. There currently are no agreements in place to limit the amount of radioactive material at the CAES facility or what is done to the material in the facility. The scope of this analysis is a summary look at the basis dose for each radionuclide included under the license at a distance of 100, 500, and 1,000 m. Inhalation, ingestion and ground surface dose was evaluated using the NRC design basis guidelines. The results can be used to determine a sum of the fractions approach to facility safety. This sum of the fractions allows a facility threshold value (TV) to be established and potential activities to be evaluated against

  18. National Low-Level Waste Management Program radionuclide report series. Volume 2, Niobium-94

    International Nuclear Information System (INIS)

    Adams, J.P.; Carboneau, M.L.

    1995-04-01

    The Purpose of the National Low-Level Waste Management Program Radionuclide Report Series is to provide information to, state representatives and developers of low-level radioactive waste disposal facilities about the radiological chemical, and physical characteristics of selected radionuclides and their behavior in the low-level radioactive waste disposal facility environment. Extensive surveys of available literature provided information used to produce this series of reports and an introductory report. This report is Volume 11 of the series. It outlines the basic radiological, chemical, and physical characteristics of niobium-94, waste types and forms that contain it, and its behavior in environmental media such as soils, plants, groundwater, air, animals and the human body

  19. Towards Verifying National CO2 Emissions

    Science.gov (United States)

    Fung, I. Y.; Wuerth, S. M.; Anderson, J. L.

    2017-12-01

    With the Paris Agreement, nations around the world have pledged their voluntary reductions in future CO2 emissions. Satellite observations of atmospheric CO2 have the potential to verify self-reported emission statistics around the globe. We present a carbon-weather data assimilation system, wherein raw weather observations together with satellite observations of the mixing ratio of column CO2 from the Orbiting Carbon Observatory-2 are assimilated every 6 hours into the NCAR carbon-climate model CAM5 coupled to the Ensemble Kalman Filter of DART. In an OSSE, we reduced the fossil fuel emissions from a country, and estimated the emissions innovations demanded by the atmospheric CO2 observations. The uncertainties in the innovation are analyzed with respect to the uncertainties in the meteorology to determine the significance of the result. The work follows from "On the use of incomplete historical data to infer the present state of the atmosphere" (Charney et al. 1969), which maps the path for continuous data assimilation for weather forecasting and the five decades of progress since.

  20. An exposure assessment of radionuclide emissions associated with potential mixed-low level waste disposal facilities at fifteen DOE sites

    International Nuclear Information System (INIS)

    Lombardi, D.A.; Socolof, M.L.

    1996-01-01

    A screening method was developed to compare the doses received via the atmospheric pathway at 15 potential DOE MLLW (mixed low-level waste) sites. Permissible waste concentrations were back calculated using the radioactivity NESHAP (National Emissions Standards for Hazardous Air Pollutants) in 40 FR 61 (DOE Order 5820.2A performance objective). Site-specific soil and meteorological data were used to determine permissible waste concentrations (PORK). For a particular radionuclide, perks for each site do not vary by more than one order of magnitude. perks of 14 C are about six orders of magnitude more restrictive than perks of 3 H because of differences in liquid/vapor partitioning, decay, and exposure dose. When comparing results from the atmospheric pathway to the water and intruder pathways, 14 C disposal concentrations were limited by the atmospheric pathway for most arid sites; for 3 H, the atmospheric pathway was not limiting at any of the sites. Results of this performance evaluation process are to be used for planning for siting of disposal facilities

  1. The activity of selected gamma radionuclides in the Tatra National Park

    Directory of Open Access Journals (Sweden)

    Kubica Barbara

    2017-01-01

    Full Text Available Cesium is naturally occurring active metal, represented by one stable isotope 133Cs, and number of artificial, unstable, isotopes. The most common artificial isotope of cesium is 137Cs, present in the environment of the Tatra Mountains due to nuclear weapon testing in late `50, and nuclear reactor accident in Chernobyl in 1986. However in recent years the growth in biofuels use for power generation can be the next source of 137Cs emission. Burning wood cultivated on grounds contaminated by 137Cs can introduce secondary emission of this isotope to the atmosphere.This paper presents the results of determination of gamma emitting radionuclides artificial 137Cs and natural 40K in soil samples from the Tatra Mountains. Results show some differences in the vertical distribution of examined radionuclides. It was found that the change of activity of 137Cs in the soil samples depends mostly on the soil density and on the concentration of organic material. The state of “zero” 137Cs activity was developed in the form of maps.

  2. Radionuclides in bats using a contaminated pond on the Nevada National Security Site, USA

    International Nuclear Information System (INIS)

    Warren, Ronald W.; Hall, Derek B.; Greger, Paul D.

    2014-01-01

    Perched groundwater percolating through radionuclide contamination in the E Tunnel Complex on the Nevada National Security Site, formerly the Nevada Test Site, emerges and is stored in a series of ponds making it available to wildlife, including bats. Since many bat species using the ponds are considered sensitive or protected/regulated and little information is available on dose to bats from radioactive water sources, bats were sampled to determine if the dose they were receiving exceeded the United States Department of Energy dose limit of 1.0E-3 Gy/day. Radionuclide concentrations in water, sediment, and flying insects were also measured as input parameters to the dose rate model and to examine trophic level relationships. The RESRAD-Biota model was used to calculate dose rates to bats using different screening levels. Efficacy of RESRAD-Biota and suggested improvements are discussed. Dose to bats foraging and drinking at these ponds is well below the dose limit set to protect terrestrial biota populations. - Highlights: • Bats uptake radionuclides from a contaminated pond. • Tritium had highest concentrations but 137 Cs gave highest dose. • Tritium concentrations in bats are approximately one-twentieth of that in the pond. • Population level effects are not expected based on RESRAD-Biota dose estimates. • It may be more appropriate to model the bats as riparian animals in RESRAD-Biota

  3. 76 FR 13851 - National Emission Standards for Hazardous Air Pollutants: Mercury Emissions From Mercury Cell...

    Science.gov (United States)

    2011-03-14

    ... National Emission Standards for Hazardous Air Pollutants: Mercury Emissions From Mercury Cell Chlor-Alkali...-5] RIN 2060-AN99 National Emission Standards for Hazardous Air Pollutants: Mercury Emissions From Mercury Cell Chlor-Alkali Plants AGENCY: Environmental Protection Agency (EPA). ACTION: Supplemental...

  4. Investigations of the emission of radionuclides from coal fired power plants

    International Nuclear Information System (INIS)

    Chatterjee, B.; Hoetzl, H.; Rosner, G.; Winkler, R.

    1980-02-01

    Samples of coal, brown coal, bottom ash, collected fly ash and 4 sieve fractions of collected fly ash from various electrostatic filter stages as well as samples of escaping fly ash, all taken simultaneously on 3 operating-days, have been investigated. In samples from coal through fly ash sieve fractions U-238, Th-232, Ra-226, Pb-210 and K-40 have been determined by γ-spectrometry, Po-210 by chemical separation with subsequent α-spectrometry. In escaping fly ash samples, which are available in small amounts only (ca. 1 g or less), after chemical separation U-238, U-234, Th-232, Th-230, Th-228 and Po-210 were determined by α-spectrometry and Pb-210 by low-level β-counting. Furthermore, Po-210 has been determined by direct α-spectrometry in several particle size fractions collected with a cascade impactor from the exhaust stream. The analytical procedures, which partially had to be developed for the purposes of the present study, are presented shortly. Specific activities of escaping fly ash are in good agreement with specific activities of the fly ash collected from the last electrostatic precipitator stage, provided that, for the latter, the particle size distribution in escaping fly ash is taken into account. Using these specific activities annual air-borne radionuclide emissions are calculated. The resulting activity concentrations in ground level air are compared to values of natural radioactivity. (orig./HP) [de

  5. Monte Carlo calculation of correction factors for radionuclide neutron source emission rate measurement by manganese bath method

    International Nuclear Information System (INIS)

    Li Chunjuan; Liu Yi'na; Zhang Weihua; Wang Zhiqiang

    2014-01-01

    The manganese bath method for measuring the neutron emission rate of radionuclide sources requires corrections to be made for emitted neutrons which are not captured by manganese nuclei. The Monte Carlo particle transport code MCNP was used to simulate the manganese bath system of the standards for the measurement of neutron source intensity. The correction factors were calculated and the reliability of the model was demonstrated through the key comparison for the radionuclide neutron source emission rate measurements organized by BIPM. The uncertainties in the calculated values were evaluated by considering the sensitivities to the solution density, the density of the radioactive material, the positioning of the source, the radius of the bath, and the interaction cross-sections. A new method for the evaluation of the uncertainties in Monte Carlo calculation was given. (authors)

  6. Summary of proposed approach for deriving cleanup guidelines for radionuclides in soil at Brookhaven National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Meinhold, A.F.; Morris, S.C.; Dionne, B.; Moskowitz, P.D.

    1996-11-01

    Past activities at Brookhaven National Laboratory (BNL) resulted in soil and groundwater contamination. As a result, BNL was designated a Superfund site under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). BNL`s Office of Environmental Restoration (OER) is overseeing environmental restoration activities at the Laboratory, carried out under an Interagency Agreement (IAG) with the United States Department of Energy (DOE), the United States Environmental Protection Agency (EPA) and the New York State Department of Environmental Conservation (NYSDEC). The objective of this paper is to propose a standard approach to deriving risk-based cleanup guidelines for radionuclides in soil at BNL.

  7. Summary of proposed approach for deriving cleanup guidelines for radionuclides in soil at Brookhaven National Laboratory

    International Nuclear Information System (INIS)

    Meinhold, A.F.; Morris, S.C.; Dionne, B.; Moskowitz, P.D.

    1996-11-01

    Past activities at Brookhaven National Laboratory (BNL) resulted in soil and groundwater contamination. As a result, BNL was designated a Superfund site under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA). BNL's Office of Environmental Restoration (OER) is overseeing environmental restoration activities at the Laboratory, carried out under an Interagency Agreement (IAG) with the United States Department of Energy (DOE), the United States Environmental Protection Agency (EPA) and the New York State Department of Environmental Conservation (NYSDEC). The objective of this paper is to propose a standard approach to deriving risk-based cleanup guidelines for radionuclides in soil at BNL

  8. Profitability of applications of radionuclides and ionizing radiation in national economy

    International Nuclear Information System (INIS)

    Jankowski, L.

    1983-01-01

    The economic importance is underlined of applications of radionuclides and ionizing radiation based on the results of numerous studies conducted especially within the framework of CMEA. Fields of activity are listed in which interesting results have been achieved. Concrete data on investments and financial benefits, including improved technical and technological standards and product quality, are given. Examples are given to show that the applied techniques belong among the most important factors for intensifying the development of the national economy with quick return of invested means. (author)

  9. Air Emission Inventory for the Idaho National Engineering and Environmental Laboratory - Calendar Year 1999 Emission Report

    Energy Technology Data Exchange (ETDEWEB)

    Zohner, S.K.

    2000-05-30

    This report presents the 1999 calendar year update of the Air Emission Inventory for the Idaho National Engineering and Environmental Laboratory (INEEL). The INEEL Air Emission Inventory documents sources and emissions of nonradionuclide pollutants from operations at the INEEL. The report describes the emission inventory process and all of the sources at the INEEL, and provides nonradionuclide emissions estimates for stationary sources.

  10. Air Emission Inventory for the Idaho National Engineering and Environmental Laboratory - Calendar Year 1998 Emissions Report

    Energy Technology Data Exchange (ETDEWEB)

    S. K. Zohner

    1999-10-01

    This report presents the 1998 calendar year update of the Air Emission Inventory for the Idaho National Engineering and Environmental Laboratory (INEEL). The INEEL Air Emission Inventory documents sources and emissions of nonradionuclide pollutants from operations at the INEEL. The report describes the emission inventory process and all of the sources at the INEEL, and provides nonradiological emissions estimates for stationary sources.

  11. Vegetation fires, smoke emissions, and dispersion of radionuclides in the chernobyl exclusion zone

    Science.gov (United States)

    Wei Min Hao; Oleg O. Bondarenko; Sergiy Zibtsev; Diane Hutton

    2009-01-01

    The accident of the Chernobyl nuclear power plant (ChNPP) in 1986 was probably the worst environmental disaster in the past 30 years. The fallout and accumulation of radionuclides in the soil and vegetation could have long-term impacts on the environment. Radionuclides released during large, catastrophic vegetation fires could spread to continental Europe, Scandinavia...

  12. Air Quality Modelling and the National Emission Database

    DEFF Research Database (Denmark)

    Jensen, S. S.

    The project focuses on development of institutional strengthening to be able to carry out national air emission inventories based on the CORINAIR methodology. The present report describes the link between emission inventories and air quality modelling to ensure that the new national air emission...... inventory is able to take into account the data requirements of air quality models...

  13. Radionuclide contaminant analysis of small mammals at Area G, TA-54, Los Alamos National Laboratory, 1995

    International Nuclear Information System (INIS)

    Bennett, K.; Biggs, J.; Fresquez, P.

    1997-01-01

    At Los Alamos National Laboratory, small mammals were sampled at two waste burial sites (Site 1-recently disturbed and Site 2-partially disturbed) at Area G, Technical Area 54 and a control site on Frijoles Mesa (Site 4) in 1995. Our objectives were (1) to identify radionuclides that are present within surface and subsurface soils at waste burial sites, (2) to compare the amount of radionuclide uptake by small mammals at waste burial sites to a control site, and (3) to identify if the primary mode of contamination to small mammals is by surface contact or ingestion/inhalation. Three composite samples of at least rive animals per sample were collected at each site. Pelts and carcasses of each animal were separated and analyzed independently. Samples were analyzed for 241 Am, 90 Sr , 238 Pu, 239 Pu, total U, 137 Cs, and 3 H. Significantly higher (parametric West at p=0.05) levels of total U, 241 Am, 238 Pu and 239 Pu were detected in pelts than in carcasses of small mammals at TA-54. Concentrations of other measured radionuclides in carcasses were nearly equal to or exceeded the mean concentrations in the pelts. Our results show higher concentrations in pelts compared to carcasses, which is similar to what has been found at waste burial/contaminated sites outside of Los Alamos National Laboratory. Site 1 had a significantly higher (alpha=0.05, P=0.0125) mean tritium concentration in carcasses than Site 2 or Site 4. In addition Site 1 also had a significantly higher (alpha=0.05, p=0.0024) mean tritium concentration in pelts than Site 2 or Site 4. Site 2 had a significantly higher (alpha=0.05, P=0.0499) mean 239 Pu concentration in carcasses than either Site 1 or Site 4

  14. National Emission Standards for Hazardous Air Pollutants Calendar Year 2005

    International Nuclear Information System (INIS)

    Bechtel Nevada

    2006-01-01

    The Nevada Test Site (NTS) is operated by the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). From 1951 through 1992, the NTS was operated as the nation's site for nuclear weapons testing. The release of man-made radionuclides from the NTS as a result of testing activities has been monitored since the first decade of atmospheric testing. After 1962, when nuclear tests were conducted only underground, the radiation exposure to the public surrounding the NTS was greatly reduced. After the 1992 moratorium on nuclear testing, radiation monitoring on the NTS focused on detecting airborne radionuclides that are resuspended into the air (e.g., by winds, dust-devils) along with historically-contaminated soils on the NTS. To protect the public from harmful levels of man-made radiation, the Clean Air Act, National Emission Standards for Hazardous Air Pollutants (NESHAP) (40 Code of Federal Regulations 61 Subpart H) limits the release of radioactivity from a U. S. Department of Energy (DOE) facility (e.g., the NTS) to 10 millirem per year (mrem/yr) effective dose equivalent (EDE) to any member of the public. This is the dose limit established for someone living off of the NTS for inhaling radioactive particles that may be carried by wind off of the NTS. This limit assumes that members of the public surrounding the NTS may also inhale 'background levels' or radioactive particles unrelated to NTS activities that come from naturally-occurring elements in the environment (e.g., radon gas from the earth or natural building materials) or from other man-made sources (e.g., cigarette smoke). The U. S. Environmental Protection Agency (EPA) requires DOE facilities (e.g., the NTS) to demonstrate compliance with the NESHAP dose limit by annually estimating the dose to a hypothetical member of the public, referred to as the maximally exposed individual (MEI), or the member of the public who resides within an 80-kilometer (50-mile) radius

  15. Emission, transport, deposition, and re-suspension of radionuclides from Fukushima Dai-ichi Nuclear Power Plant in the atmosphere - Overview of 2-year investigations in Japan

    Science.gov (United States)

    Kita, Kazuyuki; Igarashi, Yasuhiro; Yoshida, Naohiro; Nakajima, Teruyuki

    2013-04-01

    Following a huge earthquake and tsunami in Eastern Japan on 11 March, 2011, the accident in Fukushima Dai-ichi Nuclear Power Plant (FDNPP) occurred to emit a large amount of artificial radionuclides to the environment. Soon after the FDNPP accident, many Japanese researchers, as well as researchers in other countries, started monitoring radionuclides in various environmental fields and/or model calculations to understand extent and magnitude of radioactive pollution. In this presentation, we overview these activities for the atmospheric radionuclides in Japan as followings: 1. Investigations to evaluate radionuclide emissions by explosions at FNDPP in March 2011 and to estimate the respiration dose of the radiation at this stage. 2. Investigations to evaluate atmospheric transport and deposition processes of atmospheric radionuclide to determine the extent of radionuclide pollution. -- Based on results of the regular and urgent monitoring results, as well as the mapping of the distribution of radionuclide s accumulated by the deposition to the ground, restoration of their time-dependent emission rates has been tried, and processes determining atmospheric concentration and deposition to the ground have been investigated by using the model calculations. 3. Monitoring of the atmospheric concentrations of radionuclide after the initial, surge phase of FNDPP accident. 4. Investigations to evaluate re-suspension of radionuclide from the ground, including the soil and the vegetation. -- Intensive monitoring of the atmospheric concentrations and deposition amount of radionuclide after the initial, surge phase of the accident enable us to evaluate emission history from FNDPP, atmospheric transport and deposition processes, chemical and physical characteristics of atmospheric radionuclide especially of radio cesium, and re-suspension processes which has become dominant process to supply radio cesium to the atmosphere recently.

  16. Radionuclide contaminant analysis of rodents at a waste burial site, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Biggs, J.R.; Bennett, K.D.; Fresquez, P.R.

    1996-01-01

    Small mammals were sampled at two waste burial sites (Sites 1 and 2) at Area G, TA-54, and a control site outside Area G (Site 3) to identify radionuclides that are present within surface and subsurface soils at waste burial sites, to compare the amount of radionuclide uptake by small mammals at waste burial sites to a control site, and to identify the primary mode of contamination to small mammals, either through surface contact or ingestion/inhalation. Three composite samples of at least five animals per sample were collected at each site. Pelts and carcasses of each animal were separated and analyzed independently. Samples were analyzed for americium ( 241 Am), strontium ( 90 Sr), plutonium ( 238 Pu and 239 Pu), total uranium (U), and examined by gamma spectroscopy (including cesium [ 137 Cs]). Significantly higher (parametric t-test at p = 0.05) levels of total U, 241 Am, 238 Pu, and potassium ( 40 K) were detected in pelts as compared to the carcasses of small mammals at TA-54. Concentrations of other measured radionuclides in carcasses were nearly equal to or exceeded the mean concentrations in the pelts. The results show higher concentrations in pelts compared to carcasses which is similar to what has been found at waste burial/contaminated sites outside of Los Alamos National Laboratory. Site 1 had significantly higher (alpha = 0.05, P = 0.0095) total U concentrations in carcasses than Sites 2 and 3. Site 2 had significantly higher (alpha = 0.05, P = 0.0195) 239 Pu concentrations in carcasses than either Site 1 or Site 3

  17. National emissions from tourism: An overlooked policy challenge?

    International Nuclear Information System (INIS)

    Gössling, Stefan

    2013-01-01

    Tourism has been recognized as a significant greenhouse gas (GHG) emissions sector on a global scale. Yet, only few studies assess tourism's share in national emissions. This paper compares and analyses existing inventories of national emissions from tourism. Studies are difficult to compare, because they use different system boundaries and allocation principles, omitting or including lifecycle emissions and GHG other than CO 2 . By outlining and analysing these differences, the paper estimates the contribution made by tourism to national emissions, and its greenhouse gas intensity in comparison to other economic sectors. Results indicate that while emissions from tourism are significant in all countries studied, they may, in some countries, exceed ‘official' emissions as calculated on the basis of guidelines for national emission inventories under the Kyoto Protocol. This is a result of the fact that bunker fuels are not considered in national GHG inventories, leading to underestimates of the energy- and GHG intensity of tourism economies. While further growth in tourism emissions can be expected in all countries studied, energy-related vulnerabilities are already considerable in many of these. Climate policy for tourism, on the other hand, is largely non-existent, calling for immediate action to consider this sector in national legislation. - Highlights: • Emissions from tourism are equivalent to 5–150% of ’official’ national emissions. • Inconsistent methods are used to calculate national tourism emissions. • Tourism is an energy-intense economic sector compared to other sectors. • Emissions from tourism are growing rapidly. • National policy is not concerned with tourism-related emissions

  18. Secondary Aluminum Production: National Emission Standards for Hazardous Air Pollutants

    Science.gov (United States)

    National emission standards for hazardous air pollutants (NESHAP) for new and existing sources at secondary aluminum production facilities. Includes rule history, summary, federal register citations and implementation information.

  19. Radionuclide concentrations in vegetation at the Los Alamos National Laboratory in 1998

    International Nuclear Information System (INIS)

    Gonzales, G.J.; Fresquez, P.R.; Mullen, M.A.; Naranjo, L. Jr.

    2000-01-01

    This report summarizes and evaluates the concentrations of 3 H, 137 Cs, 238 Pu, 239,240 Pu, 241 Am, 90 Sr, and total U in understory and overstory vegetation collected from Los Alamos National Laboratory (LANL), its perimeter, and regional background areas in 1998. Comparisons to conservative toxicity reference value safe limits were also made. The arithmetic mean LANL radionuclide concentrations in understory were 501 pCi L -1 for 3 H, 0.581 pCi ash g -1 for 137 Cs, 0.001 pCi ash g -1 for 238 Pu, 0.008 pCi ash g -1 for 239,240 Pu, 0.007 pCi ash g -1 for 241 Am, 1.46 pCi ash g -1 for 90 Sr, and 0.233 microg ash g -1 for total uranium. The mean LANL radionuclide concentrations in overstory were 463 pCi L -1 for 3 H, 1.51 pCi ash g -1 for 137 Cs, 0.0004 pCi ash g -1 238 Pu, 0.008 pCi ash g -1 for 239,240 Pu, 0.014 pCi ash g -1 for 241 Am, 1.97 pCi ash g -1 for 90 Sr, and 0.388 microg ash g -1 for total uranium. Concentrations of radionuclides and total U in both understory and overstory vegetation at LANL generally were not statistically higher than in perimeter and regional background vegetation (α = 0.05). The exceptions were LANL 3 H > perimeter 3 H (understory) and LANL 3 H background 3 H (overstory). All maximum radionuclide concentrations were lower than toxicity reference values. With the exception of total U, the relationship between contaminant concentration in soil vs. vegetation was insignificant (α = 0.05). Generally, as the concentration of total U in soil decreased, the concentration in vegetation increased. This held true for both understory and overstory and regardless of whether data were separated by general location (LANL, perimeter, and background) or not. There was no apparent relationship between contaminant concentrations in understory vs. overstory

  20. Transuranium radionuclide pollution in the waters of the La Maddalena National Marine Park

    International Nuclear Information System (INIS)

    Aumento, F.; Le Donne, K.; Eroe, K.

    2005-01-01

    Following the grounding and subsequent explosion, in October 2003, of a nuclear submarine in the waters of the La Maddalena National Marine Park, fears arose of possible radioactive leakages. However, isotopic analyses on algae showed that the gamma-ray emitting artificial radionuclides that one might expect to leak from a damaged nuclear reactor (such as U-235, I-131, Cs-137) were absent, and that U-238/U-234 activities were in equilibrium with values typical of sea water; this excluded any direct anthropogenic contamination as a result of the accident. We used alpha autoradiographic techniques to detect possible traces of transuranium radionuclides; 160 samples of algae, granites, sea urchins, gastropods, limpets, cuttlefish and jellyfish were collected from the area, as well as from other Mediterranean coastlines and the Baltic Sea. All samples were autoradiographed, and selected samples further analysed by alpha spectrometry. There were no alpha track concentrations above background levels in our control Mediterranean specimens. In the samples from the La Maddalena and Baltic areas two different track distributions were observed:-those homogeneously distributed over the surfaces examined; -groups (10 to over 500) of radially distributed alpha tracks (forming 'star' bursts, or 'hot spots') emanating from point sources. By comparing radionuclide activities measured by alpha spectroscopy with alpha track densities, we extrapolated Pu activities for all samples. About 74% of algae had Pu activities of less than 1Bq/kg and 0.25Bq/kg, 16% had accumulated Pu to levels between 1 and 2Bq/kg, and a very few specimens had concentrations between 2 and 6Bq/kg. Plots showed that alpha tracks and stars concentrate around the northern and eastern margins of the Rada (Basin) di Santo Stefano, sites facing the nuclear submarine base on the eastern shore of the island of Santo Stefano. What is the source of these nuclides: last century's atmospheric nuclear testing, Chernobyl or

  1. Electrocardiograph-gated single photon emission computed tomography radionuclide angiography presents good interstudy reproducibility for the quantification of global systolic right ventricular function.

    Science.gov (United States)

    Daou, Doumit; Coaguila, Carlos; Vilain, Didier

    2007-05-01

    Electrocardiograph-gated single photon emission computed tomography (SPECT) radionuclide angiography provides accurate measurement of right ventricular ejection fraction and end-diastolic and end-systolic volumes. In this study, we report the interstudy precision and reliability of SPECT radionuclide angiography for the measurement of global systolic right ventricular function using two, three-dimensional volume processing methods (SPECT-QBS, SPECT-35%). These were compared with equilibrium planar radionuclide angiography. Ten patients with chronic coronary artery disease having two SPECT and planar radionuclide angiography acquisitions were included. For the right ventricular ejection fraction, end-diastolic volume and end-systolic volume, the interstudy precision and reliability were better with SPECT-35% than with SPECT-QBS. The sample sizes needed to objectify a change in right ventricular volumes or ejection fraction were lower with SPECT-35% than with SPECT-QBS. The interstudy precision and reliability of SPECT-35% and SPECT-QBS for the right ventricle were better than those of equilibrium planar radionuclide angiography, but poorer than those previously reported for the left ventricle with SPECT radionuclide angiography on the same population. SPECT-35% and SPECT-QBS present good interstudy precision and reliability for right ventricular function, with the results favouring the use of SPECT-35%. The results are better than those of equilibrium planar radionuclide angiography, but poorer than those previously reported for the left ventricle with SPECT radionuclide angiography. They need to be confirmed in a larger population.

  2. Calibration of radionuclides with decay trough beta emission or electron capture by liquid scintillation technique

    International Nuclear Information System (INIS)

    Loureiro, Jamir dos Santos

    2000-02-01

    In this work is reported a methodology a methodology for pure beta and electron capture radionuclides standardization, suing liquid scintillation technique. In this sense the CIEMAT/NIST method, recently utilized by international laboratories, was implemented and the lack in the Laboratorio Nacional das Radiacoes Ionizantes - LNMRI, of the Comissao Nacional de Energia Nuclear - CNEN, for adequate methodology to standardize this kind if radionuclides was filled, fact that was not present with alpha and gamma radionuclides. The implementation procedure evaluation was provided by concentration activity determination of the following radionuclides: 14 C and 90 Sr, pure beta emitters; 55 Fe, electron capture decay; 204 Tl, electron capture and beta decay and 60 Co, beta-gamma emitter. In this way, a careful analysis of the implementation procedure with these radionuclides types, ranging on a broad energy spectral, was possible. To check the calibration results, intercomparisons among our measurements of these radionuclides and the reference values of the CIEMAT/Spain laboratory were provided. To check the calibration results, intercomparisons among our measurements of these radionuclides and the reference values of the CIEMAT/Spain laboratory were provided. Besides this intercomparisons, one was provided with a 204 Tl solution, utilized in the international comparison recently promoted by BIPM, and another one with a 60 C solution calibrated in LNMRI/CNEN previously by a relative calibration system, with a well type pressurized ionization chamber, and an absolute beta-gamma coincidence system, with a pill-box type proportional counter 4 π geometry, coupled with a scintillator system with a sodium iodide cristal of 4x4 inches. The comparisons among LNMRI/CNEN results and the reference values, showed a small deviation of 1,32% for 14 C, 0,40% for 60 Co, 1,12% for 55 Fe, 0,10% for 90 Sr and 0,73% for 204 Tl. For the BIPM solution the deviation was 0,46% and for 60 Co

  3. Dose assessment for potential radionuclide emissions from stacks on the Hanford Site: NESHAP compliance

    International Nuclear Information System (INIS)

    Davis, W.E.; Barnett, J.M.; Kenoyer, J.L.

    1994-03-01

    The purpose of this document is to present the assessment results for the registered stacks on the Hanford Site for potential emissions, i.e. emissions with no control devices in place. Further, the document will identify those stacks requiring continuous monitoring, i.e. the effective dose equivalent from potential emissions >0.1 mrem/yr. The stack assessment of potential emissions was performed on 84 registered stacks on the Hanford Site. These emission sources represent individual point sources presently registered under Washington Administrative code 246-247 with the Washington Department of Health. The methods used in assessing the potential emissions from the stacks are described

  4. Air Emission Inventory for the Idaho National Engineering Laboratory, 1993 emissions report

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    This report presents the 1993 update of the Air Emission Inventory for the Idaho National Engineering Laboratory (INEL). The purpose of the Air Emission Inventory is to commence the preparation of the permit to operate application for the INEL, as required by the recently promulgated Title V regulations of the Clean Air Act. The report describes the emission inventory process and all of the sources at the INEL and provides emissions estimates for both mobile and stationary sources.

  5. Air Emission Inventory for the Idaho National Engineering Laboratory, 1993 emissions report

    International Nuclear Information System (INIS)

    1994-06-01

    This report presents the 1993 update of the Air Emission Inventory for the Idaho National Engineering Laboratory (INEL). The purpose of the Air Emission Inventory is to commence the preparation of the permit to operate application for the INEL, as required by the recently promulgated Title V regulations of the Clean Air Act. The report describes the emission inventory process and all of the sources at the INEL and provides emissions estimates for both mobile and stationary sources

  6. EPA perspective on radionuclide aerosol sampling

    Energy Technology Data Exchange (ETDEWEB)

    Karhnak, J.M. [Environmental Protection Agency, Washington, DC (United States)

    1995-02-01

    The Environmental Protection Agency (EPA) is concerned with radionuclide aerosol sampling primarily at Department of Energy (DOE) facilities in order to insure compliance with national air emission standards, known as NESHAPs. Sampling procedures are specified in {open_quotes}National Emission Standards for Emissions of Radionuclides other than Radon from Department of Energy Sites{close_quotes} (Subpart H). Subpart H also allows alternate procedures to be used if they meet certain requirements. This paper discusses some of the mission differences between EPA and Doe and how these differences are reflected in decisions that are made. It then describes how the EPA develops standards, considers alternate sampling procedures, and lists suggestions to speed up the review and acceptance process for alternate procedures. The paper concludes with a discussion of the process for delegation of Radionuclide NESHAPs responsibilities to the States, and responsibilities that could be retained by EPA.

  7. National intercomparison programme for radionuclide analysis in environmental samples: Aramar radioecological laboratory performance

    Energy Technology Data Exchange (ETDEWEB)

    Arine, Bruno Burini Robles, E-mail: bruno.arine@ctmsp.mar.mil.b [Centro Tecnologico da Marinha em Sao Paulo (CTMSP/ARAMAR), Ipero, SP (Brazil). Lab. Radioecologico; Moraes, Marco Antonio P.V., E-mail: marco.proenca@ctmsp.mar.mil.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    The radioecological laboratory is concerned with the measurements of background radiation (mainly uranium and thorium natural series) and present effluents in the Aramar Experimental Centre, as well as in its surroundings. The laboratory is directly subordinated to the Navy Technological Centre in Sao Paulo (CTMSP - Sao Paulo - Brazil), a military research organization whose goal is to develop nuclear and energy systems for the Brazilian naval ship propulsion. The measurements were performed in addition to the Environmental Monitoring Programme carried out in the same region. For this endeavour, the laboratory has attended to the National Intercomparison Programme conducted by the Institute for Radioprotection and Dosimetry (IRD) by analyzing several kinds of solid and liquid samples containing specific radionuclides through gamma spectrometry, liquid scintillation, alpha-beta total counting and fluorimetry techniques, since December 1995. In the last 15 years, our results were compared to another 19 laboratories and rated as 'very good' and 'acceptable' in at least 90% of the results. (author)

  8. Implementation of a metrology national network for radionuclides used in nuclear medicine

    International Nuclear Information System (INIS)

    Santos, J.A. dos; Lopes, R.T.; Iwahara, A.; Tauhata, L.; Nicoli, I.G.; Dias, C.M.

    2003-01-01

    The Brazilian Laboratory for Metrology of Ionizing Radiation (LNMRI), of the Radioprotection and Dosimetry Institute, owned by the National Commission of Nuclear Energy (IRD/CNEN-RJ) has conducting since 1998, a comparison program for measurements of radiopharmaceuticals activities applied to patients at Nuclear Medicine sector aiming to the assessment the quality of those measurements. In the Rio de Janeiro state this program is successfully performed existing however the necessity to implement such program all over the country. This problem is being solved through the implementation of a reference laboratories network at several points in the brazilian territory. For the establishment and good working of the network the following factors must be observed: the radionuclide calibrators at the reference laboratories must be connected to the LNMRI; the operators must be trained by the staff or the LNMRI, and the quality guarantee must be assured through a comparison program. Presently, the network point placed in Brasilia is running and covering all the center-west region. The results obtained at this region show that the implementation of the metrology network is viable, important and achievable

  9. Radionuclide concentrations in elk that winter on Los Alamos National Laboratory lands. Revision

    International Nuclear Information System (INIS)

    Fresquez, P.R.; Armstrong, D.A.; Salazar, J.G.

    1994-07-01

    Elk spend the winter in areas at Los Alamos National Laboratory (LANL) that may contain radioactivity above natural and/or worldwide fallout levels. This study was initiated to determine the levels of 90 Sr, 137 Cs, 238 Pu, 239 Pu, and total uranium in various tissues (brain, hair, heart, jawbone, kidneys, leg bone, liver, and muscle) of adult cow elk that use LANL lands during the fall/winter months. No significant differences in radionuclide contents were detected in any of the tissue samples collected from elk on LANL lands as compared with elk collected from off-site locations. The total effective (radiation) dose equivalent a person would receive from consuming 3.2 lb of heart, 5.6 lb of liver, and 226 lb of muscle from elk that winter on LANL lands, after natural background has been subtracted, was 0.00008, 0.0001, and 0.008 mrem/yr, respectively. The highest dose was less than 0.01% of the International Commission on Radiological Protection permissible dose limit for protecting the public

  10. Radionuclide concentrations in elk that winter on Los Alamos National Laboratory lands

    International Nuclear Information System (INIS)

    Fresquez, P.R.; Armstrong, D.A.; Salazar, J.G.

    1994-07-01

    Elk spend the winter in areas at Los Alamos National Laboratory (LANL) that may contain radioactivity above natural and/or worldwide fallout levels. This study was initiated to determine the levels of 90 Sr, 137 Cs, 238 Pu, 239 Pu, and total uranium in various tissues (brain, hair, heart, jawbone, kidneys, leg bone, liver, and muscle) of adult cow elk that use LANL lands during the fall/winter months. No significant differences in radionuclide contents were detected in any of the tissue samples collected from elk on LANL lands as compared with elk collected from off-site locations. The total effective (radiation) dose equivalent a person would receive from consuming 3.2 lb of heart, 5.6 lb of liver, and 226 lb of muscle from elk that winter on LANL lands, after natural background has been subtracted, was 0.00008, 0.0001, and 0.008 mrem/yr, respectively. The highest dose was less than 0.01% of the International Commission of Radiological Protection permissible dose limit for protecting the public

  11. GHG emission estimates for road transport in national GHG inventories

    NARCIS (Netherlands)

    Pulles, M.P.J.; Yang, H.

    2011-01-01

    The annual reporting procedures of the United Nations Framework Convention on Climate Change (UNFCCC) have now produced greenhouse gas (GHG) emission inventories from 40 so-called Annex I countries for 18 years. This article analyses a subset of these data: emissions from road transport. The article

  12. An evaluation of the effectiveness of the EPA comply code to demonstrate compliance with radionuclide emission standards at three manufacturing facilities

    International Nuclear Information System (INIS)

    Smith, L.R.; Laferriere, J.R.; Nagy, J.W.

    1991-01-01

    Measurements of airborne radionuclide emissions and associated environmental concentrations were made at, and in the vicinity of, two urban and one suburban facility where radiolabeled chemicals for biomedical research and radiopharmaceuticals are manufactured. Emission, environmental and meteorological measurements were used in the EPA COMPLY code and in environmental assessment models developed specifically for these sites to compare their ability to predict off-site measurements. The models and code were then used to determine potential dose to hypothetical maximally exposed receptors and the ability of these methods to demonstrate whether these facilities comply with proposed radionuclide emission standards assessed. In no case did the models and code seriously underestimate off-site impacts. However, for certain radionuclides and chemical forms, the EPA COMPLY code was found to overestimate off-site impacts by such a large factor as to render its value questionable for determining regulatory compliance. Recommendations are offered for changing the code to enable it to be more serviceable to radionuclide users and regulators

  13. Assessment for potential radionuclide emissions from stacks and diffuse and fugitive sources on the Hanford Site

    International Nuclear Information System (INIS)

    Davis, W.E.; Schmidt, J.W.; Gleckler, B.P.; Rhoads, K.

    1995-06-01

    By using the six EPA-approved methods, instead of only the original back calculation method for assessing the 84 WHC registered stacks, the number of stacks requiring continuous monitoring was reduced from 32 to 19 stacks. The intercomparison between results showed that no correlation existed between back calculations and release fractions. Also the NDA, upstream air samples, and powder release fraction method results were at least three orders of magnitude lower then the back calculations results. The most surprising results of the assessment came from NDA. NDA was found to be an easy method for assessing potential emissions. For the nine stacks assessed by NDA, all nine of the stacks would have required continuous monitoring when assessed by back calculations. However, when NDA was applied all stacks had potential emissions that would cause an EDE below the > 0.1 mrem/y standard. Apparent DFs for the HEPA filter systems were calculated for eight nondesignated stacks with emissions above the detection limit. These apparent DFs ranged from 0.5 to 250. The EDE dose to the MEI was calculated to be 0.028 mrem/y for diffuse and fugitive emissions from the Hanford Sited. This is well below the > 0.1 mrem/y standard

  14. Measurement of the induced radionuclides in production of radiopharmaceuticals for positron emission tomography (PET)

    International Nuclear Information System (INIS)

    Machizuki, Shingo; Ogatam Yoshimune; Ishigure, Nobuhito; Hatano, Kentaro; Abe, Junichiro; Ito, Kengo; Ito, Yoshihiro; Nishino, Masanari; Miyahara, Hiroshi

    2006-01-01

    The radioactive by-products contained in an entire series of target foil, [ 18 O]H 2 O and synthesis apparatus were identified and quantified. From the perspective of waste management, 60 Co induced in Havar foil should be taken into consideration. Because the exempt activity of 60 Co in BSS is 0.1 MBq, the used Havar foil should be managed more than for 20 years. The radionuclides in the [ 18 F]-FDG synthesis apparatus are negligible. Equivalent doses at skin and to tissues were estimated assuming a point source at a distance of 30 cm in air. The annual equivalent doses at skin and equivalent dose at deep tissues of such an operating staff will be 56 and 8.3 μSv, respectively, as two times the remove of the target foil and five hundreds times the synthesis of the [ 18 F]-FDG. When proper radiation protection is provided, the exposure from the cyclotron management and the [ 18 F]-FDG synthesis process will not cause meaningful radiological risk to the operating staff. The activity concentration of 3 H, 180 kBq·cm -3 , detected in the target water, is 3,000 times the legal limit of effluent for 3 H. The operators should take care of the treatment of the target water when they make a distillation for reuse and a disposal. (author)

  15. Radionuclide scanning

    International Nuclear Information System (INIS)

    Shapiro, B.

    1986-01-01

    Radionuclide scanning is the production of images of normal and diseased tissues and organs by means of the gamma-ray emissions from radiopharmaceutical agents having specific distributions in the body. The gamma rays are detected at the body surface by a variety of instruments that convert the invisible rays into visible patterns representing the distribution of the radionuclide in the body. The patterns, or images, obtained can be interpreted to provide or to aid diagnoses, to follow the course of disease, and to monitor the management of various illnesses. Scanning is a sensitive technique, but its specificity may be low when interpreted alone. To be used most successfully, radionuclide scanning must be interpreted in conjunction with other techniques, such as bone radiographs with bone scans, chest radiographs with lung scans, and ultrasonic studies with thyroid scans. Interpretation is also enhanced by providing pertinent clinical information because the distribution of radiopharmaceutical agents can be altered by drugs and by various procedures besides physiologic and pathologic conditions. Discussion of the patient with the radionuclide scanning specialist prior to the study and review of the results with that specialist after the study are beneficial

  16. Air Emission Inventory for the Idaho National Engineering Laboratory: 1992 emissions report

    International Nuclear Information System (INIS)

    Stirrup, T.S.

    1993-06-01

    This report presents the 1992 Air Emission Inventory for the Idaho National Engineering Laboratory. Originally, this report was in response to the Environmental Oversight and Monitoring Agreement in 1989 between the State of Idaho and the Department of Energy Idaho Field Office, and a request from the Idaho Air Quality Bureau. The current purpose of the Air Emission Inventory is to provide the basis for the preparation of the INEL Permit-to-Operate (PTO) an Air Emission Source Application, as required by the recently promulgated Title V regulations of the Clean Air Act. This report includes emissions calculations from 1989 to 1992. The Air Emission Inventory System, an ORACLE-based database system, maintains the emissions inventory

  17. Air Emission Inventory for the Idaho National Engineering Laboratory: 1992 emissions report

    Energy Technology Data Exchange (ETDEWEB)

    Stirrup, T.S.

    1993-06-01

    This report presents the 1992 Air Emission Inventory for the Idaho National Engineering Laboratory. Originally, this report was in response to the Environmental Oversight and Monitoring Agreement in 1989 between the State of Idaho and the Department of Energy Idaho Field Office, and a request from the Idaho Air Quality Bureau. The current purpose of the Air Emission Inventory is to provide the basis for the preparation of the INEL Permit-to-Operate (PTO) an Air Emission Source Application, as required by the recently promulgated Title V regulations of the Clean Air Act. This report includes emissions calculations from 1989 to 1992. The Air Emission Inventory System, an ORACLE-based database system, maintains the emissions inventory.

  18. Production of radionuclides and radiopharmaceuticals at the Argentine Atomic Energy National Commission

    International Nuclear Information System (INIS)

    Mitta, A.E.A.; Bonetto, Oscar; Kurcbart, Horacio; Mancini, Alberto; Marquez, R.O.; Palcos, M.C.; Quihillalt, E.L.; Salas, G.N.B. de; Suner, A.A.; Troparevsky, M.L.P. de.

    1978-03-01

    The production of radionuclides and radiopharmaceuticals at the CNEA is described, as well as the preparation of reagent's sets, and informations is given on the preparation of Tc-99m and In-113m generators. Some figures of the production of 1974-1976 are given. (author) [es

  19. Natural attenuation of metals and radionuclides: Report from a workshop held by Sandia National Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Brady, P.V.; Borns, D.J. [Sandia National Labs., Albuquerque, NM (United States). Geochemistry Dept.

    1997-11-01

    Natural attenuation is increasingly applied to remediate contaminated soils and ground waters. Roughly 25% of Superfund groundwater remedies in 1995 involved some type of monitored natural attenuation, compared to almost none 5 years ago. Remediation by natural attenuation (RNA) requires clear evidence that contaminant levels are decreasing sufficiently over time, a defensible explanation of the attenuation mechanism, long-term monitoring, and a contingency plan at the very least. Although the primary focus of implementation has to date been the biodegradation of organic contaminants, there is a wealth of scientific evidence that natural processes reduce the bioavailability of contaminant metals and radionuclides. Natural attenuation of metals and radionuclides is likely to revolve around sorption, solubility, biologic uptake and dilution controls over contaminant availability. Some of these processes can be applied to actively remediate sites. Others, such as phytoremediation, are likely to be ineffective. RNA of metals and radionuclides is likely to require specialized site characterization to construct contaminant and site-specific conceptual models of contaminant behavior. Ideally, conceptual models should be refined such that contaminant attenuation can be confidently predicted into the future. The technical approach to RNA of metals and radionuclides is explored here.

  20. Natural attenuation of metals and radionuclides: Report from a workshop held by Sandia National Laboratories

    International Nuclear Information System (INIS)

    Brady, P.V.; Borns, D.J.

    1997-11-01

    Natural attenuation is increasingly applied to remediate contaminated soils and ground waters. Roughly 25% of Superfund groundwater remedies in 1995 involved some type of monitored natural attenuation, compared to almost none 5 years ago. Remediation by natural attenuation (RNA) requires clear evidence that contaminant levels are decreasing sufficiently over time, a defensible explanation of the attenuation mechanism, long-term monitoring, and a contingency plan at the very least. Although the primary focus of implementation has to date been the biodegradation of organic contaminants, there is a wealth of scientific evidence that natural processes reduce the bioavailability of contaminant metals and radionuclides. Natural attenuation of metals and radionuclides is likely to revolve around sorption, solubility, biologic uptake and dilution controls over contaminant availability. Some of these processes can be applied to actively remediate sites. Others, such as phytoremediation, are likely to be ineffective. RNA of metals and radionuclides is likely to require specialized site characterization to construct contaminant and site-specific conceptual models of contaminant behavior. Ideally, conceptual models should be refined such that contaminant attenuation can be confidently predicted into the future. The technical approach to RNA of metals and radionuclides is explored here

  1. Radionuclide concentrations in game and nongame fish upstream and downstream of Los Alamos National Laboratory: 1981 to 1993

    International Nuclear Information System (INIS)

    Fresquez, P.R.; Armstrong, D.R.; Salazar, J.G.

    1994-08-01

    Radionuclide concentrations were determined in game (surface-feeding) and nongame (bottom-feeding) fish collected from reservoirs upstream (Abiquiu, Heron, and El Vado) and downstream (Cochiti) of Los Alamos National Laboratory from 1981 to 1993. The average levels of 90 Sr, 137 Cs, 238 Pu, and 239 Pu in game and nongame fish collected from Cochiti reservoir were not significantly different in fish collected from reservoirs upstream of the Laboratory. Total uranium was the only radionuclide that was found to be significantly higher n both game and nongame fish from Cochiti as compared to fish from Abiquiu, Heron, and El Vado. Uranium concentrations in fish collected from Cochiti, however, significantly decreased from 1981 to 1993, and no evidence of depleted uranium was found in fish samples collected from Cochiti in 1993. Based on the average concentration of radionuclides over the year the effective (radiation) dose equivalent from consuming 46 lb of game fish and nongame fish from Cochiti reservoir after natural background has been subtracted was 0.005 and 0.009 mrem/yr, respectively. The highest dose was <0.01% of the International Commission on Radiological Protection (ICRP) permissible dose limit for protecting members of the public

  2. National Framework for GHG Emission Trading in Russia

    International Nuclear Information System (INIS)

    Kotov, V.; Nikitina, E.

    2003-01-01

    If Russia ratifies the Kyoto Protocol to the United Nations Framework Convention on Climate Change (UNFCCC), domestic implementation of its international commitments under this international regime will require special national responses, i.e. institutional capacity building for application of its mechanisms. The Kyoto Protocol and its mechanisms, particularly, international emission trading (IET) and joint implementation (JI), mark a turning point, with opportunities for Russia to benefit from an economic and environmental standpoint from international cooperation. Russia might wish to sell to other parties a surplus in its assigned amount for the first commitment period in 2008-2012, as according to existing estimates its GHG emissions are expected to be below their 1990 base level. In order to participate in international emission trading, Russia has to meet several international requirements, including providing national inventory and reporting and establishing national registry compatible with the standard international format. It is to establish a domestic institutional regime defining laws and rules of behaviour for its participants, the administrative frameworks, and designing major schemes for domestic emission trading programme. Russia's emission trading system is not formed yet. This is a challenging innovation for Russia, as in its previous environmental management practices it did not have any experience in domestic emission trading with other air pollutants. The paper examines the key elements suggested in a number of existing proposals, assessments, and approaches of the government, parliamentarians and non-governmental experts for its institutional design which is at the core of ongoing climate policy debates in the country. These approaches and practical suggestions define the current state-of-the-art in domestic emission trading regime formation and channel the paths of its institutional development in the future. This paper analyses peculiarities

  3. National environmental targets and international emission reduction instruments

    International Nuclear Information System (INIS)

    Morthorst, P.E.

    2003-01-01

    According to the agreed burden sharing within the European Union the overall EU emission reduction target as agreed by in the Kyoto protocol is converted into national greenhouse gas reduction-targets for each of the member states. In parallel with national emission reduction initiatives common EU policies for emission reductions are considered. Currently discussed is the introduction of a market for tradable permits for CO 2 -emissions to achieve emission reductions within the power industry and other energy intensive industries. In parallel with this markets for green certificates to deploy renewable energy technologies seem to be appearing in a number of countries, among these Denmark, Italy, Sweden, Belgium (Flanders), England and Australia. Although these national initiatives for a green certificate market are fairly different, they could be a starting point for establishing a common EU certificate market. But interactions between national targets for greenhouse gas emissions and these international instruments for emission reduction are not a trivial matter, especially not seen in relation to the possible contributions of these instruments in achieving national GHG-reduction targets. The paper is split into three parts all taking a liberalised power market as starting point: The first part discusses the consequences of a general deployment of renewable energy technologies, using planning initiatives or national promotion schemes (feed-in tariffs). In the second part an international green certificate market is introduced into the liberalised power market context, substituting other national promotion schemes. Finally, in the third part a combination of an international green certificate market (TGC) and an international emission-trading scheme for CO 2 is analysed within the liberalised international power market set-up. The main conclusion is that neither the use of national renewable support schemes nor the introduction of a TGC-market into a liberalised

  4. New national emission inventory for navigation in Denmark

    Science.gov (United States)

    Winther, Morten

    This article explains the new emission inventory for navigation in Denmark, covering national sea transport, fisheries and international sea transport. For national sea transport, the new Danish inventory distinguishes between regional ferries, local ferries and other national sea transport. Detailed traffic and technical data lie behind the fleet activity-based fuel consumption and emission calculations for regional ferries. For local ferries and other national sea transport, the new inventory is partly fleet activity based; fuel consumption estimates are calculated for single years, and full fuel consumption coverage is established in a time series by means of appropriate assumptions. For fisheries and international sea transport, the new inventory remains fuel based, using fuel sales data from the Danish Energy Authority (DEA). The new Danish inventory uses specific fuel consumption (sfc) and NO x emission factors as a function of engine type and production year. These factors, which are used directly for regional ferries and, for the remaining navigation categories, are derived by means of appropriate assumptions, serve as a major inventory improvement, necessary for making proper emission trend assessments. International sea transport is the most important fuel consumption and emission source for navigation, and the contributions are large even compared with the overall Danish totals. If the contributions from international sea transport were included in the Danish all-sector totals, the extra contributions in 2005 from fuel consumption (and CO 2), NO x and SO 2 would be 5%, 34% and 167%, respectively. The 1990-2005 changes in fuel consumption as well as NO x and SO 2 emissions for national sea transport (-45, -45, -81), fisheries (-18, 6, -18) and international sea transport (-14, 1, -14) reflect changes in fleet activity/fuel consumption and emission factors. The 2006-2020 emission forecasts demonstrate a need for stricter fuel quality and NO x emission

  5. Hydrology of the solid waste burial ground as related to potential migration of radionuclides, Idaho National Engineering Laboratory

    Science.gov (United States)

    Barraclough, Jack T.; Robertson, J.B.; Janzer, V.J.; Saindon, L.G.

    1976-01-01

    A study was made (1970-1974) to evaluate the geohydrologic and geochemical controls on subsurface migration of radionuclides from pits and trenches in the Idaho National Engineering Laboratory (INEL) solid waste burial ground and to determine the existence and extent of radionuclide migration from the burial ground. A total of about 1,700 sediment, rock, and water samples were collected from 10 observation wells drilled in and near the burial ground of Idaho National Engineering Laboratory, formerly the National Reactor Testing Station (NRTS). Within the burial ground area, the subsurface rocks are composed principally of basalt. Wind- and water-deposited sediments occur at the surface and in beds between the thicker basalt zones. Two principal sediment beds occur at about 110 feet and 240 feet below the land surface. The average thickness of the surficial sedimentary layer is about 15 feet while that of the two principal subsurface layers is 13 and 14 feet, respectively. The water table in the aquifer beneath the burial ground is at a depth of about 580 feet. Fission, activation, and transuranic elements were detected in some of the samples from the 110- and 240-foot sedimentary layers. (Woodard-USGS)

  6. Influence of trade on national CO2 emissions

    International Nuclear Information System (INIS)

    Munksgaard, Jesper; Pade, Lise-Lotte; Minx, Jan; Lenzen, Manfred

    2005-01-01

    International trade has an impact on national CO 2 emissions and consequently on the ability to fulfil national CO 2 reduction targets. Through goods and services traded in a globally interdependent world, the consumption in each country is linked to greenhouse gas emissions in other countries. It has been argued that in order to achieve equitable reduction targets, international trade has to be taken into account when assessing nations' responsibility for abating climate change. Especially for open economies such as Denmark, greenhouse gases embodied in internationally traded commodities can have a considerable influence on the national 'greenhouse gas responsibility'. By using input-output modelling, we analyse the influence from international trade on national CO 2 emissions. The aim is to show that trade is the key to define CO 2 responsibility on a macroeconomic level and that imports should be founded in a multi-region model approach. Finally, the paper concludes on the need to consider the impact from foreign trade when negotiating reduction targets and base line scenarios. (Author)

  7. Investigation of radionuclide release from Solid Waste Disposal Area 3, Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Stueber, A.M.; Webster, D.A.; Munro, I.L.; Farrow, N.D.; Scott, T.G.

    1981-08-01

    Radionuclide release from Solid Waste Disposal Area (SWDA) 3 has been studied through the analysis of surface and ground waters from the local drainage areas. SWDA 3 is located in the Northwest Tributary drainage basin, a part of the White Oak Creek drainage; 90 Sr is the only radionuclide being discharged in solution in the main stream. Water-level measurements in wells around SWDA 3 suggest the presence of a ground-water divide beneath the southwestern end of the disposal area. Ground water below this area may be moving southwestward toward the Raccoon Creek drainage system. Strontium-90 activity has been detected in this watershed, discharging from a seep adjacent to a Raccoon Creek tributary stream about 640 m southwest of SWDA 3. It appears that 90 Sr is moving through ground-water flow to the northeast and to the southwest of SWDA 3 and that this direction of movement is related to bedrock structure. The trend of a line connecting the two seeps passes through the disposal area and is parallel to bedrock strike. Information from core-hole logs and televiewer logs suggests that 90 Sr in ground water may be moving through solution channels near the contact between units F and G of the Chickamauga Limestone. The apparent extent of migration of 90 Sr in bedrock has implications regarding potential underground radionuclide movement in Melton Valley

  8. U.S. Department of Energy Report 1998 LANL Radionuclide Air Emissions

    Energy Technology Data Exchange (ETDEWEB)

    Keith W. Jacobson

    1999-07-01

    Presented is the Laboratory-wide certified report regarding radioactive effluents released into the air by Los Alamos National Laboratory (LANL) in 1998. This information is required under the Clean Air Act and is being reported to the US Environmental Protection Agency (EPA). The highest effective dose equivalent (EDE) to an off-site member of the public was calculated using procedures specified by the EPA and described in this report. For 1998, the dose was 1.72 mrem. Airborne effluents from a 1 mA, 800 MeV proton accelerator contributed about 80% of the EDE; the majority of the total dose contribution was via the air immersion pathway.

  9. Radionuclide radiology

    International Nuclear Information System (INIS)

    Scarsbrook, A.F.; Graham, R.N.J.; Perriss, R.W.; Bradley, K.M.

    2006-01-01

    This is the fourth in a series of short reviews of internet-based radiological educational resources, and will focus on radionuclide radiology and nuclear medicine. What follows is a list of carefully selected websites to save time in searching them out. Most of the sites cater for trainee or non-specialist radiologists, but may also be of interest to specialists for use in teaching. This article may be particularly useful to radiologists interested in the rapidly expanding field of positron emission tomography computed tomography (PET-CT). Hyperlinks are available in the electronic version of this article and were all active at the time of going to press (February 2006)

  10. U.S. Department of Energy Report 1997 LANL Radionuclide Air Emissions

    International Nuclear Information System (INIS)

    Jacobson, K.W.

    1998-01-01

    Presented is the Laboratory-wide certified report regarding radioactive effluents released into the air by the Los Alamos National Laboratory (LANL) in 1997. This information is required under the Clean Air Act and is being reported to the U.S. Environmental Protection Agency (EPA). The highest effective dose equivalent (EDE) to an offsite member of the public was calculated using procedures specified by the EPA and described in this report. For 1997, the dose was 3.51 mrem. Airborne effluents from a 1mA, 800 MeV proton accelerator contributed to over 90% of the EDE; more than 86% of the total dose contribution was through the air immersion pathway

  11. U.S. Department of Energy Report 1997 LANL Radionuclide Air Emissions

    Energy Technology Data Exchange (ETDEWEB)

    Jacobson, K.W.

    1998-09-01

    Presented is the Laboratory-wide certified report regarding radioactive effluents released into the air by the Los Alamos National Laboratory (LANL) in 1997. This information is required under the Clean Air Act and is being reported to the U.S. Environmental Protection Agency (EPA). The highest effective dose equivalent (EDE) to an offsite member of the public was calculated using procedures specified by the EPA and described in this report. For 1997, the dose was 3.51 mrem. Airborne effluents from a 1mA, 800 MeV proton accelerator contributed to over 90% of the EDE; more than 86% of the total dose contribution was through the air immersion pathway.

  12. Experience in teaching of radionuclide diagnosis in radiology course at Bogomolets national medical university

    International Nuclear Information System (INIS)

    Tkachenko, M.M.; Romanenko, G.O.; Morozova, N.L.; Mironova, O.V.

    2017-01-01

    The article highlights aspects of teaching radionuclide diagnosis (RND) in the study of complex radiation diagnosis and radiotherapy. Teaching of radiation at undergraduate stage is based on the results of new scientific achievements in radiology and guiding principles of evidence-based medicine. At present studying RND is intended to support the aspiration of European medical community to create a unified science-based approaches to diagnosis and it shows promise of new forms of learning that promote active creative work of a student.

  13. ACCELERATED SITE TECHNOLOGY DEPLOYMENT COST AND PERFORMANCE REPORT COMPARABILITY OF ISOCS INSTRUMENT IN RADIONUCLIDE CHARACTERICATION AT BROOKHAVEN NATIONAL LABORATORY

    Energy Technology Data Exchange (ETDEWEB)

    KALB,P.; LUCKETT,L.; MILLER,K.; GOGOLAK,C.; MILIAN,L.

    2001-03-01

    This report describes a DOE Accelerated Site Technology Deployment project being conducted at Brookhaven National Laboratory to deploy innovative, radiological, in situ analytical techniques. The technologies are being deployed in support of efforts to characterize the Brookhaven Graphite Research Reactor (BGRR) facility, which is currently undergoing decontamination and decommissioning. This report focuses on the deployment of the Canberra Industries In Situ Object Counting System (ISOCS) and assesses its data comparability to baseline methods of sampling and laboratory analysis. The battery-operated, field deployable gamma spectrometer provides traditional spectra of counts as a function of gamma energy. The spectra are then converted to radionuclide concentration by applying innovative efficiency calculations using monte carlo statistical methods and pre-defined geometry templates in the analysis software. Measurement of gamma emitting radionuclides has been accomplished during characterization of several BGRR components including the Pile Fan Sump, Above Ground Ducts, contaminated cooling fans, and graphite pile internals. Cs-137 is the predominant gamma-emitting radionuclide identified, with smaller quantities of Co-60 and Am-241 detected. The Project used the Multi-Agency Radiation Survey and Site Investigation Manual guidance and the Data Quality Objectives process to provide direction for survey planning and data quality assessment. Analytical results have been used to calculate data quality indicators (DQI) for the ISOCS measurements. Among the DQIs assessed in the report are sensitivity, accuracy, precision, bias, and minimum detectable concentration. The assessment of the in situ data quality using the DQIs demonstrates that the ISOCS data quality can be comparable to definitive level laboratory analysis when the field instrument is supported by an appropriate Quality Assurance Project Plan. A discussion of the results obtained by ISOCS analysis of

  14. ACCELERATED SITE TECHNOLOGY DEPLOYMENT COST AND PERFORMANCE REPORT COMPARABILITY OF ISOCS INSTRUMENT IN RADIONUCLIDE CHARACTERICATION AT BROOKHAVEN NATIONAL LABORATORY

    International Nuclear Information System (INIS)

    KALB, P.; LUCKETT, L.; MILLER, K.; GOGOLAK, C.; MILIAN, L.

    2001-01-01

    This report describes a DOE Accelerated Site Technology Deployment project being conducted at Brookhaven National Laboratory to deploy innovative, radiological, in situ analytical techniques. The technologies are being deployed in support of efforts to characterize the Brookhaven Graphite Research Reactor (BGRR) facility, which is currently undergoing decontamination and decommissioning. This report focuses on the deployment of the Canberra Industries In Situ Object Counting System (ISOCS) and assesses its data comparability to baseline methods of sampling and laboratory analysis. The battery-operated, field deployable gamma spectrometer provides traditional spectra of counts as a function of gamma energy. The spectra are then converted to radionuclide concentration by applying innovative efficiency calculations using monte carlo statistical methods and pre-defined geometry templates in the analysis software. Measurement of gamma emitting radionuclides has been accomplished during characterization of several BGRR components including the Pile Fan Sump, Above Ground Ducts, contaminated cooling fans, and graphite pile internals. Cs-137 is the predominant gamma-emitting radionuclide identified, with smaller quantities of Co-60 and Am-241 detected. The Project used the Multi-Agency Radiation Survey and Site Investigation Manual guidance and the Data Quality Objectives process to provide direction for survey planning and data quality assessment. Analytical results have been used to calculate data quality indicators (DQI) for the ISOCS measurements. Among the DQIs assessed in the report are sensitivity, accuracy, precision, bias, and minimum detectable concentration. The assessment of the in situ data quality using the DQIs demonstrates that the ISOCS data quality can be comparable to definitive level laboratory analysis when the field instrument is supported by an appropriate Quality Assurance Project Plan. A discussion of the results obtained by ISOCS analysis of

  15. Tank exhaust comparison with 40 CFR 61.93, Subpart H, and other referenced guidelines for Tank Farms National Emission Standards for Hazardous Air Pollutant (NESHAP) designated stacks

    International Nuclear Information System (INIS)

    Bachand, D.D.; Crummel, G.M.

    1994-07-01

    The US Environmental Protection Agency (EPA) promulgated National Emission Standards other than Radon from US Department of Energy (DOE) Facilities (40 CFR 61, Subpart H) on December 15, 1989. The regulations specify procedures, equipment, and test methods that.are to be used to measure radionuclide emissions from exhaust stacks that are designated as National Emission Standards for Hazardous Air Pollutant (NESHAP) stacks. Designated NESHAP stacks are those that have the potential to cause any member of the public to receive an effective dose equivalent (EDE) greater than or equal to 0.1 mrem/year, assuming all emission controls were removed. Tank Farms currently has 33 exhaust stacks, 15 of which are designated NESHAP stacks. This document assesses the compliance status of the monitoring and sampling systems for the designated NESHAP stacks

  16. Tank exhaust comparison with 40 CFR 61.93, Subpart H, and other referenced guidelines for Tank Farms National Emission Standards for Hazardous Air Pollutant (NESHAP) designated stacks

    Energy Technology Data Exchange (ETDEWEB)

    Bachand, D.D.; Crummel, G.M.

    1994-07-01

    The US Environmental Protection Agency (EPA) promulgated National Emission Standards other than Radon from US Department of Energy (DOE) Facilities (40 CFR 61, Subpart H) on December 15, 1989. The regulations specify procedures, equipment, and test methods that.are to be used to measure radionuclide emissions from exhaust stacks that are designated as National Emission Standards for Hazardous Air Pollutant (NESHAP) stacks. Designated NESHAP stacks are those that have the potential to cause any member of the public to receive an effective dose equivalent (EDE) greater than or equal to 0.1 mrem/year, assuming all emission controls were removed. Tank Farms currently has 33 exhaust stacks, 15 of which are designated NESHAP stacks. This document assesses the compliance status of the monitoring and sampling systems for the designated NESHAP stacks.

  17. Gridded National Inventory of U.S. Methane Emissions

    Science.gov (United States)

    Maasakkers, Joannes D.; Jacob, Daniel J.; Sulprizio, Melissa P.; Turner, Alexander J.; Weitz, Melissa; Wirth, Tom; Hight, Cate; DeFigueiredo, Mark; Desai, Mausami; Schmeltz, Rachel; hide

    2016-01-01

    We present a gridded inventory of US anthropogenic methane emissions with 0.1 deg x 0.1 deg spatial resolution, monthly temporal resolution, and detailed scale dependent error characterization. The inventory is designed to be onsistent with the 2016 US Environmental Protection Agency (EPA) Inventory of US Greenhouse Gas Emissionsand Sinks (GHGI) for 2012. The EPA inventory is available only as national totals for different source types. We use a widerange of databases at the state, county, local, and point source level to disaggregate the inventory and allocate the spatial and temporal distribution of emissions for individual source types. Results show large differences with the EDGAR v4.2 global gridded inventory commonly used as a priori estimate in inversions of atmospheric methane observations. We derive grid-dependent error statistics for individual source types from comparison with the Environmental Defense Fund (EDF) regional inventory for Northeast Texas. These error statistics are independently verified by comparison with the California Greenhouse Gas Emissions Measurement (CALGEM) grid-resolved emission inventory. Our gridded, time-resolved inventory provides an improved basis for inversion of atmospheric methane observations to estimate US methane emissions and interpret the results in terms of the underlying processes.

  18. Radionuclide concentrations in pinto beans, sweet corn, and zucchini squash grown in Los Alamos Canyon at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Fresquez, P.R.; Mullen, M.A.; Naranjo, L. Jr.; Armstrong, D.R.

    1997-05-01

    Pinto beans, sweet corn, and zucchini squash (Cucurbita pepo var. black beauty) were grown in a randomized complete-block field/pot experiment at a site that contained the highest observed levels of surface gross gamma radioactivity within Los Alamos Canyon (LAC) at Los Alamos National Laboratory. Soils as well as washed edible and nonedible crop tissues were analyzed for various radionuclides and heavy metals . Most radionuclides, with the exception of 3 H and tot U, in soil from LAC were detected in significantly higher concentrations (p -1 . This dose was below the International Commission on Radiological Protection permissible dose limit (PDL) of 100 mrem y -1 from all pathways; however, the addition of other internal and external exposure route factors may increase the overall dose over the PDL. Also, the risk of an excess cancer fatality, based on 74 mrem y -1 , was 3.7 x 10 -5 (37 in a million), which is above the Environmental Protection Agency's (acceptable) guideline of one in a million. 31 refs., 15 tabs

  19. 76 FR 4155 - National Emission Standards for Hazardous Air Pollutants for Source Categories: Gasoline...

    Science.gov (United States)

    2011-01-24

    ... 63 National Emission Standards for Hazardous Air Pollutants for Source Categories: Gasoline Distribution Bulk Terminals, Bulk Plants, and Pipeline Facilities; and Gasoline Dispensing Facilities; Final...] RIN 2060-AP16 National Emission Standards for Hazardous Air Pollutants for Source Categories: Gasoline...

  20. Heavy element radionuclides (Pu, Np, U) and 137Cs in soils collected from the Idaho National Engineering and Environmental Laboratory and other sites in Idaho, Montana, and Wyoming

    International Nuclear Information System (INIS)

    Beasley, T.M.; Rivera, W. Jr.; Liszewski, M.J.; Orlandini, K.A.

    1998-10-01

    The isotopic composition of Pu in soils on and near the Idaho National Engineering and Environmental Laboratory (INEEL) has been determined in order to apportion the sources of the Pu into those derived from stratospheric fallout, regional fallout from the Nevada Test Site (NTS), and facilities on the INEEL site. Soils collected offsite in Idaho, Montana, and Wyoming were collected to further characterize NTS fallout in the region. In addition, measurements of 237 Np and 137 Cs were used to further identify the source of the Pu from airborne emissions at the Idaho Chemical Processing Plant (ICPP) or fugitive releases from the Subsurface Disposal Area (SDA) in the Radioactive Waste Management Complex (RWMC). There is convincing evidence from this study that 241 Am, in excess of that expected from weapons-grade Pu, constituted a part of the buried waste at the SDA that has subsequently been released to the environment. Measurements of 236 U in waters from the Snake River Plain aquifer and a soil core near the ICPP suggest that this radionuclide may be a unique interrogator of airborne releases from the ICPP. Neptunium-237 and 238 Pu activities in INEEL soils suggest that airborne releases of Pu from the ICPP, over its operating history, may have recently been overestimated

  1. 76 FR 42052 - National Emission Standards for Hazardous Air Pollutants From Petroleum Refineries

    Science.gov (United States)

    2011-07-18

    ...-AO55 National Emission Standards for Hazardous Air Pollutants From Petroleum Refineries AGENCY... the National Emission Standards for Hazardous Air Pollutants From Petroleum Refineries. EPA is now... signed a final rule amending the National Emission Standards for Hazardous Air Pollutants From Petroleum...

  2. Measurement of radionuclides in waste packages

    Science.gov (United States)

    Brodzinski, R.L.; Perkins, R.W.; Rieck, H.G.; Wogman, N.A.

    1984-09-12

    A method is described for non-destructively assaying the radionuclide content of solid waste in a sealed container by analysis of the waste's gamma-ray spectrum and neutron emissions. Some radionuclides are measured by characteristic photopeaks in the gamma-ray spectrum; transuranic nuclides are measured by neutron emission rate; other radionuclides are measured by correlation with those already measured.

  3. Radionuclide characterization of subsurface soil on the site of building 3505 at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Alexander, W.A.; Oakes, T.W.; Eldridge, J.S.; Huang, S.; Hubbard, H.M.

    1982-12-01

    Ninety-two samples at varying depths were collected from 25 cores. Sample tubes were driven into the ground and segments of soil cores were retrieved at depths from the ground surface to subsurface consolidated material. forty samples of the 92 collected had detectable gamma activities [i.e., > 2 x 10 - 2 Bq/g (0.5 pCi/g)] of 137 Cs. However, only four samples, all from the same borehole, were found to have significant amounts of 137 Cs with a maximum of 1.7 x 10 3 Bq/g (4.6 x 10 4 pCi/g). These four samples also contained the highest activities of other radionuclides ( 60 Co, 90 Sr, 235 U, 238 U, 239 Pu, and 241 Am). These subsamples came from core number 4DD, which was the deepest core collected. Core 4DD was taken at the southwest corner of the site, which is at the lower elevation of the site. Since most of the activity in this core was found below the bedrock (or shale) in the groundwater region, the contamination is probably not from Building 3505. Additional investigation in the area around core location 4DD will be required to determine the extent of contamination

  4. Synthesis of Poly[APMA]-DOTA-64Cu Conjugates for Interventional Radionuclide Therapy of Prostate Cancer: Assessment of Intratumoral Retention by Micro–Positron Emission Tomography

    Directory of Open Access Journals (Sweden)

    Jianchao Yuan

    2007-01-01

    Full Text Available To develop new radiopharmaceuticals for interventional radionuclide therapy of locally recurrent prostate cancer, poly[N-(3-aminopropylmethacrylamide] [poly(APMA] polymers were synthesized by free radical precipitation polymerization in acetonedimethylsulfoxide using N,N‘-azobis(isobutyronitrile as the initiator. The polymers were characterized with nuclear magnetic resonance, size exclusion chromatography, and dynamic light scattering (Mn 5 2.40 × 104, Mw/Mn = 1.87. Subsequently, poly[APMA] was coupled with 1,4,7,10-tetraazacyclododecane-1,4,7,10-tetraacetic acid (DOTA using 1-(3-dimethylaminopropyl-3-ethylcarbodiimide hydrochloride as an activator, followed by conjugation with 64Cu radionuclide. Prolonged retention of poly[APMA]-DOTA-64Cu conjugates within the tumor tissues was demonstrated by micro–positron emission tomography at 24 hours following intra-tumoral injection of the conjugates to human prostate xenografts in mice. The data suggest that the poly[APMA]-DOTA-64Cu conjugates might be useful for interventional radionuclide therapy of locally recurrent prostate cancer in humans.

  5. Pacific Northwest Laboratory facilities radionuclide inventory assessment CY 1992-1993

    International Nuclear Information System (INIS)

    Sula, M.J.; Jette, S.J.

    1994-09-01

    Assessments for evaluating compliance with airborne radionuclide emission monitoring requirements in the National Emission Standards for Hazardous Air Pollutants (NESHAPs - U.S. Code of Federal Regulations, Title 40 Part 61, Subparts H and I) were performed for 33 buildings at the U.S. Department of Energy's (DOE) Pacific Northwest Laboratory on the Hanford Site, and for five buildings owned and operated by Battelle, Pacific Northwest Laboratories in Richland, Washington. The assessments were performed using building radionuclide inventory data obtained in 1992 and 1993. Results of the assessments are summarized in Table S.1 for DOE-PNL buildings and in Table S.2 for Battelle-owned buildings. Based on the radionuclide inventory assessments, four DOE-PNL buildings (one with two emission points) require continuous sampling for radionuclides per 40 CFR 61. None of the Battelle-owned buildings require continuous emission sampling

  6. National plan of allocation of CO2 emission quotas

    International Nuclear Information System (INIS)

    2006-01-01

    The directive 2003/87/CE of the European parliament and council from October 13, 2003 establishes a trading system of CO 2 emission quotas for some companies of the energy generation industry, of the manufacturing industry and of services. These quotas are tradable and negotiable and an initial amount of quotas is allocated to these companies according to their facilities in concern. The national plan of quotas allocation must precise the total amount of tradable emissions and its share among the different sectors of activity and facilities. The first project of allocation plan was transmitted to the European Commission on July 6, 2004 after its public consultation between June 8 and June 29 2004. Modifications have been added to meet the requests of the Commission and the French plan was finally approved on December 17, 2004 for an annual amount of 156.51 Mt of CO 2 quotas during the 2005-2007 period. This paper precises the modifications requested by the commission, the modifications of the French juridical system necessary to complete the implementation of the French part of the European quotas trading system, the elaboration of the next allocation plan for the 2008-2012 period, and the link between the European emissions trading system and the 'joint implementation' and 'clean development ' mechanisms implemented by the Kyoto protocol. (J.S.)

  7. Emission projections 2008-2012 versus national allocation plans II

    International Nuclear Information System (INIS)

    Neuhoff, Karsten; Ferrario, Federico; Grubb, Michael; Gabel, Etienne; Keats, Kim

    2006-01-01

    We compare the national allocation plans (NAPs), proposed and submitted by EU Member States as of October 2006, with our estimations for CO 2 emissions by the installations covered by these NAPs. The collective allocations proposed under phase II NAPs exceed the historic trend of emissions extrapolated forward. Using our projections we find, depending on uncertainty in fuel prices, economic growth rates, performance of the non-power sector and CDM/JI availability, a 15% chance of a 'dead market' with emissions below cap even at zero prices. With an expected inflow of committed CDM/JI credits of 100 MtCO 2 /year, allowance supply will exceed demand in 50% of cases without any carbon price, and in 80% of our euros20/tCO 2 scenarios. Banking of allowances towards post-2012 conditions could create additional demand, but this is difficult to anticipate and conditional on policy evolution. The proposed phase II NAPs would result in low prices and only small volumes of CDM/JI would enter the EU ETS. CDM/JI would almost exclusively be public-sector funded, placing the cost of Kyoto compliance entirely upon governments. (Author)

  8. Dose Assessment of Los Alamos National Laboratory-Derived Residual Radionuclides in Soils within Tract A-18-2 for Land Conveyance and Transfer Decisions

    Energy Technology Data Exchange (ETDEWEB)

    Ruedig, Elizabeth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Whicker, Jeffrey Jay [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2018-01-26

    In 2017, soil sampling for radiological materials was conducted within Tract A-18-2 at Los Alamos National Laboratory (LANL) for land conveyance decisions. Measurements of radionuclides in soil samples were evaluated against a recreational use scenario, and all measurements were below screening action levels for each radionuclide. The total estimated dose was less than 1 mrem/yr (<10 μSv/yr) for a hypothetical recreational user (compared with a dose limit of 25 mrem/yr [250 μSv/yr]). Dose estimates were based on the 95% upper confidence levels for radionuclide concentrations within the Tract. Dose estimates less than 3 mrem/yr are considered to be as low as reasonably achievable (ALARA), therefore no follow-up analysis was conducted. Release of this property is consistent with the requirements of DOE Order 458.1 (DOE 2013) and Policy 412 (LANL 2014).

  9. Radionuclide trap

    International Nuclear Information System (INIS)

    McGuire, J.C.

    1978-01-01

    The deposition of radionuclides manganese-54, cobalt-58 and cobalt-60 from liquid sodium coolant is controlled by providing surfaces of nickel or high nickel alloys to extract the radionuclides from the liquid sodium, and by providing surfaces of tungsten, molybdenum or tantalum to prevent or retard radionuclide deposition

  10. 77 FR 3223 - National Emissions Standards for Hazardous Air Pollutants: Mineral Wool Production and Wool...

    Science.gov (United States)

    2012-01-23

    ... Emission Standards for Hazardous Air Pollutants: Mineral Wool Production Risk and Technology Review..., Administrative practice and procedure, Air pollution control, Hazardous substances, Intergovernmental relations... National Emissions Standards for Hazardous Air Pollutants: Mineral Wool Production and Wool Fiberglass...

  11. 77 FR 33811 - National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion...

    Science.gov (United States)

    2012-06-07

    ... 63 National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion Engines; New Source Performance Standards for Stationary Internal Combustion Engines; Proposed Rule #0;#0... Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion Engines; New Source...

  12. Spectrum analysis of national greenhouse gas emission: a case study of Germany

    Energy Technology Data Exchange (ETDEWEB)

    Su, Meirong [Dongguan University of Technology, School of Chemistry and Environmental Engineering, Dongguan, Guangdong Province (China); Beijing Normal University, State Key Joint Laboratory of Environment Simulation and Pollution Control, School of Environment, Beijing (China); Technical University of Munich, Strategic Landscape Planning and Management, Freising (Germany); Pauleit, Stephan; Xu, Chao [Technical University of Munich, Strategic Landscape Planning and Management, Freising (Germany)

    2016-10-15

    It is essential to abstract the key information from accounting results of greenhouse gas (GHG) emissions because it can provide a highly generalized and clear picture of GHG emissions, which is especially helpful for the public and policy makers. To clearly display the composition of GHG emissions, the concept of spectrum analysis is introduced and defined in this paper. Next, a multilayer analysis framework for national GHG emissions was proposed, which is represented by a pyramid of three layers: total emissions (first layer), emissions decomposed by gas type or sector (second layer), and emissions decomposed by both gas type and sector (third layer). Based on the analysis results from the first to third layers, the main compositional information of national GHG emissions was gradually summarized and analyzed until a spectrum of GHG emissions was acquired. The spectrum of GHG emissions displays the compositional structure of national GHG emissions in the different layers, which is helpful in identifying priorities for emissions reduction. A case study of Germany's GHG emissions during 1990-2012 was conducted, which indicated that CO{sub 2} and the energy sector were the biggest contributors to the total GHG emissions. Some suggestions for reducing GHG emissions are offered based on the obtained results. And the potential development of spectrum analysis for GHG emissions is also expected from aspects of both research and technology. (orig.)

  13. Spectrum analysis of national greenhouse gas emission: a case study of Germany

    International Nuclear Information System (INIS)

    Su, Meirong; Pauleit, Stephan; Xu, Chao

    2016-01-01

    It is essential to abstract the key information from accounting results of greenhouse gas (GHG) emissions because it can provide a highly generalized and clear picture of GHG emissions, which is especially helpful for the public and policy makers. To clearly display the composition of GHG emissions, the concept of spectrum analysis is introduced and defined in this paper. Next, a multilayer analysis framework for national GHG emissions was proposed, which is represented by a pyramid of three layers: total emissions (first layer), emissions decomposed by gas type or sector (second layer), and emissions decomposed by both gas type and sector (third layer). Based on the analysis results from the first to third layers, the main compositional information of national GHG emissions was gradually summarized and analyzed until a spectrum of GHG emissions was acquired. The spectrum of GHG emissions displays the compositional structure of national GHG emissions in the different layers, which is helpful in identifying priorities for emissions reduction. A case study of Germany's GHG emissions during 1990-2012 was conducted, which indicated that CO_2 and the energy sector were the biggest contributors to the total GHG emissions. Some suggestions for reducing GHG emissions are offered based on the obtained results. And the potential development of spectrum analysis for GHG emissions is also expected from aspects of both research and technology. (orig.)

  14. Miscellaneous Coating Manufacturing: National Emission Standards for Hazardous Air Pollutants (NESHAP)

    Science.gov (United States)

    The national emission standards for hazardous air pollutants for miscellaneous coating manufacturing. Includes summary, rule history, compliance and implementation information, federal registry citations.

  15. Reinforced Plastic Composites Production: National Emission Standards for Hazardous Air Pollutants

    Science.gov (United States)

    National emissions standards for hazardous air pollutants for reinforced plastic composites production facilities. Regulates production and ancillary processes used to manufacture products with thermoset resins and gel coats.

  16. General guidance and procedures for estimating and reporting national GHG emissions for agriculture

    International Nuclear Information System (INIS)

    Rypdal, K.

    2002-01-01

    Greenhouse gas (GHG) emissions from agriculture account for a large share of total GHG emissions in most countries. Methane from ruminants, animal manure and rice fields, and nitrous oxide from agricultural soils are among the most important sources. In general, these emission estimates also are more uncertain than most other parts of the GHG emission inventory. IPCC has developed guidelines for estimating and reporting emissions of GHG. These guidelines shall be followed to secure complete, consistent, accurate and transparent reporting of emissions. However, the recommended methodologies are tiered, and choice of methods shall preferably reflect national circumstances, the national importance of a source, and different resources to prepare inventories. A country may also apply a national methodology given that it is well documented and not in conflict with good practice. Emission data reported under the United Nation Framework Convention on Climate Change are subject to external control, and the methodologies are reviewed by experts on agricultural inventories. (au)

  17. Radionuclides in shallow groundwater at Solid Waste Storage Area 5 North, Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Ashwood, T.L.; Marsh, J.D. Jr.

    1994-04-01

    This report presents a compilation of groundwater monitoring data from Solid Waste Storage Area (SWSA) 5 North at Oak Ridge National Laboratory (ORNL) between November 1989 and September 1993. Monitoring data were collected as part of the Active Sites Environmental Monitoring Program that was implemented in 1989 in response to DOE Order 5820.2A. SWSA 5 North was established for the retrievable storage of transuranic (TRU) wastes in 1970. Four types of storage have been used within SWSA 5 North: bunkers, vaults, wells, and trenches. The fenced portion of SWSA 5 North covers about 3.7 ha (9 acres) in the White Oak Creek watershed south of ORNL. The area is bounded by White Oak Creek and two ephemeral tributaries of White Oak Creek. Since 1989, groundwater has been monitored in wells around SWSA 5 North. During that time, elevated gross alpha contamination (reaching as high as 210 Bq/L) has consistently been detected in well 516. This well is adjacent to burial trenches in the southwest corner of the area. Water level measurements in wells 516 and 518 suggest that water periodically inundates the bottom of some of those trenches. Virtually all of the gross alpha contamination is generated by Curium 244 and Americium 241. A special geochemical investigation of well 516 suggests that nearly all of the Curium 44 and Americium 241 is dissolved or associated with dissolved organic matter. These are being transported at the rate of about 2 m/year from the burial trenches, through well 516, to White Oak Creek, where Curium 244 has been detected in a few bank seeps. Concentrations at these seeps are near detection levels (<1 Bq/L)

  18. Radionuclides in shallow groundwater at Solid Waste Storage Area 5 North, Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Ashwood, T.L.; Marsh, J.D. Jr.

    1994-04-01

    This report presents a compilation of groundwater monitoring data from Solid Waste Storage Area (SWSA) 5 North at Oak Ridge National Laboratory (ORNL) between November 1989 and September 1993. Monitoring data were collected as part of the Active Sites Environmental Monitoring Program that was implemented in 1989 in response to DOE Order 5820.2A. SWSA 5 North was established for the retrievable storage of transuranic (TRU) wastes in 1970. Four types of storage have been used within SWSA 5 North: bunkers, vaults, wells, and trenches. The fenced portion of SWSA 5 North covers about 3.7 ha (9 acres) in the White Oak Creek watershed south of ORNL. The area is bounded by White Oak Creek and two ephemeral tributaries of White Oak Creek. Since 1989, groundwater has been monitored in wells around SWSA 5 North. During that time, elevated gross alpha contamination (reaching as high as 210 Bq/L) has consistently been detected in well 516. This well is adjacent to burial trenches in the southwest corner of the area. Water level measurements in wells 516 and 518 suggest that water periodically inundates the bottom of some of those trenches. Virtually all of the gross alpha contamination is generated by Curium 244 and Americium 241. A special geochemical investigation of well 516 suggests that nearly all of the Curium 44 and Americium 241 is dissolved or associated with dissolved organic matter. These are being transported at the rate of about 2 m/year from the burial trenches, through well 516, to White Oak Creek, where Curium 244 has been detected in a few bank seeps. Concentrations at these seeps are near detection levels (<1 Bq/L).

  19. National Emission Standards for Hazardous Air Pollutants Calendar Year 2001

    International Nuclear Information System (INIS)

    Townsend, Y. E.

    2002-01-01

    The Nevada Test Site (NTS) is operated by the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Operations Office (NNSA/NV) as the site for nuclear weapons testing, now limited to readiness activities, experiments in support of the national Stockpile Stewardship Program, and the activities listed below. Located in Nye County, Nevada, the site's southeast corner is about 88 km (55 mi) northwest of the major population center, Las Vegas, Nevada. The NTS covers about 3,561 km2 (1,375 mi2), an area larger than Rhode Island. Its size is 46 to 56 km (28 to 35 mi) east to west and from 64 to 88 km (40 to 55 mi) north to south. The NTS is surrounded, except on the south side, by public exclusion areas (Nellis Air Force Range [NAFR]) that provide another 24 to 104 km (15 to 65 mi) between the NTS and public lands (Figure 1.0). The NTS is characterized by desert valley and Great Basin mountain topography, with a climate, flora, and fauna typical of the southwest deserts. Population density within 150 km (93 mi) of the NTS is only about 0.2 persons per square kilometer, excluding the Las Vegas area. Restricted access, low population density in the surrounding area, and extended wind transport times are advantageous factors for the activities conducted at the NTS. Surface waters are scarce on the NTS, and slow-moving groundwater is present hundreds to thousands of feet below the land surface. The sources of radionuclides include current and previous activities conducted on the NTS (Figure 2.0). The NTS was the primary location for testing of nuclear explosives in the Continental U.S. between 1951 and 1992. Historical testing above or at ground surface has included (1) atmospheric testing in the 1950s and early 1960s, (2) earth-cratering experiments, and (3) open-air nuclear reactor and rocket engine testing. Since the mid-1950s, testing of nuclear explosive devices has occurred underground in drilled vertical holes or in mined tunnels (DOE 1996a

  20. Joint release rate estimation and measurement-by-measurement model correction for atmospheric radionuclide emission in nuclear accidents: An application to wind tunnel experiments.

    Science.gov (United States)

    Li, Xinpeng; Li, Hong; Liu, Yun; Xiong, Wei; Fang, Sheng

    2018-03-05

    The release rate of atmospheric radionuclide emissions is a critical factor in the emergency response to nuclear accidents. However, there are unavoidable biases in radionuclide transport models, leading to inaccurate estimates. In this study, a method that simultaneously corrects these biases and estimates the release rate is developed. Our approach provides a more complete measurement-by-measurement correction of the biases with a coefficient matrix that considers both deterministic and stochastic deviations. This matrix and the release rate are jointly solved by the alternating minimization algorithm. The proposed method is generic because it does not rely on specific features of transport models or scenarios. It is validated against wind tunnel experiments that simulate accidental releases in a heterogonous and densely built nuclear power plant site. The sensitivities to the position, number, and quality of measurements and extendibility of the method are also investigated. The results demonstrate that this method effectively corrects the model biases, and therefore outperforms Tikhonov's method in both release rate estimation and model prediction. The proposed approach is robust to uncertainties and extendible with various center estimators, thus providing a flexible framework for robust source inversion in real accidents, even if large uncertainties exist in multiple factors. Copyright © 2017 Elsevier B.V. All rights reserved.

  1. Development of methods for activity determination for radionuclides with double decay emission β- β+ / electron capture - application to the standardization of 192Ir, 152Eu and 186 Re

    International Nuclear Information System (INIS)

    Hilario, Katia Aparecida Fonseca

    2002-01-01

    In the present work alternative procedures have been developed for standardization of radionuclides with double decay, β - β + / electron capture using the 4πβ-γ coincidence technique, applying different systems. Two 4πβ-γ coincidence systems were used: one with a 4π gas-flow proportional counter coupled to a pair of NaI(Tl) scintillators and the other one with the same type of proportional counter coupled to HPGe detector. The radionuclides selected for this standardization, due to great interest in nuclear medicine, detector calibration and industrial radiography, were 192 Ir, 152 Eu and 186 Re. The first and the second were part of international comparisons sponsored by the Bureau International des Poids et Mesures (BIPM), France, who supplied the radioactive solution. For 186 Re, the gamma-ray emission probability per decay was measured by means REGe spectrometer system, previously calibrated with standard ampoules. All the uncertainties involved were treated rigorously, by means of covariance analysis. (author)

  2. National Emissions Inventory Vehicle Miles Traveled, U.S., 2014, EPA/OAR/OAQPS/AQAD

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web service contains layers that depict gridded Vehicle Miles Traveled (VMT) for 2014 from the National Emission Inventory (NEI). The default 2014 National...

  3. Gold-195m first-pass radionuclide ventriculography, thallium-201 single-photon emission CT, and 12-lead ECG stress testing as a combined procedure

    International Nuclear Information System (INIS)

    Kipper, S.L.; Ashburn, W.L.; Norris, S.L.; Rimkus, D.S.; Dillon, W.A.

    1985-01-01

    Graded, sequential, rest/exercise, gold-195m, first-pass ventriculography and thallium-201 (Tl-201) single-photon emission computed tomography (SPECT) were performed simultaneously during a single, electrocardiograph-monitored, bicycle stress test in 24 individuals. The technical aspects and logistics involved in performing this combined radionuclide study are stressed in this preliminary report. Fourteen healthy volunteers each had a normal left ventricular ejection fraction and wall-motion response, along with normal T1-201 perfusion and washout, as determined by both visual and quantitative analysis of the tomographic sections. Each of ten patients with coronary artery disease had at least one abnormality of these parameters. The authors suggest that it is technically feasible to evaluate both cardiac function and myocardial perfusion simultaneously by combing Au-195m ventriculography and Tl-201 SPECT imaging into a single, noninvasive, diagnostic package

  4. Preclosure probabilistic assessment of the Canadian concept for used fuel disposal focussing on key radionuclides and exposure pathways for routine emissions

    International Nuclear Information System (INIS)

    Russell, S.B.

    1996-01-01

    The Canadian Nuclear Fuel Waste Management Program was initiated in 1978 to develop a concept for safe disposal of nuclear fuel waste (intact used nuclear fuel or high-level waste from any future reprocessing of used fuel) from CANDU reactors. The concept includes the immobilization of nuclear fuel waste and emplacement of the waste in an engineered vault, deep underground in a stable rock formation within the Canadian Shield. In 1994, AECL submitted an environmental and safety assessment of the disposal concept in the form of an Environmental Impact Statement or EIS for regulatory, scientific and public reviews. Ontario Hydro's contribution to the EIS included the preclosure assessment consisting of the safety and environmental implications of the construction, operation and decommissioning (closure) of a conceptual used-fuel disposal centre (UFDC), plus transportation of used fuel from storage at reactor sites to the UFDC. In the EIS, the environmental impact from routine emissions from the UFDC during the operation phase was calculated in a deterministic mode using single-valued constants representing the geometric mean or the average value of the input parameters in the preclosure model PREAC (Preclosure Radiological Environmental Assessment Code). A qualitative estimate of the range of uncertainty associated with the preclosure model dose predictions was about an order of magnitude based on a review of the expected range of input parameter values. This paper examines the time-behaviour of the preclosure system and provides a quantitative estimate of the uncertainty, as determined through the use of probabilistic techniques, associated with the potential radiological impact from the same chronic UFDC radionuclide emissions during the preclosure phase. The individual dose to a member of the critical group assumed to be living near the UFDC has been assessed for selected key radionuclides and exposure pathways identified in the EIS. The purpose of this post

  5. Performance study and influence of radiation emission energy and soil contamination level on γ-radiation shielding of stabilised/solidified radionuclide-polluted soils

    International Nuclear Information System (INIS)

    Falciglia, Pietro P.; Puccio, Valentina; Romano, Stefano; Vagliasindi, Federico G.A.

    2015-01-01

    This work focuses on the stabilisation/solidification (S/S) of radionuclide-polluted soils at different 232 Th levels using Portland cement alone and with barite aggregates. The potential of S/S was assessed applying a full testing protocol and calculating γ-radiation shielding (γRS) index, that included the measurement of soil radioactivity before and after the S/S as a function of the emission energy and soil contamination level. The results indicate that setting processes are strongly dependent on the contaminant concentration, and for contamination level higher than 5%, setting time values longer than 72 h. The addition of barite aggregates to the cement gout leads to a slight improvement of the S/S performance in terms of durability and contaminant leaching but reduces the mechanical resistance of the treated soils samples. Barite addition also causes an increase in the γ-rays shielding properties of the S/S treatment up to about 20%. Gamma-ray measurements show that γRS strongly depends on the energy, and that the radioactivity with the contamination level was governed by a linear trend, while, γRS index does not depend on the radionuclide concentration. Results allow the calculated γRS values and those available from other experiments to be applied to hazard radioactive soil contaminations. - Highlights: • We assess the effects of 232 Th contamination on performance of S/S treated soil. • We assess the γ-radiation shielding of the S/S materials as a function of energy. • We report a full testing protocol for assessing S/S resistance performance. • Emission energy influences the γ radiation shielding of the S/S. • Barite gives high γ-radiation shielding and low contaminant leaching

  6. National fossil fuels consumption: Estimates of CO2 emissions and thermic pollution

    International Nuclear Information System (INIS)

    Mariani, Mario; Casale, Francesco

    1997-01-01

    The study on the basis of the national energy consumption from 1988 to 1994, estimates CO 2 emission rates produced by the most relevant hydrocarbons involved in the technological combustion processes and assess the potential thermic impact on the environment. Two calculation procedures have been developed taking into account once emission factors and other emission indexes in order to verify the two estimates. Besides, the work determines the national trend of CO 2 emission with regard to the aim for the stabilization of carbon dioxide emissions at 1990 levels by 2000

  7. Impacts of nationally determined contributions on 2030 global greenhouse gas emissions: uncertainty analysis and distribution of emissions

    Science.gov (United States)

    Benveniste, Hélène; Boucher, Olivier; Guivarch, Céline; Le Treut, Hervé; Criqui, Patrick

    2018-01-01

    Nationally Determined Contributions (NDCs), submitted by Parties to the United Nations Framework Convention on Climate Change before and after the 21st Conference of Parties, summarize domestic objectives for greenhouse gas (GHG) emissions reductions for the 2025-2030 time horizon. In the absence, for now, of detailed guidelines for the format of NDCs, ancillary data are needed to interpret some NDCs and project GHG emissions in 2030. Here, we provide an analysis of uncertainty sources and their impacts on 2030 global GHG emissions based on the sole and full achievement of the NDCs. We estimate that NDCs project into 56.8-66.5 Gt CO2eq yr-1 emissions in 2030 (90% confidence interval), which is higher than previous estimates, and with a larger uncertainty range. Despite these uncertainties, NDCs robustly shift GHG emissions towards emerging and developing countries and reduce international inequalities in per capita GHG emissions. Finally, we stress that current NDCs imply larger emissions reduction rates after 2030 than during the 2010-2030 period if long-term temperature goals are to be fulfilled. Our results highlight four requirements for the forthcoming ‘climate regime’: a clearer framework regarding future NDCs’ design, an increasing participation of emerging and developing countries in the global mitigation effort, an ambitious update mechanism in order to avoid hardly feasible decarbonization rates after 2030 and an anticipation of steep decreases in global emissions after 2030.

  8. Comparison of models used for national agricultural ammonia emission inventories in Europe

    DEFF Research Database (Denmark)

    Reidy, B; Dämmgen, U; Döhler, H

    2008-01-01

    and harmonized the available knowledge on emission factors (EFs) for nitrogen (N)-flow emission calculation models and initiated a new generation of emission inventories. As a first step in summarizing the available knowledge, six N-flow models, used to calculate national NH3 emissions from agriculture...... the variation in the results generated awareness and consensus concerning available scientific data and the importance of specific processes not yet included in some models...

  9. Radionuclide cisternography

    International Nuclear Information System (INIS)

    Song, H.H.

    1980-01-01

    The purpose of this thesis is to show that radionuclide cisternography makes an essential contribution to the investigation of cerebrospinal fluid (CSF) dynamics, especially for the investigation of hydrocephalus. The technical details of radionuclide cisternography are discussed, followed by a description of the normal and abnormal radionuclide cisternograms. The dynamics of CFS by means of radionuclide cisternography were examined in 188 patients in whom some kind of hydrocephalus was suspected. This study included findings of anomalies associated with hydrocephalus in a number of cases, such as nasal liquorrhea, hygromas, leptomeningeal or porencephalic cysts. The investigation substantiates the value of radionuclide cisternography in the diagnosis of disturbances of CSF flow. The retrograde flow of radiopharmaceutical into the ventricular system (ventricular reflux) is an abnormal phenomenon indicating the presence of communicating hydrocephalus. (Auth.)

  10. Disproportionality in Power Plants’ Carbon Emissions: A Cross-National Study

    Science.gov (United States)

    Jorgenson, Andrew; Longhofer, Wesley; Grant, Don

    2016-01-01

    Past research on the disproportionality of pollution suggests a small subset of a sector’s facilities often produces the lion’s share of toxic emissions. Here we extend this idea to the world’s electricity sectors by calculating national-level disproportionality Gini coefficients for plant-level carbon emissions in 161 nations based on data from 19,941 fossil-fuel burning power plants. We also evaluate if disproportionalities in plant-level emissions are associated with increased national carbon emissions from fossil-fuel based electricity production, while accounting for other well-established human drivers of greenhouse gas emissions. Results suggest that one potential pathway to decreasing nations’ greenhouse gas emissions could involve reducing disproportionality among fossil-fuel power plants by targeting those plants in the upper end of the distribution that burn fuels more inefficiently to produce electricity. PMID:27363677

  11. Radiation and decay characteristics of long-lived radionuclides used in the national economy and scientific research (evaluated data)

    International Nuclear Information System (INIS)

    Chechev, V.P.; Chukreev, F.E.

    1991-10-01

    This handbook contains new evaluated data for a series of radionuclides distributed by the All-Union Organization ''Izotop''. It is intended for use by the wide range of scientists and engineers using these isotopes in their work. (author). 13 refs

  12. Evaluation of compliance with national legislation on emissions in Portugal

    Energy Technology Data Exchange (ETDEWEB)

    Joao F.P. Gomes [Instituto de Soldadura e Qualidade, Oeiras (Portugal). Centro de Tecnologias Ambientais

    2005-04-01

    More than 13 years after publication of the first air quality laws in Portugal and more than 10 years after the publication of the respective emission limits, it seems appropriate to analyze the degree of compliance by the Portuguese manufacturing industry. Using the data from emission measurements made regularly by the Instituto de Soldadura e Qualidade, the only officially accredited laboratory according to standard ISO 17025. The author analyzed a set of 400 sources in terms of compliance with the emission limits regarding total suspended particulates, sulfur dioxide, nitrogen oxides, and volatile organic compounds. He evaluated compliance through a nondimensional parameter and plotted it versus the emission flow rate to derive conclusions: the results indicate that emission limits are generally met regarding sulfur dioxide and nitrogen oxides but not for the other pollutants considered in this study. However, noncompliance occurs mainly for very low emission flow rates, which suggests some alterations in the emission limits, which are being revised at the moment. These alterations will include the exemption of measurements in minor sources. 7 refs., 8 figs., 7 tabs.

  13. Evaluation of compliance with national legislation on emissions in Portugal.

    Science.gov (United States)

    Gomes, João F P

    2005-04-01

    More than 13 years after publication of the first air quality laws in Portugal and more than 10 years after the publication of the respective emission limits, it seems appropriate to analyze the degree of compliance by the Portuguese manufacturing industry. Using the data from emission measurements made regularly by the Instituto de Soldadura e Qualidade, the only officially accredited laboratory according to standard ISO 17025, I analyzed a set of approximately 400 sources in terms of compliance with the emission limits regarding total suspended particulates, sulfur dioxide, nitrogen oxides, and volatile organic compounds. I evaluated compliance through a nondimensional parameter and plotted it versus the emission flow rate to derive conclusions: the results indicate that emission limits are generally met regarding sulfur dioxide and nitrogen oxides but not for the other pollutants considered in this study. However, noncompliance occurs mainly for very low emission flow rates, which suggests some alterations in the emission limits, which are being revised at the moment. These alterations will include the exemption of measurements in minor sources.

  14. Estimating national exhaust emissions from railway vehicles in Turkey

    International Nuclear Information System (INIS)

    Dincer, Faruk; Elbir, Tolga

    2007-01-01

    The estimated exhaust emissions from railway vehicles in Turkey were presented. The emissions of nitrogen oxides (NO x ), hydrocarbon compounds (HC), carbon monoxide (CO), particulate matter (PM), sulfur dioxide (SO 2 ) and carbon dioxide (CO 2 ) from the diesel locomotives and railcars were calculated using the railway traffic data recorded by Turkish State Railways (TSR) for the period of 2000-2005. EPA emission factors were used for different vehicle types and operation modes such as shunting and line-hauling. Total emissions from railway vehicles in Turkey were estimated as 384 t y - 1 for HC, 1016 t y - 1 for CO, 6799 t y - 1 for NO X , 256 t y - 1 for PM, 357 t y - 1 for SO 2 and 383 537 t y - 1 for CO 2 for the year 2005. The distribution of emissions with respect to type of railway vehicles shows that the mainline locomotives contribute ∝ 91% to the total emissions. The increases of 22%, 39% and 49% in the current numbers of mainline locomotives, shunting locomotives and diesel railcars, respectively corresponding to the full capacity of railway network in Turkey will increase the annual emissions to 431 t y - 1 for HC, 1121 t y - 1 for CO, 7399 t y - 1 for NO X , 342 t y - 1 for PM, 552 t y - 1 for SO 2 and 420 256 t y - 1 for CO 2 . Total railway emissions constitute 0.15%, 0.08% and 4.21% of total Turkish traffic emissions for HC, CO and NO X , respectively. (author)

  15. National Emissions Trading; Interim Report by the Committee on the Kyoto mechanisms

    International Nuclear Information System (INIS)

    2001-01-01

    By emissions trading is meant that operators eligible for emissions trading can trade in emission rights, which entitle the operator to greenhouse gas emissions. The domestic emissions trading in gases released into the atmosphere would be limited to domestic units and emissions only. Emissions trading does not reduce emissions. Emissions are reduced by investments and changes in lines of action. The role of the national emissions trading depends on the overall national climate programme. Emissions trading - especially if it is connected with quotas imposed on greenhouse gas emissions or with other quantitative restrictions - is a strong instrument of which there is no previous experience in Finland. Compared to mere emission quotas, emissions trading might, however, offer a flexible and cost-efficient means of meeting the emission targets. The Committee thinks that the majority of - and most important - points speak in favour of the option that, if emissions trading is to be taken among the methodology of the climate policy, it is more profitable and more cost-efficient for Finland to use emissions trading as one instrument included in the climate policy together with other countries. The emissions trading area should also include countries that have lower costs of reducing emissions than those of Finland. The Committee does not propose that emissions trading between companies be initiated so as to be applicable in Finland only. If the EU Member States and the Community ratify the Kyoto Protocol and if emissions trading within the EU area begins, Finland will have to consider joining the trading system. If no decisions are made on the EU trading system by the year 2005, or if Finland cannot join it due to an implementation method that would be disadvantageous to Finland, Finland will have to consider joining the emissions trading system especially on the regional level covering the Nordic countries and the Baltic Sea States. Before joining any emissions trading

  16. National Emissions Trading; Interim Report by the Committee on the Kyoto mechanisms

    International Nuclear Information System (INIS)

    2001-01-01

    By emissions trading is meant that operators eligible for emissions trading can trade in emission rights, which entitle the operator to greenhouse gas emissions. The domestic emissions trading in gases released into the atmosphere would be limited to domestic units and emissions only. Emissions trading does not reduce emissions. Emissions are reduced by investments and changes in lines of action. The role of the national emissions trading depends on the overall national climate programme. Emissions trading - especially if it is connected with quotas imposed on greenhouse gas emissions or with other quantitative restrictions - is a strong instrument of which there is no previous experience in Finland. Compared to mere emission quotas, emissions trading might, however, offer a flexible and cost-efficient means of meeting the emission targets. The Committee thinks that the majority of - and most important- points speak in favour of the option that, i emissions trading is to be taken among the methodology of the climate policy, it is more profitable and more cost-efficient for Finland to use emissions trading as one instrument included in the climate policy together with other countries. The emissions trading area should also include countries that have lower costs of reducing emissions than those of Finland. The Committee does not propose that emissions trading between companies be initiated so as to be applicable in Finland only. If the EU Member States and the Community ratify the Kyoto Protocol and if emissions trading within the EU area begins, Finland will have to consider joining the trading system. If no decisions are made on the EU trading system by the year 2005, or if Finland cannot join it due to an implementation method that would be disadvantageous to Finland, Finland will have to consider joining the emissions trading system especially on the regional level covering the Nordic countries and the Baltic Sea States. Before joining any emissions trading

  17. National inventory report. Greenhouse gas emissions 1990-2009

    Energy Technology Data Exchange (ETDEWEB)

    2011-05-15

    Emissions of the following greenhouse gases are covered in this report: carbon dioxide (CO{sub 2}), methane (CH{sub 4}), nitrous oxide (N{sub 2}O), perfluoro carbons (PFCs), hydro fluorocarbons (HFCs) and sulphur hexafluoride (SF{sub 6}). In addition, the inventory includes calculations of emissions of the precursors NO{sub x}, NMVOC, and CO, as well as for SO{sub 2}. Indirect CO{sub 2} emissions originating from the fossil part of CH{sub 4} and NMVOC are calculated according to the reporting guidelines to the UNFCCC, and accounted for in the inventory. (AG)

  18. National inventory report. Greenhouse gas emissions 1990-2010

    Energy Technology Data Exchange (ETDEWEB)

    Kolshus, Hans H.; Gjerald, Eilev; Hoem, Britta; Ramberg, Simen Helgesen; Haugland, Hege; Valved, Hilde; Nelson, George Nicholas; Asphjell, Torgrim; Christophersen, Oeyvind; Gaustad, Alice; Rubaek, Birgitte; Hvalryg, Marte Monsen

    2012-07-01

    Emissions of the following greenhouse gases are covered in this report: carbon dioxide (CO{sub 2}), methane (CH{sub 4}), nitrous oxide (N{sub 2}O), perfluoro carbons (PFCs), hydro fluorocarbons (HFCs) and sulphur hexafluoride (SF{sub 6}). In addition, the inventory includes calculations of emissions of the precursors NO{sub x}, NMVOC, and CO, as well as for SO{sub 2}. Indirect CO{sub 2} emissions originating from the fossil part of CH{sub 4} and NMVOC are calculated according to the reporting guidelines to the UNFCCC, and accounted for in the inventory.(eb)

  19. Being prepared to verify the CTBT-Atmospheric Transport modeling and radionuclide analysis at the Austrian National Data Centre during the NDC Preparedness Exercise 2009

    Science.gov (United States)

    Wotawa, Gerhard; Schraick, Irene

    2010-05-01

    An explosion in the Kara-Zhyra mine in Eastern Kazakhstan on 28 November 2009 around 07:20 UTC was recorded by both the CTBTO seismic and infrasound networks. This event triggered a world-wide preparedness exercise among the CTBTO National Data Centres. Within an hour after the event was selected by the German NDC, a computer program developed by NDC Austria based on weather forecasts from the European Centre for Medium-Range Weather Forecasts (ECMWF) and from the U.S. National Centers for Environmental Prediction (NCEP) was started to analyse what Radionuclide Stations of the CTBTO International Monitoring System (IMS) would be potentially affected by the release from a nuclear explosion at this place in the course of the following 3-10 days. These calculations were daily updated to consider the observed state of the atmosphere instead of the predicted one. Based on these calculations, automated and reviewed radionuclide reports from the potentially affected stations as produced by the CTBTO International Data Centre (IDC) were looked at. An additional analysis of interesting spectra was provided by the Seibersdorf Laboratories. Based on all the results coming in, no evidence whatsoever was found that the explosion in Kazakhstan was nuclear. This is in accordance with ground truth information saying that the event was caused by the detonation of more than 53 Tons of explosives as part of mining operations. A number of conclusions can be drawn from this exercise. First, the international, bilateral as well as national mechanisms and procedures in place for such an event worked smoothly. Second, the products and services from the CTBTO IDC proved to be very useful to assist the member states in their verification efforts. Last but not least, issues with the availability of data from IMS radionuclide stations do remain.

  20. National Greenhouse Gas Emission Inventory (EV-GHG)

    Data.gov (United States)

    U.S. Environmental Protection Agency — The EV-GHG Mobile Source Data asset contains measured mobile source GHG emissions summary compliance information on light-duty vehicles, by model, for certification...

  1. 77 FR 73968 - Reconsideration of Certain New Source and Startup/Shutdown Issues: National Emission Standards...

    Science.gov (United States)

    2012-12-12

    ...; FRL-9762-1] RIN 2060-AR62 Reconsideration of Certain New Source and Startup/Shutdown Issues: National... Source and Startup/Shutdown Issues: National Emission Standards for Hazardous Air Pollutants from Coal... November 30, 2012, proposed ``Reconsideration of Certain New Source and Startup/Shutdown Issues: National...

  2. Verification of the Danish emission inventory data by national and international data comparisons

    Energy Technology Data Exchange (ETDEWEB)

    Fauser, P.; Thomsen, Marianne; Nielsen, Ole-Kenneth; Winther, M.; Gyldenkaerne, S.; Hoffmann, L.; Lyck, E.; Boll Illerup, J.

    2007-08-15

    Danish emission intensity values, activity values and implied emission factors for identified key source categories are compared with corresponding values for the EU-15 countries (excluding Luxemburg). The emission values for all countries are based on national greenhouse gas inventories for the years 1990 (base year), 1997 and 2003 provided by the UNFCCC. The comparison is based on a proposed verification procedure that is designed for identifying emission indicators and evaluating data consistency and reliability for the energy and industry sectors. For all sectors the method gives good possibility for checking emission levels and consistency in time trends. (au)

  3. Accounting for greenhouse gas emissions outside the national borders in FENCH-GHG energy planning

    International Nuclear Information System (INIS)

    Vate, J.F. van de

    1996-01-01

    This paper aims at providing guidance to the workshop discussion on the accountability of full-energy-chain greenhouse gas emissions from the use of energy sources if emissions did not take place inside the national borders of a country. Examples of such emissions are those from the generation of imported electricity or from mining and transportation of coal and natural gas. The FENCH-GHG approach, if used in energy planning, would automatically take such greenhouse gas emissions, which are inherent to energy systems, into account. The paper raises the basics, practicality and the feasibility of dealing with extra-boundary emissions in energy planning. (author). 3 refs

  4. Single Photon Emission Computed Tomography/Positron Emission Tomography Imaging and Targeted Radionuclide Therapy of Melanoma: New Multimodal Fluorinated and Iodinated Radiotracers

    International Nuclear Information System (INIS)

    Maisonial, A.; Papon, J.; Bayle, M.; Vidal, A.; Auzeloux, Ph.; Rbah, L.; Bonnet-Duquennoy, M.; Miot-Noirault, E.; Galmier, M.J.; Borel, M.; Madelmont, J.C.; Moins, N.; Chezal, J.M.; Kuhnast, B.; Boisgard, R.; Dolle, F.; Tavitian, B.; Boisgard, R.; Tavitian, B.; Askienazy, S.

    2011-01-01

    This study reports a series of 14 new iodinated and fluorinated compounds offering both early imaging ( 123 I, 124 I, 18 F) and systemic treatment ( 131 I) of melanoma potentialities. The biodistribution of each 125 I-labeled tracer was evaluated in a model of melanoma B16F0-bearing mice, using in vivo serial γ scintigraphic imaging. Among this series, [ 125 I]56 emerged as the most promising compound in terms of specific tumoral uptake and in vivo kinetic profile. To validate our multimodality concept, the radiosynthesis of [ 18 F]56 was then optimized and this radiotracer has been successfully investigated for in vivo PET imaging of melanoma in B16F0- and B16F10-bearing mouse model. The therapeutic efficacy of [ 131 I]56 was then evaluated in mice bearing subcutaneous B16F0 melanoma, and a significant slow down in tumoral growth was demonstrated. These data support further development of 56 for PET imaging ( 18 F, 124 I) and targeted radionuclide therapy ( 131 I) of melanoma using a single chemical structure. (authors)

  5. Radionuclide carrier

    International Nuclear Information System (INIS)

    Hartman, F.A.; Kretschmar, H.C.; Tofe, A.J.

    1978-01-01

    A physiologically acceptable particulate radionuclide carrier is described. It comprises a modified anionic starch derivative with 0.1% to 1.5% by weight of a reducing agent and 1 to 20% by weight of anionic substituents

  6. Estimating marginal CO2 emissions rates for national electricity systems

    International Nuclear Information System (INIS)

    Hawkes, A.D.

    2010-01-01

    The carbon dioxide (CO 2 ) emissions reduction afforded by a demand-side intervention in the electricity system is typically assessed by means of an assumed grid emissions rate, which measures the CO 2 intensity of electricity not used as a result of the intervention. This emissions rate is called the 'marginal emissions factor' (MEF). Accurate estimation of MEFs is crucial for performance assessment because their application leads to decisions regarding the relative merits of CO 2 reduction strategies. This article contributes to formulating the principles by which MEFs are estimated, highlighting the strengths and weaknesses in existing approaches, and presenting an alternative based on the observed behaviour of power stations. The case of Great Britain is considered, demonstrating an MEF of 0.69 kgCO 2 /kW h for 2002-2009, with error bars at +/-10%. This value could reduce to 0.6 kgCO 2 /kW h over the next decade under planned changes to the underlying generation mix, and could further reduce to approximately 0.51 kgCO 2 /kW h before 2025 if all power stations commissioned pre-1970 are replaced by their modern counterparts. Given that these rates are higher than commonly applied system-average or assumed 'long term marginal' emissions rates, it is concluded that maintenance of an improved understanding of MEFs is valuable to better inform policy decisions.

  7. Hydrology of the solid waste burial ground, as related to the potential migration of radionuclides, Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Barraclough, J.T.; Robertson, J.B.; Janzer, V.J.; Saindon, L.G.

    1976-08-01

    This report describes a study conducted by the U. S. Geological Survey with the following objectives: to evaluate the hydrologic, radiologic and geochemical variables that control the potential for subsurface migration of waste radionuclides from the burial trenches to the Snake River Plain aquifer; to determine the extent of radionuclide migration, if any; and, to construct monitoring wells into the aquifer. Statistically significant trace amounts of radioactivity were found in about one-half of the 44 sedimentary samples from the six holes core drilled inside the burial ground and from all water samples from one hole tapping a perched water table. These very low levels of radioactivity are detectable only with the most sensitive of analytical equipment and techniques. The levels of radioactivity detected were, in most cases, less than the amounts found in surface soils in this region resulting from world-wide fallout. This radioactivity found in the cores could have been introduced naturally by migration by infiltrating water which had made contact with buried waste or could have been introduced artificially during drilling and sampling. The available data from the four peripheral monitoring wells do not indicate that radionuclide constituents from the burial ground have migrated into the underlying Snake River Plain aquifer. The low concentrations of radionuclides detected in samples taken from the sedimentary layers are not expected to migrate to the Snake River Plain aquifer. Water samples from the peripheral wells and one core hole inside the burial ground will continue to be collected and analyzed for radioactivity semi-annually

  8. 77 FR 58219 - National Emission Standards for Hazardous Air Pollutant Emissions: Hard and Decorative Chromium...

    Science.gov (United States)

    2012-09-19

    ... for public health and the environment by reducing emissions of hexavalent chromium (a known human... alternatives to PFOS-based WAFS had been successfully used in the hard and decorative chrome source categories... the number of people exposed to risks greater than 1-in-1 million due to emissions of hexavalent...

  9. Pesticide Active Ingredient Production Industry: National Emission Standards for Hazardous Air Pollutants (NESHAP)

    Science.gov (United States)

    This action promulgates national emission standards for hazardous air pollutants (NESHAP) for the pesticide active ingredient (PAI) production source category under section 112 of the Clean Air Act as amended (CAA or Act).

  10. National Emissions Inventory (NEI) 2005 Point Facility Data for the US (US EPA)

    Data.gov (United States)

    U.S. Environmental Protection Agency — This map service displays 2005 USEPA National Emissions Inventory (NEI) point facility information for the United States. The map service was created for inclusion...

  11. National Emissions Inventory (NEI) 2011 Point Facility Data for the US (US EPA)

    Data.gov (United States)

    U.S. Environmental Protection Agency — This map service displays 2011 USEPA National Emissions Inventory (NEI) point facility information for the United States. The map service was created for inclusion...

  12. Primary Aluminum Reduction Industry - National Emission Standards for Hazardous Air Pollutants (NESHAP)

    Science.gov (United States)

    National emission standards for each new or existing potline, paste production operation, and anode bake furnace associated with a primary aluminum reduction plant. Includes rule history, implementation information and additional resources.

  13. 75 FR 37732 - National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion...

    Science.gov (United States)

    2010-06-30

    ... National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion Engines... hazardous air pollutants for existing stationary compression ignition reciprocating internal combustion... combustion engines. 40 CFR 63.6590 was amended by revising paragraphs (b)(1) and (3). Inadvertently...

  14. 75 FR 75937 - National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion...

    Science.gov (United States)

    2010-12-07

    ... National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion Engines... internal combustion engines. Subsequently, the Administrator received two petitions for reconsideration... Any industry using a stationary 2211 Electric power reciprocating internal generation, combustion...

  15. 76 FR 12923 - National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion...

    Science.gov (United States)

    2011-03-09

    ... National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion Engines... pollutants for existing stationary spark ignition reciprocating internal combustion engines. The final rule... reciprocating internal combustion generation, engine. transmission, or distribution. 622110 Medical and surgical...

  16. 77 FR 60341 - National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion...

    Science.gov (United States)

    2012-10-03

    ... National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion Engines; New Source Performance Standards for Stationary Internal Combustion Engines AGENCY: Environmental Protection... Pollutants for Stationary Reciprocating Internal Combustion Engines to solicit comment on specific issues...

  17. 77 FR 37361 - National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion...

    Science.gov (United States)

    2012-06-21

    ... National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion Engines; New Source Performance Standards for Stationary Internal Combustion Engines AGENCY: Environmental Protection... Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion Engines; New Source Performance...

  18. Cellulose Products Manufacturing: National Emission Standards for Hazardous Air Pollutants (NESHAP)

    Science.gov (United States)

    Read the National Emission Standards for Hazardous Air Pollutants (NESHAP) for Cellulose Products Manufacturing, see the rule history for this Maximum Achievable Control Technology (MACT), and find Compliance help for this source.

  19. 75 FR 28227 - National Emission Standards for Hazardous Air Pollutants: Gold Mine Ore Processing and Production...

    Science.gov (United States)

    2010-05-20

    ...-AP48 National Emission Standards for Hazardous Air Pollutants: Gold Mine Ore Processing and Production... published a proposed rule for mercury emissions from the gold mine ore processing and production area source... Environmental protection, Air pollution control, Hazardous substances, Incorporations by reference, Reporting...

  20. 76 FR 9409 - National Emission Standards for Hazardous Air Pollutants: Primary Lead Smelting

    Science.gov (United States)

    2011-02-17

    ... National Emission Standards for Hazardous Air Pollutants: Primary Lead Smelting; Proposed Rule #0;#0... Emission Standards for Hazardous Air Pollutants: Primary Lead Smelting AGENCY: Environmental Protection... standards for hazardous air pollutants (NESHAP) for Primary Lead Smelting to address the results of the...

  1. 76 FR 12863 - National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion...

    Science.gov (United States)

    2011-03-09

    ... National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion Engines... combustion engines. The final rule was published on August 20, 2010. This direct final action amends certain... Emission Standards for Hazardous Air Pollutant for Stationary Reciprocating Internal Combustion Engines...

  2. Effect of diltiazem on myocardial infarct size estimated by enzyme release, serial thallium-201 single-photon emission computed tomography and radionuclide angiography

    International Nuclear Information System (INIS)

    Zannad, F.; Amor, M.; Karcher, G.; Maurin, P.; Ethevenot, G.; Sebag, C.; Bertrand, A.; Pernot, C.; Gilgenkrantz, J.M.

    1988-01-01

    Diltiazem is a calcium antagonist with demonstrated experimental cardioprotective effects. Its effects on myocardial infarct size were studied in 34 patients admitted within 6 hours after the first symptoms of acute myocardial infarction. These patients were randomized, double-blind to placebo or diltiazem (10-mg intravenous bolus followed by 15 mg/hr intravenous infusion during 72 hours, followed by 4 X 60 mg during 21 days). Myocardial infarct size was assessed by plasma creatine kinase and creatine kinase-MB indexes, perfusion defect scores using single-photon emission computed tomography with thallium-201 and left ventricular ejection fraction measured by radionuclide angiography. Tomographic and angiographic scanning was performed serially before randomization, after 48 hours and 21 days later. Groups were comparable in terms of age, sex, inclusion time and baseline infarct location and size. Results showed no difference in creatine kinase and creatine kinase-MB data between controls and treated patients, a significant decrease in the perfusion defect scores in the diltiazem group (+0.1 +/- 3.0 placebo vs -2.2 +/- 1.9 diltiazem, p less than 0.02) and a better ejection fraction recovery in the diltiazem group (-4.2 +/- 7.4 placebo vs +7.7 +/- 11.2 diltiazem, p less than 0.05). Myocardial infarct size estimates from perfusion defect scores and enzyme data were closely correlated. These preliminary results suggest that diltiazem may reduce ischemic injury in acute myocardial infarction

  3. Counting efficiency for radionuclides decaying by beta and gamma-ray emission; Calculo de la eficiencia de recuento de nucleidos que experimentan desintegracion beta y desexcitacion gamma simple

    Energy Technology Data Exchange (ETDEWEB)

    Grau, A.; Garcia-Torano, E.

    1988-07-01

    In this paper, counting efficiency vs figure of merit for beta and gamma-ray emitters has been computed. It is assumed that the decay scheme has only a gamma level and the beta-ray emission may be coincident with the gamma-rays or the internal-conversion electrons. The radionuclides tabulated are: 20 {sub 0}, 20{sub p}, 28{sub A}l, 35{sub p}, 41{sub A}r, 42{sub K}, 47{sub S}e, 62{sub F}e, 66{sub C}u, 81{sub G}e, 86{sub B}b, 108{sub R}u, 112{sub p}d, 121{sub S}n(Ni), 122{sub I}n, 129{sub I}, 141{sub C}e 171{sub T}m, 194{sub O}s, 2O3{sub H}g, 205{sub H}g, 210{sub p}b, 225{sub R}a, 142{sub p}r, 151{sub S}m, 244{sub A}m(m). It has been assumed that the liquid is a toluene based scintillator solution in standard glass vials containing 10 cm''3. (Author) 8 refs.

  4. The PRIMAP-hist national historical emissions time series

    Science.gov (United States)

    Gütschow, Johannes; Jeffery, M. Louise; Gieseke, Robert; Gebel, Ronja; Stevens, David; Krapp, Mario; Rocha, Marcia

    2016-11-01

    To assess the history of greenhouse gas emissions and individual countries' contributions to emissions and climate change, detailed historical data are needed. We combine several published datasets to create a comprehensive set of emissions pathways for each country and Kyoto gas, covering the years 1850 to 2014 with yearly values, for all UNFCCC member states and most non-UNFCCC territories. The sectoral resolution is that of the main IPCC 1996 categories. Additional time series of CO2 are available for energy and industry subsectors. Country-resolved data are combined from different sources and supplemented using year-to-year growth rates from regionally resolved sources and numerical extrapolations to complete the dataset. Regional deforestation emissions are downscaled to country level using estimates of the deforested area obtained from potential vegetation and simulations of agricultural land. In this paper, we discuss the data sources and methods used and present the resulting dataset, including its limitations and uncertainties. The dataset is available from doi:10.5880/PIK.2016.003 and can be viewed on the website accompanying this paper (de/primap-live/primap-hist/" target="_blank">http://www.pik-potsdam.de/primap-live/primap-hist/).

  5. Influence of atmospheric emission from coal fuel cycle on the levels of natural radionuclides and heavy metals in the population

    International Nuclear Information System (INIS)

    Jaworowski, Z.

    1983-07-01

    From the determination of Ra, Pb, Zn and Cd concentrations in air and various human tissues of inhabitants exposed to large industrial emissions as well as of those of other regions it could be seen that geographical distribution of these elements is rather related to local natural background factors than to industrial activity in the region. The concentrations of 226 Ra and Pb increased during the last century in precipitations in Southern Poland, but in the same time they decreased dramatically in the bones of the Polish population. The contemporary Polish bones contain about 10 times less Pb and 2 times less 226 Ra than 11th to 19th century Polish bones and 18th century Peruvian bones. The decrease of 226 Ra content probably results from the introduction of drinking-water treatment systems which remove majority of 226 Ra and from decrease in consumption of cereals, which are principal sources of 226 Ra intake in the diet

  6. Subpart W: National Emission Standards for Radon Emissions From Operating Mill Tailings

    Science.gov (United States)

    Subpart W limits the radon-222 emissions rate from uranium tailings piles to 20 picocuries per square meter per second and requires that new tailings impoundments meet certain work practice standards.

  7. 76 FR 22565 - National Emission Standards for Hazardous Air Pollutant Emissions: Group I Polymers and Resins...

    Science.gov (United States)

    2011-04-21

    ... Production, Nitrile Butadiene Rubber (NBR) Production, Polybutadiene Rubber Production, Polysulfide Rubber..., Epichlorohydrin Elastomers, Neoprene Rubber, and NBR source categories will not require additional control to meet... Emissions Standards for Group I Polymers and Resins (Butyl Rubber Production, Epichlorohydrin Elastomers...

  8. Ethylene Oxide Emissions Standards for Sterilization Facilities: National Emission Standards for Hazardous Air Pollutants (NESHAP)

    Science.gov (United States)

    Learn about the NESHAP for ethylene oxide emissions for sterilization facilities. Find the rule history information, federal register citations, legal authority, and related rules as well as a rule summary.

  9. 134Cs emission probabilities determination by gamma spectrometry

    Science.gov (United States)

    de Almeida, M. C. M.; Poledna, R.; Delgado, J. U.; Silva, R. L.; Araujo, M. T. F.; da Silva, C. J.

    2018-03-01

    The National Laboratory for Ionizing Radiation Metrology (LNMRI/IRD/CNEN) of Rio de Janeiro performed primary and secondary standardization of different radionuclides reaching satisfactory uncertainties. A solution of 134Cs radionuclide was purchased from commercial supplier to emission probabilities determination of some of its energies. 134Cs is a beta gamma emitter with 754 days of half-life. This radionuclide is used as standard in environmental, water and food control. It is also important to germanium detector calibration. The gamma emission probabilities (Pγ) were determined mainly for some energies of the 134Cs by efficiency curve method and the Pγ absolute uncertainties obtained were below 1% (k=1).

  10. National emission standards for hazardous air pollutants submittal - 1996

    International Nuclear Information System (INIS)

    Townsend, Y.E.; Black, S.C.

    1997-06-01

    The Nevada Test Site (NTS) is operated by the US Department of Energy, Nevada Operations Office (DOE/NV) as the site for nuclear weapons testing. Monitoring and evaluation of the various activities conducted onsite indicate that the potential sources of offsite radiation exposure in 1996 were releases from the following: evaporation of tritiated water from containment ponds that receive drainage from E tunnel and from wells used for site characterization studies; onsite radioanalytical laboratories; the Area 5 RWMS facility; and diffuse sources of tritium and resuspension of plutonium. Section 1 describes these sources on the NTS. Section 2 tabulates the air emissions data for the NTS. These data are used to calculate the effective dose equivalents to offsite residents. Appendices describe the methods used to determine the emissions from the sources listed

  11. Radionuclide data

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    Chapter 8 presents tables on selected alpha, beta, gamma and x-ray emitters by increasing energy; information on specific activity for selected radionuclides; naturally occurring radionuclides; the natural decay series; and the artificially produced neptunium series. A table of alpha emitters is listed by increasing atomic number and by energy. The table of β emitters presented is useful in identifying β emitters whose energies and possibly half-lives have been determined by standard laboratory techniques. It is also a handy guide to β-emitting isotopes for applications requiring specific half-lives and/or energies. Gamma rays for radionuclides of importance to radiological assessments and radiation protection are listed by increasing energy. The energies and branching ratios are important for radionuclide determinations with gamma spectrometry detectors. This section also presents a table of x-ray energies which are useful for radiochemical analyses. A number of nuclides emit x-rays as part of their decay scheme. These x-rays may be counted with Ar proportional counters, Ge planar or n-type Ge co-axial detectors, or thin crystal NaI(T1) scintillation counters. In both cases, spectral measurements can be made and both qualitative and quantitative information obtained on the sample. Nuclear decay data (energy and probability by radiation type) for more than one hundred radionuclides that are important to health physicists are presented in a schematic manner

  12. The role of multiple regression and exploratory data analysis in the development of leukemia incidence risk models for comparison of radionuclide air stack emissions from nuclear and coal power industries

    International Nuclear Information System (INIS)

    Prybutok, V.R.

    1995-01-01

    Risk associated with power generation must be identified to make intelligent choices between alternate power technologies. Radionuclide air stack emissions for a single coal plant and a single nuclear plant are used to compute the single plant leukemia incidence risk and total industry leukemia incidence risk. Leukemia incidence is the response variable as a function of radionuclide bone dose for the six proposed dose response curves considered. During normal operation a coal plant has higher radionuclide emissions than a nuclear plant and the coal industry has a higher leukaemia incidence risk than the nuclear industry, unless a nuclear accident occurs. Variation of nuclear accident size allows quantification of the impact of accidents on the total industry leukemia incidence risk comparison. The leukemia incidence risk is quantified as the number of accidents of a given size for the nuclear industry leukemia incidence risk to equal the coal industry leukemia incidence risk. The general linear model is used to develop equations that relate the accident frequency required for equal industry risks to the magnitude of the nuclear emission. Exploratory data analysis revealed that the relationship between the natural log of accident number versus the natural log of accident size is linear. (Author)

  13. Emission pathway modeling to analyze national ambition levels of decarbonization

    International Nuclear Information System (INIS)

    Kainuma, Mikiko; Waisman, Henri

    2015-01-01

    The Deep Decarbonization Pathways Project (DDPP) is a knowledge network comprising 15 Country Research Teams and several Partner Organizations which develop and share methods, assumptions, and findings related to deep decarbonization. It analyzes the technical decarbonization potential, exploring options for deep decarbonization, but also better taking into account existing infrastructure stocks. It shows the possibility to reduce total CO 2 -energy emissions by 45% by 2050, with bottom-up analyses by 15 Country Research Teams

  14. Radionuclide generators

    International Nuclear Information System (INIS)

    Lambrecht, R.M.

    1983-01-01

    The status of radionuclide generators for chemical research and applications related to the life sciences and biomedical research are reviewed. Emphasis is placed upon convenient, efficient and rapid separation of short-lived daughter radionuclides in a chemical form suitable for use without further chemical manipulation. The focus is on the production of the parent, the radiochemistry associated with processing the parent and daughter, the selection and the characteristic separation methods, and yields. Quality control considerations are briefly noted. The scope of this review includes selected references to applications of radionuclide generators in radiopharmaceutical chemistry, and the life sciences, particularly in diagnostic and therapeutic medicine. The 99 Mo-sup(99m)Tc generator was excluded. 202 references are cited. (orig.)

  15. Updated national emission of perfluoroalkyl substances (PFASs) from wastewater treatment plants in South Korea.

    Science.gov (United States)

    Kwon, Hye-Ok; Kim, Hee-Young; Park, Yu-Mi; Seok, Kwang-Seol; Oh, Jeong-Eun; Choi, Sung-Deuk

    2017-01-01

    A nationwide emission estimate of perfluoroalkyl substances (PFASs) from wastewater treatment plants (WWTPs) is required to understand the source-receptor relationship of PFASs and to manage major types of WWTPs. In this study, the concentrations of 13 PFASs (8 perfluorocarboxylic acids, 3 perfluoroalkane sulfonates, and 2 intermediates) in wastewater and sludge from 81 WWTPs in South Korea were collected. The emission pathways of PFASs were redefined, and then the national emission of PFASs from WWTPs was rigorously updated. In addition to the direct calculations, Monte Carlo simulations were also used to calculate the likely range of PFAS emissions. The total (Σ 13 PFAS) emission (wastewater + sludge) calculated from the direct calculation with mean concentrations was 4.03 ton/y. The emissions of perfluorooctanoic acid (PFOA, 1.19 ton/y) and perfluorooctane sulfonate (PFOS, 1.01 ton/y) were dominant. The Monte Carlo simulations suggested that the realistic national emission of Σ 13 PFASs is between 2 ton/y and 20 ton/y. Combined WWTPs treating municipal wastewater from residential and commercial areas were identified as a major emission source, contributing 65% to the total PFAS emissions. The Han and Nakdong Rivers were the primary contaminated rivers, receiving 89% of the total PFAS discharge from WWTPs. The results and methodologies in this study can be useful to establish a management policy for PFASs. Copyright © 2016 Elsevier Ltd. All rights reserved.

  16. Energy and environmental impact of domestic heating in Italy: Evaluation of national NOx emissions

    International Nuclear Information System (INIS)

    Aste, Niccolò; Adhikari, R.S.; Compostella, Junia; Pero, Claudio Del

    2013-01-01

    The domestic heating sector has a high potential in terms of energy savings and environmental impact. In the present study, an analysis has been carried out on the effect of domestic heating on natural gas (NG) consumption and pollutants emissions. In particular, among various emission pollutants, the nitrogen oxides (NO x ) emissions at national level were analyzed in detail. The work was carried out under a collaborative research project between the Italian Ministry of the Environment and Politecnico di Milano. For the assessment of the national NO x emissions due to residential heating, an inventory of the domestic boilers stock operating in Italy from 1999 to 2010 was made. As from a technological point of view, the precise data about the real composition of national domestic boilers stock were incomplete and not updated, a methodological procedure was developed in order to reconstruct the national domestic boilers stock based on the available technologies and thermal power. According to this scenario, the technological improvement of national boilers stock in the last decade was evaluated in terms of natural gas saving and reduced NO x emissions. Further some discussion has been made on the energy policies for the diffusion of more efficient boilers. - Highlights: ► First-of-its-kind study on the effect of domestic heating on NO x emissions. ► Inventory of national gas boiler population for domestic heating. ► Estimation of the main boilers typologies distribution on a national level. ► Technological improvement of thermal appliances and NO x emissions reduction.

  17. Radionuclides deposition over Antarctica

    International Nuclear Information System (INIS)

    Pourchet, M.; Magand, O.; Frezzotti, M.; Ekaykin, A.; Winther, J.-G.

    2003-01-01

    A detailed and comprehensive map of the distribution patterns for both natural and artificial radionuclides over Antarctica has been established. This work integrates the results of several decades of international programs focusing on the analysis of natural and artificial radionuclides in snow and ice cores from this polar region. The mean value (37±20 Bq m -2 ) of 241 Pu total deposition over 28 stations is determined from the gamma emissions of its daughter 241 Am, presenting a long half-life (432.7 yrs). Detailed profiles and distributions of 241 Pu in ice cores make it possible to clearly distinguish between the atmospheric thermonuclear tests of the fifties and sixties. Strong relationships are also found between radionuclide data ( 137 Cs with respect to 241 Pu and 210 Pb with respect to 137 Cs), make it possible to estimate the total deposition or natural fluxes of these radionuclides. Total deposition of 137 Cs over Antarctica is estimated at 760 TBq, based on results from the 90-180 deg. East sector. Given the irregular distribution of sampling sites, more ice cores and snow samples must be analyzed in other sectors of Antarctica to check the validity of this figure

  18. Characterization of the near-surface radionuclide contamination associated with the bathtub effect at Solid Waste Storage Area 4, Oak Ridge National Laboratory, Tennessee

    International Nuclear Information System (INIS)

    Melroy, L.A.; Huff, D.D.; Farrow, N.D.

    1986-06-01

    Solid Waste Storage Area 4 (SWSA-4) at the Oak Ridge National Laboratory (ORNL) was studied to determine the extent of near-surface radionuclide contamination associated with the bathtub effect in low-lying trenches. A surface survey of the low-elevation portion of the burial ground was conducted to identify areas where the bathtub effect had resulted in surface contamination. Using this initial survey as a guide, 15 soil cores, each approximately 3 m deep, were taken to determine the depth to which contamination had spread and to help identify an contamination plumes. Results showed that two areas of surface radionuclide contamination exist, one located between the western end of the SWSA-4 tributary and the edge of the burial ground, the other located just north of the tributary below the central paved runoff channel. In addition, some downward migration of the solutes has occurred. However, the penetration depth for 90 Sr seems to be generally less than 2.7 m

  19. 76 FR 70833 - National Emission Standards for Hazardous Air Pollutant Emissions for Primary Lead Processing

    Science.gov (United States)

    2011-11-15

    ... INFORMATION: For specific information regarding the modeling methodology, contact Dr. Michael Stewart, Office... there is a malfunction, the emission limitation is still enforceable through injunctive relief. While... (GEP) stack height of 330 feet (as was done in the SIP and in modeling submitted by the Doe Run Company...

  20. Establishment of national emission measurement activity in neighbouring areas of Finland

    Energy Technology Data Exchange (ETDEWEB)

    Aunela, L.; Larjava, K.; Jormanainen, P. [VTT Chemical Technology, Espoo (Finland). Environmental Technology; Muurinen, M. [Enemi Ltd, Lahti (Finland); Hietamaeki, M. [Ministry of the Environment, Helsinki (Finland)

    1995-12-31

    Estonia, Latvia, and Lithuania (the Baltic countries) and the Republic State of Carelia, Russia belong to the so-called nearby areas of Finland. All being part of the former Soviet Union, they are now undergoing the establishment of their own environment- managing systems. Finland has shown a great amount of interest in supporting the efforts of these areas to solve their environmental problems. In 1993 VTT started, at the request of the East European Project of the Finnish Ministry of the Environment, a four year project aiming at the establishment of national atmospheric emission measurement systems in the Baltic countries and the Republic state of Carelia (later: the counterpart countries). Proper national emission measurement systems were regarded important in order to provide reliable data on the emission situation for national and international use. The main target of the work is to raise the level of the emission measurements in the counterpart countries to the international level. Two aspects were considered to be required to achieve this goal; (1) delivery of proper emission measurement equipment, (2) training of the emission measurement personnel. It was estimated that within three to four years these counterpart countries could join the Finnish quality assurance system in emission measurements if desired. (author)

  1. Establishment of national emission measurement activity in neighbouring areas of Finland

    Energy Technology Data Exchange (ETDEWEB)

    Aunela, L; Larjava, K; Jormanainen, P [VTT Chemical Technology, Espoo (Finland). Environmental Technology; Muurinen, M [Enemi Ltd, Lahti (Finland); Hietamaeki, M [Ministry of the Environment, Helsinki (Finland)

    1996-12-31

    Estonia, Latvia, and Lithuania (the Baltic countries) and the Republic State of Carelia, Russia belong to the so-called nearby areas of Finland. All being part of the former Soviet Union, they are now undergoing the establishment of their own environment- managing systems. Finland has shown a great amount of interest in supporting the efforts of these areas to solve their environmental problems. In 1993 VTT started, at the request of the East European Project of the Finnish Ministry of the Environment, a four year project aiming at the establishment of national atmospheric emission measurement systems in the Baltic countries and the Republic state of Carelia (later: the counterpart countries). Proper national emission measurement systems were regarded important in order to provide reliable data on the emission situation for national and international use. The main target of the work is to raise the level of the emission measurements in the counterpart countries to the international level. Two aspects were considered to be required to achieve this goal; (1) delivery of proper emission measurement equipment, (2) training of the emission measurement personnel. It was estimated that within three to four years these counterpart countries could join the Finnish quality assurance system in emission measurements if desired. (author)

  2. Radionuclide generators

    International Nuclear Information System (INIS)

    Lambrecht, R.M.; Wollongong Univ.; Tomiyoshi, K.; Sekine, T.

    1997-01-01

    The present status and future directions of research and development on radionuclide generator technology are reported. The recent interest to develop double-neutron capture reactions for production of in vivo generators; neutron rich nuclides for radio-immunotherapeutic pharmaceuticals: and advances with ultra-short lived generators is highlighted. Emphasis is focused on: production of the parent radionuclide; the selection and the evaluation of support materials and eluents with respect to the resultant radiochemical yield of the daughter, and the breakthrough of the radionuclide parent: and, the uses of radionuclide generators in radiopharmaceutical chemistry, biomedical and industrial applications. The 62 Zn → 62 Cu, 66 Ni → 66 Cu, 103m Rh → 103 Rh, 188 W → 188 Re and the 225 Ac → 221 Fr → 213 Bi generators are predicted to be emphasized for future development. Coverage of the 99 Mo → 99m Tc generator was excluded, as it the subject of another review. The literature search ended June, 1996. (orig.)

  3. Positron emission tomography in a national research centre

    International Nuclear Information System (INIS)

    Weinreich, R.

    1989-01-01

    The example of the Paul Scherrer Institute shows that positron emission tomography can be implanted successfully as spin-off into an appropriate environment. The adaption to the existing irradiation facilities of the technique of production of the short-lived positron emitters is complex. However, the basic necessities of a tomography programme can be covered. Moreover, the relatively high energy of the institute's injector cyclotron allows additional production of rare-used longer-lived positron emitters. The scanner exceeded the guaranteed specifications. With respect to the somewhat lower availability of beam time compared to a usual baby cyclotron, the research programme must not be very patient-intense. A strong participation of the pharmaceutical industry has directed research priorities into the pharmacological area. (orig.) [de

  4. The true extent of agriculture's contribution to national greenhouse gas emissions

    International Nuclear Information System (INIS)

    Bell, M.J.; Cloy, J.M.; Rees, R.M.

    2014-01-01

    Highlights: • Quantification of agricultural GHG emissions is required under legislation. • Alternative approaches to calculating agricultural GHG inventories were compared. • The Scottish Government and IPCC attribute different emissions to the agricultural sector. • High emissions from agriculture are calculated when land-use change is included. • Agriculture is a greater source of emissions using the Scottish Government approach. - Abstract: The agricultural sector is a significant contributor to greenhouse gas (GHG) emissions, and a growing global population means that agricultural production will remain high if food demands are to be met. Mitigation methods to reduce emissions from this sector are thus required, along with identification and quantification of emission sources, so that the agricultural community can act and measure its progress. International legislation requires the submission of annual reports quantifying GHG emissions from agriculture. The importance of attributing the correct sources of emissions to the agricultural sector is clear; however the current approach taken by the IPCC, and reported to the UNFCCC, omits emissions from soils during agricultural land-use change from its agricultural inventory. This paper questions the IPCC approach, and the attribution of agricultural land-use change emissions to a separate category: ‘Land-use, Land-use change and Forestry’. Here a new approach adopted by the Scottish Government is examined, and compared to IPCC guidelines and national communications submitted to the Department of Energy and Climate Change (DECC) and the UNFCCC. The new Scottish Government approach attributes emissions from both land-use conversion and agricultural land under continuous use to the agricultural sector, in addition to those emissions from livestock and energy use on farms. The extent of emissions attributed to the agricultural sector using the Scottish Government approach is much greater than that using

  5. Plan for studies of subsurface radionuclide migration at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. Volume 2 of 2. Appendices

    International Nuclear Information System (INIS)

    1983-11-01

    This document describes planned studies of subsurface radionuclide migration at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. A plan is provided for each proposed study. The rational for arriving at the list of proposed studies is also presented. This document consists of two volumes. In the first volume, Sections 1 through 5 contain the introduction, the objectives of the proposed studies, and background information. The discussion is not comprehensive in detail; documents are referenced that discuss the background material in greater detail. Sections 6 through 9 identify and select the group of studies to be performed and discuss the peer review process. The second volume contains Appendices A and B, which present the assignment of responsibilities and the detailed plans, schedules, and costs for the proposed program

  6. Plan for studies of subsurface radionuclide migration at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. Volume 1 of 2

    International Nuclear Information System (INIS)

    1983-11-01

    This document describes planned studies of subsurface radionuclide migration at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. A plan is provided for each proposed study. The rational for arriving at the list of proposed studies is also presented. This document consists of two volumes. In the first volume, Sections 1 through 5 contain the introduction, the objectives of the proposed studies, and background information. The discussion is not comprehensive in detail; documents are referenced that discuss the background material in greater detail. Sections 6 through 9 identify and select the group of studies to be performed and discuss the peer review process. The second volume contains Appendices A and B, which present the assignment of responsibilities and the detailed plans, schedules, and costs for the proposed program

  7. Heavy element radionuclides (Pu, Np, U) and {sup 137}Cs in soils collected from the Idaho National Engineering and Environmental Laboratory and other sites in Idaho, Montana, and Wyoming

    Energy Technology Data Exchange (ETDEWEB)

    Beasley, T.M.; Rivera, W. Jr. [Dept. of Energy, New York, NY (United States). Environmental Measurements Lab.; Kelley, J.M.; Bond, L.A. [Pacific Northwest National Lab., Richland, WA (United States); Liszewski, M.J. [Bureau of Reclamation (United States); Orlandini, K.A. [Argonne National Lab., IL (United States)

    1998-10-01

    The isotopic composition of Pu in soils on and near the Idaho National Engineering and Environmental Laboratory (INEEL) has been determined in order to apportion the sources of the Pu into those derived from stratospheric fallout, regional fallout from the Nevada Test Site (NTS), and facilities on the INEEL site. Soils collected offsite in Idaho, Montana, and Wyoming were collected to further characterize NTS fallout in the region. In addition, measurements of {sup 237}Np and {sup 137}Cs were used to further identify the source of the Pu from airborne emissions at the Idaho Chemical Processing Plant (ICPP) or fugitive releases from the Subsurface Disposal Area (SDA) in the Radioactive Waste Management Complex (RWMC). There is convincing evidence from this study that {sup 241}Am, in excess of that expected from weapons-grade Pu, constituted a part of the buried waste at the SDA that has subsequently been released to the environment. Measurements of {sup 236}U in waters from the Snake River Plain aquifer and a soil core near the ICPP suggest that this radionuclide may be a unique interrogator of airborne releases from the ICPP. Neptunium-237 and {sup 238}Pu activities in INEEL soils suggest that airborne releases of Pu from the ICPP, over its operating history, may have recently been overestimated.

  8. X-ray emission from National Ignition Facility indirect drive targets

    International Nuclear Information System (INIS)

    Anderson, A.T.; Managan, R.A.; Tobin, M.T.; Peterson, P.F.

    1996-01-01

    We have performed a series of 1-D numerical simulations of the x-ray emission from National Ignition Facility (NIF) targets. Results are presented in terms of total x-ray energy, pulse length, and spectrum. Scaling of x-ray emissions is presented for variations in both target yield and hohlraum thickness. Experiments conducted on the Nova facility provide some validation of the computational tools and methods

  9. Mass and emission spectrometry in the Analytical Chemistry Division of Oak Ridge National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Smith, D.H. (ed.)

    1978-11-01

    The capabilities of the Mass and Emission Spectrometry Section of the Analytical Chemistry Division of Oak Ridge National Laboratory are described. Many different areas of mass spectrometric expertise are represented in the section: gas analysis, high abundance sensitivity measurements, high- and low-resolution organic analyses, spark source trace constituent analysis, and ion microprobe analysis of surfaces. These capabilities are complemented by emission spectrometry. The instruments are described along with a few applications, some of which are unique.

  10. Mass and emission spectrometry in the Analytical Chemistry Division of Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Smith, D.H.

    1978-11-01

    The capabilities of the Mass and Emission Spectrometry Section of the Analytical Chemistry Division of Oak Ridge National Laboratory are described. Many different areas of mass spectrometric expertise are represented in the section: gas analysis, high abundance sensitivity measurements, high- and low-resolution organic analyses, spark source trace constituent analysis, and ion microprobe analysis of surfaces. These capabilities are complemented by emission spectrometry. The instruments are described along with a few applications, some of which are unique

  11. Concentrations of Radionuclides and Trace Elements in Environmantal Media arond te Dual-Axis Radiographic Hydrodynamic Test Facilit at Los Alamos National Laboratory during 2005

    Energy Technology Data Exchange (ETDEWEB)

    G.J.Gonzales; P.R. Fresquez; C.D.Hathcock; D.C. Keller

    2006-05-15

    The Mitigation Action Plan (MAP) for the Dual-Axis Radiographic Hydrodynamic Test (DARHT) facility at Los Alamos National Laboratory requires that samples of biotic and abiotic media be collected after operations began to determine if there are any human health or environmental impacts. The DARHT facility is the Laboratory's principal explosive test facility. To this end, samples of soil and sediment, vegetation, bees, and birds were collected around the facility in 2005 and analyzed for concentrations of {sup 3}H, {sup 137}Cs, {sup 90}Sr, {sup 238}Pu, {sup 239,240}Pu, {sup 241}Am, {sup 234}U, {sup 235}U, {sup 238}U, Ag, As, Ba, Be, Cd, Cr, Cu, Hg, Ni, Pb, Sb, Se, and Tl. Bird populations have also been monitored. Contaminant results, which represent up to six sample years since the start of operations, were compared with (1) baseline statistical reference levels (BSRLs) established over a four-year preoperational period before DARHT facility operations, (2) screening levels (SLs), and (3) regulatory standards. Most radionuclides and trace elements were below BSRLs and those few samples that contained radionuclides and trace elements above BSRLs were below SLs. Concentrations of radionuclides and nonradionuclides in biotic and abiotic media around the DARHT facility do not pose a significant human health hazard. The total number of birds captured and number of species represented were similar in 2003 and 2004, but both of these parameters increased substantially in 2005. Periodic interruption of the scope and schedule identified in the MAP generally should have no impact on meeting the intent of the MAP. The risk of not sampling one of the five media in any given year is that if a significant impact to contaminant levels were to occur there would exist a less complete understanding of the extent of the change to the baseline for these media and to the ecosystem as a whole. Since the MAP is a requirement that was established under the regulatory framework of

  12. National Emission Standards for Hazardous Air Pollutants (NESHAP) for Lime Manufacturing Background Information Document (BID): Public Comments and Responses

    Science.gov (United States)

    On December 20, 2002, the EPA proposed national emission standards for HAP emissions from lime manufacturing plants located at major source facilities (67 FR 78046). Summaries of the comments, and the EPA's responses, are presented in this BID.

  13. Greenhouse Gas Emissions in the Netherlands 1990-2007. National Inventory Report 2009

    International Nuclear Information System (INIS)

    Van der Maas, C.W.M.; Brandes, L.J.; Baas, K.; Van den Born, G.J.; Geilenkirchen, G.; Te Molder, R.; Nijdam, D.S.; Olivier, J.G.J.; Peek, C.J.; Van Schijndel, M.W.; Van der Sluis, S.M.; Coenen, P.W.H.G; Zijlema, P.J.; Van den Berghe, G.; Guis, B.

    2009-04-01

    This report documents the 2009 Netherlands annual submission of its greenhouse gas emission inventory in accordance with the guidelines provided by the United Nations Framework Convention on Climate Change (UNFCCC), the Kyoto Protocol and the European Union's Greenhouse Gas Monitoring Mechanism. The report comprises explanations of observed trends in emissions; a description of an assessment of key sources and their uncertainty; documentation of methods, data sources and emission factors applied; and a description of the quality assurance system and the verification activities performed on the data

  14. Potential radionuclide emissions from stacks on the Hanford site, Part 2: Dose assessment methodology using portable low-resolution gamma spectroscopy

    Energy Technology Data Exchange (ETDEWEB)

    Barnett, J.M. [Westinghouse Hanford Company, Richland, WA (United States)

    1995-02-01

    In September 1992, the Westinghouse Hanford Company began developing an in situ measurement method to assess gamma radiation emanating from high-efficiency particulate air filters using portable low-resolution gamma spectroscopy. The purpose of the new method was to assess radioactive exhaust stack air emissions from empirical data rather than from theoretical models and to determine the potential unabated dose to an offsite theoretical maximally exposed individual. In accordance with Title 40, Code of Federal Regulations, Part 61, Subpart H, {open_quotes}National Emission Standards for Hazardous Air Pollutants{close_quotes}, stacks that have the potential to emit {ge} 1 {mu}Sv y{sup {minus}1} (0.1 mrem y{sup {minus}1}) to the maximally exposed individual are considered {open_quotes}major{close_quotes} and must meet the continuous monitoring requirements. After the method was tested and verified, the U.S. Environmental Protection Agency, Region 10, approved its use in June 1993. Of the 125 stacks operated by the Westinghouse Hanford Company, 22 were targeted for evaluation by this method, and 15 were assessed. (The method could not be applied at seven stacks because of excessive background radiation or because no gamma emitting particles appear in the emission stream.) The most significant result from this study was the redesignation of the T Plant main stack. The stack was assessed as being {open_quotes}minor{close_quotes}, and it now only requires periodic confirmatory measurements and meets federally imposed sampling requirements.

  15. National inventory of anhyd ric carbonic emissions providing of fuels consumption as energy source

    International Nuclear Information System (INIS)

    1994-01-01

    The Convention of the United Nations about Climatic Change, carried out in 1992, and whose ratification this being considerate d at level Parliament in the Republica Oriental del Uruguay, it has as objective to achieve the stabilization of the concentrations of gases of effect hot house in the atmosphere at a level that impedes interferences dangerous antropogenias. The National Direction of environment has carried out and Inventory of the Emissions of gas carbonic anhydride in the execution of the arisen commitments of the mentioned Convention. It being this the first step for the realization of a national inventory, which will not include the rest of the gases of effect hothouse controlled by the Protocols of Montreal. The inventory of the emissions carried out by the Division of Global and Regional Matters, it has been carried out for each one of the years understood in the period from 1987 to 1992 being studied the contribution of each sector of the national activity in the Emissions of carbonic anhydride.The results show that the total emissions estimated for Uruguay reach only the 6655 gigagrames of annual for the year 1992, being a light increase of the emission values among the years 1989 at 1992

  16. Radionuclide examinations

    International Nuclear Information System (INIS)

    Lentle, B.C.

    1989-01-01

    This paper reports on radionuclide examinations of the pancreas. The pancreas, situated retroperitonally high in the epigastrium, was a particularly difficult organ to image noninvasively before ultrasonography and computed tomography (CT) became available. Indeed the organ still remains difficult to examine in some patients, a fact reflected in the variety of methods available to evaluate pancreatic morphology. It is something of a paradox that the pancreas is metabolically active and physiologically important but that its examination by radionuclide methods has virtually ceased to have any role in day-to-day clinical practice. To some extent this is caused by the tendency of the pancreas's commonest gross diseases emdash carcinoma and pancreatitis, for example emdash to result in nonfunction of the entire organ. Disorders of pancreatic endocrine function have generally not required imaging methods for diagnosis, although an understanding of diabetes mellitus and its nosology has been advanced by radioimmunoassay of plasma insulin concentrations

  17. Radionuclide transfer

    International Nuclear Information System (INIS)

    Gerber, G.B.

    1993-01-01

    The research project described here had the aim to obtain further information on the transfer of nuclides during pregnancy and lactation. The tests were carried out in mini-pigs and rats receiving unchanging doses of radionuclides with the food. The following findings were revealed for the elements examined: Fe, Se, Cs and Zn were characterized by very high transfer levels in the mother, infant and foetus. A substantial uptake by the mother alone was observed for Co, Ag and Mn. The uptake by the foetus and infant here was 1 to 10 times lower. A preferential concentration in certain tissues was seen for Sr and Tc; the thyroid levels of Tc were about equally high in mothers and infants, while Sr showed less accumulation in the maternal bone. The lanthanide group of substances (Ce, Eu and Gd as well as Y and Ru) were only taken up to a very limited extent. The uptake of the examined radionuclides (Fe, Co, Ag, Ce) with the food ingested was found here to be ten times greater in rats as compared to mini-pigs. This showed that great caution must be observed, if the behaviour of radionuclides in man is extrapolated from relevant data obtained in rodents. (orig./MG) [de

  18. National- to port-level inventories of shipping emissions in China

    Science.gov (United States)

    Fu, Mingliang; Liu, Huan; Jin, Xinxin; He, Kebin

    2017-11-01

    Shipping in China plays a global role, and has led worldwide maritime transportation for the last decade. However, without taking national or local port boundaries into account, it is impossible to determine the responsibility that each local authority has on emission controls, nor compare them with land-based emissions to determine the priority for controlling these emissions. In this study, we provide national- to port-level inventories for China. The results show that in 2013, the total emissions of CO, non-methane volatile organic compounds (NMVOCs), nitrogen oxides (NO x ), particulate matter (PM), SO2 and CO2 were 0.0741 ± 0.0004 Tg•yr-1, 0.0691 ± 0.0004 Tg•yr-1, 1.91 ± 0.01 Tg•yr-1, 0.164 ± 0.001 Tg•yr-1, 1.30 ± 0.01 Tg•yr-1 and 86.3 ± 0.3 Tg•yr-1 in China, respectively. By providing high-resolution spatial distribution maps of these emissions, we identify three hotspots, centered on the Bohai Rim Area, the Yangtze River Delta and Pearl River Delta. These three hotspots account for 8% of the ocean area evaluated in this study, but contribute around 37% of total shipping emissions. Compared with on-road mobile source emissions, NO x and PM emissions from ships are equivalent to about 34% and 29% of the total mobile vehicle emissions in China. Moreover, this study provides detailed emission inventories for 24 ports in the country, which also greatly contributes to our understanding of global shipping emissions, given that eight of these ports rank within the top twenty of the port league table. Several ports in China suffer emissions 12-147 times higher than those at Los Angeles port. The ports of Ningbo-Zhou Shan, Shanghai, Hong Kong and Dalian dominate the port-level inventories, with individual emissions accounting for 28%-31%, 10%-14%, 10%-12% and 8%-14% of total emissions, respectively.

  19. Table of Radionuclides (Vol. 7 - A = 14 to 245) - Monograph BIPM-5

    International Nuclear Information System (INIS)

    Arinc, Arzu; Be, Marie-Martine; Chiste, Vanessa; Mougeot, Xavier; Chechev, Valery P.; Galan, Monica; Huang, Xialong; Kondev, Filip G.; Luca, Aurelian; Nichols, Alan L.

    2013-02-01

    This monograph is one of several published in a series by the Bureau International des Poids et Mesures (BIPM) on behalf of the Consultative Committee for Ionizing Radiation (Comite Consultatif des Rayonnements Ionisants, CCRI). The aim of this series of publications is to review topics that are of importance for the measurement of ionizing radiation and especially of radioactivity, in particular those techniques normally used by participants in international comparisons. The purpose of this monograph, number 5 in the series, is to present the recommended values of nuclear and decay data for a wide range of radionuclides. Activity measurements for more than sixty-three of these radionuclides have already been the subject of comparisons under the auspices of Section II (dedicated to the Measurement of radionuclides) of the CCRI. The material for this monograph is now covered in seven volumes. The first two volumes contain the primary recommended data relating to half-lives, decay modes, x-rays, gamma-rays, electron emissions; alpha- and beta-particle transitions and emissions, and their uncertainties for a set of sixty-eight radionuclides, Volume 1 for those radionuclides with mass number up to and including 150 and Volume 2 for those radionuclides with mass number over 150. Volume 3 contains the equivalent data for twenty-six additional radionuclides as listed and re-evaluations for 125 Sb and 153 Sm. Volume 4 contains the data for a further thirty-one radionuclides with a re-evaluation for 226 Ra and Volume 5 includes seventeen new radionuclide evaluations and eight re-evaluations of previous data as identified in the contents page. Volume 6 contains twenty-one new radionuclide evaluations and four re-evaluations, for 64 Cu, 236 Np, 37 Np and 239 U. The present Volume 7 contains twenty-four new radionuclide evaluations and five re-evaluations, for 67 Ga, 208 Tl, 228 Th, 242 Cm and 244 Cm. The data have been collated and evaluated by an international working group

  20. Greenhouse Gas Emissions in the Netherlands 1990-2006. National Inventory Report 2008

    International Nuclear Information System (INIS)

    Van der Maas, C.W.M.; Ruyssenaars, P.G.; Van den Born, G.J.; Brandes, L.J.; Hoen, A.; Te Molder, R.; Nijdam, D.S.; Olivier, J.G.J.; Peek, C.J.; Coenen, P.W.H.G.; Vreuls, H.H.J.; Van den Berghe, G.; Baas, K.; Guis, B.

    2008-01-01

    This report represents the 2008 Netherlands' annual inventory submission under the Kyoto Protocol and the United Nations Framework Convention on Climate Change (UNFCCC), as well as the European Union's Greenhouse Gas Monitoring Mechanism. It has been prepared following the relevant guidelines, which also refer to Revised 1996 IPCC Guidelines and IPCC Good Practice guidance and Uncertainty Management reports, provide a format for the definition of source categories and for calculation, documentation and reporting of emissions. The guidelines aim at facilitating verification, technical assessment and expert review of the inventory information by independent Expert Review Teams of the UNFCCC. Therefore, the inventories should be transparent, consistent, comparable, complete and accurate as elaborated in the UNFCCC Guidelines for reporting and be prepared using good practice as described in the IPCC Good Practice Guidance. This National Inventory Report (NIR) 2008 therefore provides explanations of the trends in greenhouse gas emissions, activity data and (implied) emission factors for the period 1990-2006. It also summarises descriptions of methods and data sources of Tier 1 assessments of the uncertainty in annual emissions and in emission trends; it presents an assessment of key sources following the Tier 1 and Tier 2 approaches of the IPCC Good Practice Guidance; and describes Quality Assurance and Quality Control activities. This report provides no specific information on the effectiveness of government policies for reducing greenhouse gas emissions. This information can be found in the annual Environmental Balance (in Dutch: 'Milieubalans') prepared by the Netherlands' Environmental Assessment Agency (MNP) and the 4th National Communication (NC4) prepared by the government of the Netherlands. So-called Common Reporting Format (CRF) spreadsheet files, containing data on emissions, activity data and implied emission factors, accompany this report. The complete set

  1. Emissions Inventory Report Summary for Los Alamos National Laboratory for Calendar Year 2009

    Energy Technology Data Exchange (ETDEWEB)

    Environmental Stewardship Group

    2010-10-01

    Los Alamos National Laboratory (LANL) is subject to annual emissions reporting requirements for regulated air pollutants under Title 20 of the New Mexico Administrative Code, Chapter 2, Part 73 (20.2.73 NMAC), Notice of Intent and Emissions Inventory Requirements. The applicability of the requirements is based on the Laboratory's potential to emit 100 tons per year of suspended particulate matter, nitrogen oxides, carbon monoxide, sulfur oxides, or volatile organic compounds. Additionally, on April 30, 2004, LANL was issued a Title V Operating Permit from the New Mexico Environment Department/Air Quality Bureau, under 20.2.70 NMAC. This permit was modified and reissued on July 16, 2007. This Title V Operating Permit (Permit No. P-100M2) includes emission limits and operating limits for all regulated sources of air pollution at LANL. The Title V Operating Permit also requires semiannual emissions reporting for all sources included in the permit. This report summarizes both the annual emissions inventory reporting and the semiannual emissions reporting for LANL for calendar year 2009. LANL's 2009 emissions are well below the emission limits in the Title V Operating Permit.

  2. Emissions inventory report summary for Los Alamos National Laboratory for calendar year 2008

    Energy Technology Data Exchange (ETDEWEB)

    Ecology and Air Quality Group

    2009-10-01

    Los Alamos National Laboratory (LANL) is subject to annual emissions reporting requirements for regulated air pollutants under Title 20 of the New Mexico Administrative Code, Chapter 2, Part 73 (20.2.73 NMAC), Notice of Intent and Emissions Inventory Requirements. The applicability of the requirements is based on the Laboratory’s potential to emit 100 tons per year of suspended particulate matter, nitrogen oxides, carbon monoxide, sulfur oxides, or volatile organic compounds. Additionally, on April 30, 2004, LANL was issued a Title V Operating Permit from the New Mexico Environment Department/Air Quality Bureau, under 20.2.70 NMAC. This permit was modified and reissued on July 16, 2007. This Title V Operating Permit (Permit No. P-100M2) includes emission limits and operating limits for all regulated sources of air pollution at LANL. The Title V Operating Permit also requires semiannual emissions reporting for all sources included in the permit. This report summarizes both the annual emissions inventory reporting and the semiannual emissions reporting for LANL for calendar year 2008. LANL’s 2008 emissions are well below the emission limits in the Title V Operating Permit.

  3. Greenhouse Gas Emissions in the Netherlands 1990-2009. National Inventory Report 2011

    Energy Technology Data Exchange (ETDEWEB)

    Coenen, P W.H.G.; Van der Hoek, K W; Te Molder, R; Droege, R [Netherlands Organisation for Applied Scientific Research TNO, P.O. Box 80015, NL-3508 TA Utrecht (Netherlands); Van der Maas, C W.M.; Zijlema, P J; Van den Berghe, A C.W.M. [NL Agency, P.O. Box 8242, NL-3503 RE Utrecht (Netherlands); Baas, K [Statistics Netherlands CBS, P.O. Box 24500, NL-2490 HA Den Haag (Netherlands); Te Biesebeek, J D; Brandt, A T [Dutch Emission Authority, P.O. Box 91503, IPC 652, NL-2509 EC Den Haag (Netherlands); Geilenkirchen, G [Netherlands Environmental Assessment Agency PBL, P.O. Box 303 NL-3720 AH Bilthoven (Netherlands); Montfoort, J A; Peek, C J; Vonk, J; Van den Wyngaert, I [Alterra Wageningen UR, P.O. Box 47 NL-6700 AA Wageningen (Netherlands)

    2012-03-15

    The total greenhouse gas emission from the Netherlands in 2010 increased by approximately 6% compared to the emission in 2009. This increase is mainly the result of increased fuel combustion in the energy sector and space heating. In 2010, total direct greenhouse gas emissions (excluding emissions from LULUCF - land use, land use change and forestry) in the Netherlands amounted to 210.1 Tg CO2 eq. This is approximately 1.5% below the emissions in the base year (213.3 Tg CO2 eq). This report documents the 2012 Netherlands' annual submission of its greenhouse gas emission inventory in accordance with the guidelines provided by the United Nations Framework Convention on Climate Change (UNFCCC), the Kyoto Protocol and the European Union's Greenhouse Gas Monitoring Mechanism. The report comprises explanations of observed trends in emissions; a description of an assessment of key sources and their uncertainty; documentation of methods, data sources and emission factors applied; and a description of the quality assurance system and the verification activities performed on the data.

  4. Greenhouse Gas Emissions in the Netherlands 1990-2011. National Inventory Report 2013

    Energy Technology Data Exchange (ETDEWEB)

    Coenen, P. W.H.G.; Droege, R. [Netherlands Organisation for Applied Scientific Research TNO, P.O. Box 80015, NL-3508 TA Utrecht (Netherlands); Zijlema, P. J. [NL Agency, P.O. Box 8242, NL-3503 RE Utrecht (Netherlands); Arets, E. J.M.M. [Alterra Wageningen UR, P.O. Box 47 NL-6700 AA Wageningen (Netherlands); Baas, K. [Statistics Netherlands CBS, P.O. Box 24500, NL-2490 HA Den Haag (Netherlands); Van den Berghe, A. C.W.M. [Rijkswaterstaat, P.O. Box 8242, NL-3503 RE Utrecht (Netherlands); Brandt, A. T. [Dutch Emissions Authority NEa, P.O. Box 91503, NL-2509 EC Den Haag (Netherlands); Geilenkirchen, G. [PBL Netherlands Environmental Assessment Agency, P.O. Box 303 NL-3720 AH Bilthoven (Netherlands); Van der Maas, C. W.M.; Te Biesebeek, J. D.; Van der Hoek, K. W.; Te Molder, R.; Montfoort, J. A.; Peek, C. J.; Vonk, J. [National Institute of Public Health and Environmental Protection RIVM, Bilthoven (Netherlands)

    2013-04-15

    Total greenhouse gas emissions from The Netherlands in 2011 decreased by approximately 7 per cent compared with 2010 emissions. This decrease is mainly the result of decreased fuel combustion in the Energy sector (less electricity production) and in the petrochemical industry. Fuel use for space heating decreased due to the mild winter compared with the very cold 2010 winter. In 2011, total direct greenhouse gas emissions (excluding emissions from LULUCF (land use, land use change and forestry) in The Netherlands amounted to 194.4 Tg CO2 eq. This is approximately 9 per cent below the emissions in the base year 2 (213.2 Tg CO2 eq). This report documents the Netherlands' 2012 annual submission of its greenhouse gas emissions inventory in accordance with the guidelines provided by the United Nations Framework Convention on Climate Change (UNFCCC), the Kyoto Protocol and the European Union's Greenhouse Gas Monitoring Mechanism. The report comprises explanations of observed trends in emissions; a description of an assessment of key sources and their uncertainty; documentation of methods, data sources and emission factors applied; and a description of the quality assurance system and the verification activities performed on the data.

  5. Greenhouse Gas Emissions in the Netherlands 1990-2010. National Inventory Report 2012

    Energy Technology Data Exchange (ETDEWEB)

    Coenen, P. W.H.G.; Van der Hoek, K. W.; Te Molder, R.; Droege, R. [Netherlands Organisation for Applied Scientific Research TNO, P.O. Box 80015, NL-3508 TA Utrecht (Netherlands); Van der Maas, C. W.M.; Zijlema, P. J.; Van den Berghe, A. C.W.M. [NL Agency, P.O. Box 8242, NL-3503 RE Utrecht (Netherlands); Baas, K. [Statistics Netherlands CBS, P.O. Box 24500, NL-2490 HA Den Haag (Netherlands); Te Biesebeek, J. D.; Brandt, A. T. [Dutch Emission Authority, P.O. Box 91503, IPC 652, NL-2509 EC Den Haag (Netherlands); Geilenkirchen, G. [Netherlands Environmental Assessment Agency PBL, P.O. Box 303 NL-3720 AH Bilthoven (Netherlands); Montfoort, J. A.; Peek, C. J.; Vonk, J.; Van den Wyngaert, I. [Alterra Wageningen UR, P.O. Box 47 NL-6700 AA Wageningen (Netherlands)

    2012-03-15

    The total greenhouse gas emission from the Netherlands in 2010 increased by approximately 6% compared to the emission in 2009. This increase is mainly the result of increased fuel combustion in the energy sector and space heating. In 2010, total direct greenhouse gas emissions (excluding emissions from LULUCF - land use, land use change and forestry) in the Netherlands amounted to 210.1 Tg CO2 eq. This is approximately 1.5% below the emissions in the base year (213.3 Tg CO2 eq). This report documents the 2012 Netherlands' annual submission of its greenhouse gas emission inventory in accordance with the guidelines provided by the United Nations Framework Convention on Climate Change (UNFCCC), the Kyoto Protocol and the European Union's Greenhouse Gas Monitoring Mechanism. The report comprises explanations of observed trends in emissions; a description of an assessment of key sources and their uncertainty; documentation of methods, data sources and emission factors applied; and a description of the quality assurance system and the verification activities performed on the data.

  6. Greenhouse Gas Emissions in the Netherlands 1990-2009. National Inventory Report 2011

    International Nuclear Information System (INIS)

    Van der Maas, C.W.M.; Coenen, P.W.H.G.; Van der Hoek, K.W.; Te Molder, R.; Droege, R.; Zijlema, P.J.; Van den Berghe, G.; Baas, K.; Te Biesebeek, J.D.; Brandt, A.T.; Geilenkirchen, G.; Peek, C.J.; Vonk, J.; Van den Wyngaert, I.

    2011-04-01

    The total greenhouse gas emission from the Netherlands in 2009 decreased by approximately 3% compared to the emission in 2008. This decrease is a result of the economic crisis, especially due to the decrease in the industrial production. In 2009, total direct greenhouse gas emissions (excluding emissions from LULUCF - land use, land use change and forestry) in the Netherlands amount to 198.9Tg CO2 eq. This is nearly 7 % below the emissions in the base year 1990 (213.2 Tg CO2 eq). This report documents the 2011 Netherlands' annual submission of its greenhouse gas emission inventory in accordance with the guidelines provided by the United Nations Framework Convention on Climate Change (UNFCCC), the Kyoto Protocol and the European Union's Greenhouse Gas Monitoring Mechanism. The report comprises explanations of observed trends in emissions; a description of an assessment of key sources and their uncertainty; documentation of methods, data sources and emission factors applied; and a description of the quality assurance system and the verification activities performed on the data.

  7. Greenhouse Gas Emissions in the Netherlands 1990-2010. National Inventory Report 2012

    Energy Technology Data Exchange (ETDEWEB)

    Coenen, P.W.H.G.; Van der Hoek, K.W.; Te Molder, R.; Droege, R. [Netherlands Organisation for Applied Scientific Research TNO, P.O. Box 80015, NL-3508 TA Utrecht (Netherlands); Van der Maas, C.W.M.; Zijlema, P.J.; Van den Berghe, A.C.W.M. [NL Agency, P.O. Box 8242, NL-3503 RE Utrecht (Netherlands); Baas, K. [Statistics Netherlands CBS, P.O. Box 24500, NL-2490 HA Den Haag (Netherlands); Te Biesebeek, J.D.; Brandt, A.T. [Dutch Emission Authority, P.O. Box 91503, IPC 652, NL-2509 EC Den Haag (Netherlands); Geilenkirchen, G. [Netherlands Environmental Assessment Agency PBL, P.O. Box 303 NL-3720 AH Bilthoven (Netherlands); Montfoort, J.A.; Peek, C.J.; Vonk, J.; Van den Wyngaert, I. [Alterra Wageningen UR, P.O. Box 47 NL-6700 AA Wageningen (Netherlands)

    2012-03-15

    The total greenhouse gas emission from the Netherlands in 2010 increased by approximately 6% compared to the emission in 2009. This increase is mainly the result of increased fuel combustion in the energy sector and space heating. In 2010, total direct greenhouse gas emissions (excluding emissions from LULUCF - land use, land use change and forestry) in the Netherlands amounted to 210.1 Tg CO2 eq. This is approximately 1.5% below the emissions in the base year (213.3 Tg CO2 eq). This report documents the 2012 Netherlands' annual submission of its greenhouse gas emission inventory in accordance with the guidelines provided by the United Nations Framework Convention on Climate Change (UNFCCC), the Kyoto Protocol and the European Union's Greenhouse Gas Monitoring Mechanism. The report comprises explanations of observed trends in emissions; a description of an assessment of key sources and their uncertainty; documentation of methods, data sources and emission factors applied; and a description of the quality assurance system and the verification activities performed on the data.

  8. Greenhouse Gas Emissions in the Netherlands 1990-2009. National Inventory Report 2011

    Energy Technology Data Exchange (ETDEWEB)

    Coenen, P.W.H.G.; Van der Hoek, K.W.; Te Molder, R.; Droege, R. [Netherlands Organisation for Applied Scientific Research TNO, P.O. Box 80015, NL-3508 TA Utrecht (Netherlands); Van der Maas, C.W.M.; Zijlema, P.J.; Van den Berghe, A.C.W.M. [NL Agency, P.O. Box 8242, NL-3503 RE Utrecht (Netherlands); Baas, K. [Statistics Netherlands CBS, P.O. Box 24500, NL-2490 HA Den Haag (Netherlands); Te Biesebeek, J.D.; Brandt, A.T. [Dutch Emission Authority, P.O. Box 91503, IPC 652, NL-2509 EC Den Haag (Netherlands); Geilenkirchen, G. [Netherlands Environmental Assessment Agency PBL, P.O. Box 303 NL-3720 AH Bilthoven (Netherlands); Montfoort, J.A.; Peek, C.J.; Vonk, J.; Van den Wyngaert, I. [Alterra Wageningen UR, P.O. Box 47 NL-6700 AA Wageningen (Netherlands)

    2012-03-15

    The total greenhouse gas emission from the Netherlands in 2010 increased by approximately 6% compared to the emission in 2009. This increase is mainly the result of increased fuel combustion in the energy sector and space heating. In 2010, total direct greenhouse gas emissions (excluding emissions from LULUCF - land use, land use change and forestry) in the Netherlands amounted to 210.1 Tg CO2 eq. This is approximately 1.5% below the emissions in the base year (213.3 Tg CO2 eq). This report documents the 2012 Netherlands' annual submission of its greenhouse gas emission inventory in accordance with the guidelines provided by the United Nations Framework Convention on Climate Change (UNFCCC), the Kyoto Protocol and the European Union's Greenhouse Gas Monitoring Mechanism. The report comprises explanations of observed trends in emissions; a description of an assessment of key sources and their uncertainty; documentation of methods, data sources and emission factors applied; and a description of the quality assurance system and the verification activities performed on the data.

  9. Emissions Inventory Report Summary for Los Alamos National Laboratory for Calendar Year 2006

    Energy Technology Data Exchange (ETDEWEB)

    Ecology and Air Quality Group

    2007-09-28

    Los Alamos National Laboratory (LANL) is subject to annual emissions reporting requirements for regulated air pollutants under Title 20 of the New Mexico Administrative Code, Chapter 2, Part 73 (20.2.73 NMAC), Notice of Intent and Emissions Inventory Requirements. The applicability of the requirements is based on the Laboratory's potential to emit 100 tons per year of suspended particulate matter, nitrogen oxides, carbon monoxide, sulfur oxides, or volatile organic compounds. Additionally, on April 30, 2004, LANL was issued a Title V Operating Permit from the New Mexico Environment Department, Air Quality Bureau, under 20.2.70 NMAC. Modification Number 1 to this Title V Operating Permit was issued on June 15, 2006 (Permit No P-100M1) and includes emission limits and operating limits for all regulated sources of air pollution at LANL. The Title V Operating Permit also requires semi-annual emissions reporting for all sources included in the permit. This report summarizes both the annual emissions inventory reporting and the semi-annual emissions reporting for LANL for calendar year 2006. LANL's 2006 emissions are well below the emission limits in the Title V Operating Permit.

  10. Greenhouse Gas Emissions in the Netherlands 1990-2011. National Inventory Report 2013

    Energy Technology Data Exchange (ETDEWEB)

    Coenen, P.W.H.G.; Droege, R. [Netherlands Organisation for Applied Scientific Research TNO, P.O. Box 80015, NL-3508 TA Utrecht (Netherlands); Zijlema, P.J. [NL Agency, P.O. Box 8242, NL-3503 RE Utrecht (Netherlands); Arets, E.J.M.M. [Alterra Wageningen UR, P.O. Box 47 NL-6700 AA Wageningen (Netherlands); Baas, K. [Statistics Netherlands CBS, P.O. Box 24500, NL-2490 HA Den Haag (Netherlands); Van den Berghe, A.C.W.M. [Rijkswaterstaat, P.O. Box 8242, NL-3503 RE Utrecht (Netherlands); Brandt, A.T. [Dutch Emissions Authority NEa, P.O. Box 91503, NL-2509 EC Den Haag (Netherlands); Geilenkirchen, G. [PBL Netherlands Environmental Assessment Agency, P.O. Box 303 NL-3720 AH Bilthoven (Netherlands); Van der Maas, C.W.M.; Te Biesebeek, J.D.; Van der Hoek, K.W.; Te Molder, R.; Montfoort, J.A.; Peek, C.J.; Vonk, J. [National Institute of Public Health and Environmental Protection RIVM, Bilthoven (Netherlands)

    2013-04-15

    Total greenhouse gas emissions from The Netherlands in 2011 decreased by approximately 7 per cent compared with 2010 emissions. This decrease is mainly the result of decreased fuel combustion in the Energy sector (less electricity production) and in the petrochemical industry. Fuel use for space heating decreased due to the mild winter compared with the very cold 2010 winter. In 2011, total direct greenhouse gas emissions (excluding emissions from LULUCF (land use, land use change and forestry) in The Netherlands amounted to 194.4 Tg CO2 eq. This is approximately 9 per cent below the emissions in the base year 2 (213.2 Tg CO2 eq). This report documents the Netherlands' 2012 annual submission of its greenhouse gas emissions inventory in accordance with the guidelines provided by the United Nations Framework Convention on Climate Change (UNFCCC), the Kyoto Protocol and the European Union's Greenhouse Gas Monitoring Mechanism. The report comprises explanations of observed trends in emissions; a description of an assessment of key sources and their uncertainty; documentation of methods, data sources and emission factors applied; and a description of the quality assurance system and the verification activities performed on the data.

  11. National Emission Standards for Hazardous Air Pollutants Calendar Year 1999

    International Nuclear Information System (INIS)

    Grossman, R.F.

    2000-01-01

    The Nevada Test Site (NTS) is operated by the US Department of Energy's Nevada Operations Office (DOE/NV) as the site for nuclear weapons testing, now limited to readiness activities and experiments in support of the national Stockpile Stewardship Management Program. It is located in Nye County, Nevada, with the southeast corner about 105 km (65 mi) northwest of Las Vegas, Nevada. The NTS covers about 3,561 km 2 (1,375 mi 2 ), an area larger than Rhode Island. Its size is about 46 to 56 km (28 to 35 mi) east to west and from 64 to 88 km (40 to 55 mi) north to south. The NTS is surrounded, except on the south side, by public exclusion areas (Nellis Air Force Range [NAFR]) that provide another 24 to 104 km (15 to 65 mi) between the NTS and public lands. The NTS is characterized by desert valley and Great Basin mountain topography, with a climate, flora, and fauna typical of the southwest deserts. Population density within 150 km (93 mi) of the NTS is only about 0.2 persons per square kilometer, excluding the Las Vegas area. Restricted access, low population density in the surrounding area, and extended wind transport times are advantageous factors for the activities conducted at the NTS. Surface waters are scarce on the NTS and there is great depth to slow-moving groundwater

  12. Forest carbon accounting methods and the consequences of forest bioenergy for national greenhouse gas emissions inventories

    International Nuclear Information System (INIS)

    McKechnie, Jon; Colombo, Steve; MacLean, Heather L.

    2014-01-01

    Highlights: • Forest carbon accounting influences the national GHG inventory impacts of bioenergy. • Current accounting rules may overlook forest carbon trade-offs of bioenergy. • Wood pellet trade risks creating an emissions burden for exporting countries. - Abstract: While bioenergy plays a key role in strategies for increasing renewable energy deployment, studies assessing greenhouse gas (GHG) emissions from forest bioenergy systems have identified a potential trade-off of the system with forest carbon stocks. Of particular importance to national GHG inventories is how trade-offs between forest carbon stocks and bioenergy production are accounted for within the Agriculture, Forestry and Other Land Use (AFOLU) sector under current and future international climate change mitigation agreements. Through a case study of electricity produced using wood pellets from harvested forest stands in Ontario, Canada, this study assesses the implications of forest carbon accounting approaches on net emissions attributable to pellets produced for domestic use or export. Particular emphasis is placed on the forest management reference level (FMRL) method, as it will be employed by most Annex I nations in the next Kyoto Protocol Commitment Period. While bioenergy production is found to reduce forest carbon sequestration, under the FMRL approach this trade-off may not be accounted for and thus not incur an accountable AFOLU-related emission, provided that total forest harvest remains at or below that defined under the FMRL baseline. In contrast, accounting for forest carbon trade-offs associated with harvest for bioenergy results in an increase in net GHG emissions (AFOLU and life cycle emissions) lasting 37 or 90 years (if displacing coal or natural gas combined cycle generation, respectively). AFOLU emissions calculated using the Gross-Net approach are dominated by legacy effects of past management and natural disturbance, indicating near-term net forest carbon increase but

  13. Biogenic emissions of greenhouse gases caused by arable and animal agriculture. Task 3. Overall biogenic greenhouse gas emissions from agriculture. National Inventories

    International Nuclear Information System (INIS)

    Hensen, A.

    1999-12-01

    The aim of the concerted action 'Biogenic Emissions of Greenhouse Gases Caused by Arable and Animal Agriculture' is to obtain an overview of the current knowledge on the emissions of greenhouse gases related to agricultural activities. This task 3 report summarises the activities that take place in the Netherlands with respect to agriculture emission inventories. This 'national' report was compiled using information from a number of Dutch groups. Therefore, from a national point of view the compilation does not contain new information. The paper can however be useful for other European partners to get an overview of how emission estimates are obtained in the Netherlands. 14 p

  14. Osteopetrosis: Radiological & Radionuclide Imaging

    International Nuclear Information System (INIS)

    Sit, Cherry; Agrawal, Kanhaiyalal; Fogelman, Ignac; Gnanasegaran, Gopinath

    2015-01-01

    Osteopetrosis is a rare inherited bone disease where bones harden and become abnormally dense. While the diagnosis is clinical, it also greatly relies on appearance of the skeleton radiographically. X-ray, radionuclide bone scintigraphy and magnetic resonance imaging have been reported to identify characteristics of osteopetrosis. We present an interesting case of a 59-year-old man with a history of bilateral hip fractures. He underwent 99m Tc-methylene diphosphonate whole body scan supplemented with single-photon emission computed tomography/computed tomography of spine, which showed increased uptake in the humeri, tibiae and femora, which were in keeping with osteopetrosis

  15. National plans for reducing greenhouse gas emissions in the Republic of Korea

    International Nuclear Information System (INIS)

    Ki Dong Song

    1996-01-01

    The present and future Korean emission of greenhouse gases are discussed in view of the current status of and projections of the national energy consumption under fast economic growth. Present dependence on energy import is very high (94.7%) and will only marginally decrease after a maximum of 97.1% in 2010 to 95.1% in 2030 due to increased use of renewables. The annual CO 2 emissions will be three times higher in 2030 and amount to almost 200 Mtonnes. The national CO 2 /energy intensity will decrease from 0.75 in 1990 to 0.69 in 2030. Coal combustion will remain the main source of CO 2 , whereas give the largest contribution to lowering the CO 2 intensity. The strategy and the bodies created to implement the commitments made by Korea to lower greenhouse gas emissions are described. (author). 14 tabs

  16. The decrease of CO2 emission intensity is decarbonization at national and global levels

    International Nuclear Information System (INIS)

    Sun, J.W.

    2005-01-01

    This viewpoint proposes the definition: 'Decarbonization refers to a decrease of CO 2 emission intensity in a trend'. This viewpoint then argues that an analysis of decarbonization at national and global levels based on that definition would lead to the correct calculation of decarbonization

  17. 77 FR 46371 - National Emission Standards for Hazardous Air Pollutants for the Portland Cement Manufacturing...

    Science.gov (United States)

    2012-08-03

    ...-AQ93 National Emission Standards for Hazardous Air Pollutants for the Portland Cement Manufacturing... Portland Cement Manufacturing Industry and Standards of Performance for Portland Cement Plants,'' which was... Manufacturing Industry and Standards of Performance for Portland Cement Plants'' under Docket ID No. EPA-HQ-OAR...

  18. 77 FR 42367 - National Emission Standards for Hazardous Air Pollutants for the Portland Cement Manufacturing...

    Science.gov (United States)

    2012-07-18

    ... and 63 National Emission Standards for Hazardous Air Pollutants for the Portland Cement Manufacturing... Standards for Hazardous Air Pollutants for the Portland Cement Manufacturing Industry and Standards of... manufacturing plants. Federal government Not affected. State/local/tribal government.... Portland cement...

  19. 77 FR 72294 - Reconsideration of Certain New Source and Startup/Shutdown Issues: National Emission Standards...

    Science.gov (United States)

    2012-12-05

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Parts 60 and 63 [EPA-HQ-OAR-2009-0234; EPA-HQ-OAR-2011-0044; FRL-9733-2] RIN 2060-AR62 Reconsideration of Certain New Source and Startup/Shutdown Issues: National Emission Standards for Hazardous Air Pollutants From Coal- and Oil-Fired Electric Utility Steam Generating...

  20. 78 FR 38001 - Reconsideration of Certain Startup/Shutdown Issues: National Emission Standards for Hazardous Air...

    Science.gov (United States)

    2013-06-25

    ..., FRL-9827-1] RIN 2060-AR62 Reconsideration of Certain Startup/Shutdown Issues: National Emission... published in the Federal Register the proposed rule, ``Reconsideration of Certain New Source and Startup....'' That proposal opened for reconsideration certain issues, including those related to startup and...

  1. 77 FR 16987 - National Emission Standards for Hazardous Air Pollutants: Secondary Aluminum Production

    Science.gov (United States)

    2012-03-23

    ... National Emission Standards for Hazardous Air Pollutants: Secondary Aluminum Production AGENCY... for secondary aluminum production (77 FR 8576). The EPA is extending the deadline for written comments... from the Aluminum Association. The Aluminum Association has requested the extension in order to allow...

  2. 78 FR 14457 - National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion...

    Science.gov (United States)

    2013-03-06

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Parts 60 and 63 [EPA-HQ-OAR-2008-0708, FRL-9756-4] RIN 2060-AQ58 National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion Engines; New Source Performance Standards for Stationary Internal Combustion Engines Correction In rule...

  3. 75 FR 80761 - National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion...

    Science.gov (United States)

    2010-12-23

    ... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 63 [EPA-HQ-OAR-2008-0708, FRL-9244-2] RIN 2060-AP36 National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion Engines... combustion engines and requesting public comment on one issue arising from the final rule. Specifically, EPA...

  4. The 2014 National Emission Inventory for Rangeland Fires and Crop Residue Burning

    Science.gov (United States)

    Biomass burning has been identified as an important contributor to the degradation of air quality because of its impact on ozone and particulate matter. One component of the biomass burning inventory, crop residue burning, has been poorly characterized in the National Emissions I...

  5. Anthropogenic Sulfur Dioxide Emissions, 1850-2005: National and Regional Data Set by Source Category, Version 2.86

    Data.gov (United States)

    National Aeronautics and Space Administration — The Anthropogenic Sulfur Dioxide Emissions, 1850-2005: National and Regional Data Set by Source Category, Version 2.86 provides annual estimates of anthropogenic...

  6. Radionuclides, stable isotopes, inorganic constituents, and organic compounds in water from selected wells and springs from the southern boundary of the Idaho National Engineering Laboratory to the Hagerman Area, Idaho, 1995

    International Nuclear Information System (INIS)

    Bartholomay, R.C.; Williams, L.M.; Campbell, L.J.

    1996-09-01

    The US Geological Survey and the Idaho Department of Water Resources, in cooperation with the US Department of Energy, sampled 17 sites as part of a long-term project to monitor water quality of the Snake River Plain aquifer from the southern boundary of the Idaho National Engineering Laboratory to the Hagerman area. Water samples were collected and analyzed for selected radionuclides, stable isotopes, inorganic constituents, and organic compounds. The samples were collected from 11 irrigation wells, 2 domestic wells, 2 stock wells, 1 spring, and 1 public-supply well. Two quality assurance samples also were collected and analyzed. None of the radionuclide, inorganic constituents, or organic compound concentrations exceeded the established maximum contaminant levels for drinking water. Many of the radionuclide and inorganic constituent concentrations were greater than their respective reporting levels. All samples analyzed for dissolved organic carbon had concentrations that were greater than the minimum reporting level

  7. Potential radionuclide emissions from stacks on the Hanford Site, Part 2: Dose assessment methodology using portable low-resolution gamma spectroscoy

    International Nuclear Information System (INIS)

    Barnett, J.M.

    1994-07-01

    In September 1992, the Westinghouse Hanford Company began developing an in situ measurement method to assess gamma radiation emanating from high-efficiency particulate air filters using portable low-resolution gamma spectroscopy. The purpose of the new method was to assess radioactive exhaust stack air emissions from empirical data rather than from theoretical models and to determine the potential unabated dose to an offsite theoretical maximally exposed individual. In accordance with Title 40, Code of Federal Regulations, Part 61, Subpart H, ''National Emission Standards for Hazardous Air Pollutants'', stacks that have the potential to emit ≥ 0.1 mrem per year to the maximally exposed individual are considered ''major'' and must meet the continuous monitoring requirements. After the method was tested and verified, the US Environmental Protection Agency, Region 10, approved its use in June 1993. Of the 125 stacks operated by the Westinghouse Hanford Company, 22 were targeted for evaluation by this method; and 15 were assessed. The most significant,result from this study was the redesignation. of the T Plant main stack. The stack was assessed as being ''minor'', and it now only requires periodic confirmatory measurements and meets federally imposed sampling requirements

  8. How a European network may help with estimating methane emissions on the French national scale

    Science.gov (United States)

    Pison, Isabelle; Berchet, Antoine; Saunois, Marielle; Bousquet, Philippe; Broquet, Grégoire; Conil, Sébastien; Delmotte, Marc; Ganesan, Anita; Laurent, Olivier; Martin, Damien; O'Doherty, Simon; Ramonet, Michel; Spain, T. Gerard; Vermeulen, Alex; Yver Kwok, Camille

    2018-03-01

    Methane emissions on the national scale in France in 2012 are inferred by assimilating continuous atmospheric mixing ratio measurements from nine stations of the European network ICOS located in France and surrounding countries. To assess the robustness of the fluxes deduced by our inversion system based on an objectified quantification of uncertainties, two complementary inversion set-ups are computed and analysed: (i) a regional run correcting for the spatial distribution of fluxes in France and (ii) a sectorial run correcting fluxes for activity sectors on the national scale. In addition, our results for the two set-ups are compared with fluxes produced in the framework of the inversion inter-comparison exercise of the InGOS project. The seasonal variability in fluxes is consistent between different set-ups, with maximum emissions in summer, likely due to agricultural activity. However, very high monthly posterior uncertainties (up to ≈ 65 to 74 % in the sectorial run in May and June) make it difficult to attribute maximum emissions to a specific sector. On the yearly and national scales, the two inversions range from 3835 to 4050 Gg CH4 and from 3570 to 4190 Gg CH4 for the regional and sectorial runs, respectively, consistently with the InGOS products. These estimates are 25 to 55 % higher than the total national emissions from bottom-up approaches (biogeochemical models from natural emissions, plus inventories for anthropogenic ones), consistently pointing at missing or underestimated sources in the inventories and/or in natural sources. More specifically, in the sectorial set-up, agricultural emissions are inferred as 66% larger than estimates reported to the UNFCCC. Uncertainties in the total annual national budget are 108 and 312 Gg CH4, i.e, 3 to 8 %, for the regional and sectorial runs respectively, smaller than uncertainties in available bottom-up products, proving the added value of top-down atmospheric inversions. Therefore, even though the surface

  9. How a European network may help with estimating methane emissions on the French national scale

    Directory of Open Access Journals (Sweden)

    I. Pison

    2018-03-01

    Full Text Available Methane emissions on the national scale in France in 2012 are inferred by assimilating continuous atmospheric mixing ratio measurements from nine stations of the European network ICOS located in France and surrounding countries. To assess the robustness of the fluxes deduced by our inversion system based on an objectified quantification of uncertainties, two complementary inversion set-ups are computed and analysed: (i a regional run correcting for the spatial distribution of fluxes in France and (ii a sectorial run correcting fluxes for activity sectors on the national scale. In addition, our results for the two set-ups are compared with fluxes produced in the framework of the inversion inter-comparison exercise of the InGOS project. The seasonal variability in fluxes is consistent between different set-ups, with maximum emissions in summer, likely due to agricultural activity. However, very high monthly posterior uncertainties (up to ≈ 65 to 74 % in the sectorial run in May and June make it difficult to attribute maximum emissions to a specific sector. On the yearly and national scales, the two inversions range from 3835 to 4050 Gg CH4 and from 3570 to 4190 Gg CH4 for the regional and sectorial runs, respectively, consistently with the InGOS products. These estimates are 25 to 55 % higher than the total national emissions from bottom-up approaches (biogeochemical models from natural emissions, plus inventories for anthropogenic ones, consistently pointing at missing or underestimated sources in the inventories and/or in natural sources. More specifically, in the sectorial set-up, agricultural emissions are inferred as 66% larger than estimates reported to the UNFCCC. Uncertainties in the total annual national budget are 108 and 312 Gg CH4, i.e, 3 to 8 %, for the regional and sectorial runs respectively, smaller than uncertainties in available bottom-up products, proving the added value of top-down atmospheric

  10. Delineating managed land for reporting national greenhouse gas emissions and removals to the United Nations framework convention on climate change.

    Science.gov (United States)

    Ogle, Stephen M; Domke, Grant; Kurz, Werner A; Rocha, Marcelo T; Huffman, Ted; Swan, Amy; Smith, James E; Woodall, Christopher; Krug, Thelma

    2018-05-29

    Land use and management activities have a substantial impact on carbon stocks and associated greenhouse gas emissions and removals. However, it is challenging to discriminate between anthropogenic and non-anthropogenic sources and sinks from land. To address this problem, the Intergovernmental Panel on Climate Change developed a managed land proxy to determine which lands are contributing anthropogenic greenhouse gas emissions and removals. Governments report all emissions and removals from managed land to the United Nations Framework Convention on Climate Change based on this proxy, and policy interventions to reduce emissions from land use are expected to focus on managed lands. Our objective was to review the use of the managed land proxy, and summarize the criteria that governments have applied to classify land as managed and unmanaged. We found that the large majority of governments are not reporting on their application of the managed land proxy. Among the governments that do provide information, most have assigned all area in specific land uses as managed, while designating all remaining lands as unmanaged. This designation as managed land is intuitive for croplands and settlements, which would not exist without management interventions, but a portion of forest land, grassland, and wetlands may not be managed in a country. Consequently, Brazil, Canada and the United States have taken the concept further and delineated managed and unmanaged forest land, grassland and wetlands, using additional criteria such as functional use of the land and accessibility of the land to anthropogenic activity. The managed land proxy is imperfect because reported emissions from any area can include non-anthropogenic sources, such as natural disturbances. However, the managed land proxy does make reporting of GHG emissions and removals from land use more tractable and comparable by excluding fluxes from areas that are not directly influenced by anthropogenic activity. Moreover

  11. DKPRO: A radionuclide decay and reprocessing code

    International Nuclear Information System (INIS)

    Wootan, D.; Schmittroth, F.A.

    1997-01-01

    The DKPRO code solves the general problem of modeling complex nuclear wastes streams using ORIGEN2 radionuclide production files. There is a continuing need for estimates of Hanford radionuclides. Physical measurements are one basis; calculational estimates, the approach represented here, are another. Given a known nuclear fuel history, it is relatively straightforward to calculate radionuclide inventories with codes such as the widely-used Oak Ridge National Laboratory code ORIGEN2

  12. The effect of lactation length on greenhouse gas emissions from the national dairy herd.

    Science.gov (United States)

    Wall, E; Coffey, M P; Pollott, G E

    2012-11-01

    Many governments have signed up to greenhouse gas emission (GHGE) reduction programmes under their national climate change obligations. Recently, it has been suggested that the use of extended lactations in dairy herds could result in reduced GHGE. Dairy GHGE were modelled on a national basis and the model was used to compare emissions from lactations of three different lengths (305, 370 and 440 days), and a current 'base' scenario on the basis of maintaining current milk production levels. In addition to comparing GHGE from the average 'National Herd' under these scenarios, results were used to investigate how accounting for lactations of different lengths might alter the estimation of emissions calculated from the National Inventory methodology currently recommended by Intergovernmental Panel on Climate Change. Data for the three lactation length scenarios were derived from nationally recorded dairy performance information and used in the GHGE model. Long lactations required fewer milking cows and replacements to maintain current milk yield levels than short ones, but GHGEs were found to rise from 1214 t of CO2 equivalent (CE)/farm per year for lactations of 305 days to 1371 t CE/farm per year for 440-day lactations. This apparent anomaly can be explained by the less efficient milk production (kg milk produced per kg cow weight) found in later lactation, a more pronounced effect in longer lactations. The sensitivity of the model to changes in replacement rate, persistency and level of milk yield was investigated. Changes in the replacement rate from 25% to 20% and in persistency by −10% to +20% resulted in very small changes in GHGE. Differences in GHGE due to the level of milk yield were much more dramatic with animals in the top 10% for yield, producing about 25% less GHGE/year than the average animal. National Inventory results were investigated using a more realistic spread of lactation lengths than recommended for such calculations using emissions

  13. 23 CFR Appendix A to Part 772 - National Reference Energy Mean Emission Levels as a Function of Speed

    Science.gov (United States)

    2010-04-01

    ... 23 Highways 1 2010-04-01 2010-04-01 false National Reference Energy Mean Emission Levels as a Function of Speed A Appendix A to Part 772 Highways FEDERAL HIGHWAY ADMINISTRATION, DEPARTMENT OF... NOISE Pt. 772, App. A Appendix A to Part 772—National Reference Energy Mean Emission Levels as a...

  14. Methodical aspects of radionuclide study of locomotor system in patients with systemic diseases of connective tissue with single photon emission computed tomography

    International Nuclear Information System (INIS)

    Potsibyina, V.V.; Oderyij, Je.A.

    1998-01-01

    The original technique was used to examine 427 patients aged 18-64 with systemic diseases of locomotor system connective tissue and 65 controls. In addition to clinical studies, radionuclide signs of locomotor system lesions was investigated with NUCLETRON APEX SP-6 CT unit using labeled with Tc-99m and osteotropic radiopharmaceuticals

  15. Radionuclides in food

    International Nuclear Information System (INIS)

    Fernandez Gomez, Isis Maria

    2008-01-01

    The sources of the presence of radionuclides in food are presented: natural radiation and artificial radiation. The transfer of radionuclides through food chains, intakes of radionuclides to the body with its partners effective doses and typical consumption of basic foods of a rural adult population are exposed as main topics. Also the radiation doses from natural sources and exposure to man by ingestion of contaminated food with radionuclides of artificial origin are shown. The contribution of the food ingestion to the man exposure depends on: characteristics of radionuclide, natural conditions, farming practices and eating habits of the population. The principal international organizations in charge of setting guide levels for radionuclides in food are mentioned: standards, rules and the monitoring. It establishes that a guide is necessary for the food monitoring; the alone CODEX ALIMENTARIUS is applicable to emergency situations and the generic action levels proposed by the CODEX not satisfy all needs (no guiding international levels for planned or existing situations such as NORM). There are handled mainly socio-economic and political aspects. Among the actions to be taken are: to assure a public comprehensive information over the risk evaluation in food; to reinforce the collaboration among the different international organizations (WHO, IAEA, ICRP, EC) in relation with the food of set; to give follow-up to the control of the drinkable water and NORM's presence in the food. In addition, it is possible to create the necessary mechanisms to reduce the number of irrelevant measures and bureaucratic useless steps (certificates); to promote the exchange between the different institutions involved in the topic of the food, with relation to the acquired experiences and learned lessons. Likewise, it might examine the possibility of a multidisciplinary approximation (radioactive and not radioactive pollutants); to elaborate a technical guide to assure the

  16. Characterization of road freight transportation and its impact on the national emission inventory in China

    Science.gov (United States)

    Yang, X. F.; Liu, H.; Man, H. Y.; He, K. B.

    2014-06-01

    monitoring data on different roads. Depending on the results in this research, the largest differences among the emission factors (in g km-1) on different roads exceed 70 and 50% for NOx and PM2.5, respectively. The differences were caused by different driving conditions that we monitored via GPS. The estimated NOx and PM2.5 emissions from diesel freight trucks in China were 5.0 (4.8-7.2) million t and 0.20 (0.17-0.22) million t, respectively, via the REIB approach in 2011. Another implication of this research is that different road infrastructure would have different impacts for NOx and PM2.5 emissions. A region with more inter-city freeways or national roads tends to have more NOx emissions, while urban streets play a more important role in primary PM2.5 emissions from freight trucks. Compared with former studies, which allocate emissions according to local truck registration number and neglect inter-region long distance transport trips, the REIB approach has advantages regarding the allocation of diesel truck emissions into the provinces. Furthermore, the different driving conditions on the different roads types are no longer overlooked with this approach.

  17. Proficiency testing for radionuclides

    International Nuclear Information System (INIS)

    Faanhof, A.; Kotze, O.; Louw, I.

    2010-01-01

    Proficiency testing in general is only useful when it suites a certain purpose. With regards to radionuclides basically three fields of interest can be identified: (I)Foodstuffs-Introduced in the early 1960's to monitor the fall-out of nuclear tests and eventually the pathway to foodstuffs fit for human consumption. The demand for analysis increased substantially after the Chernobyl accident. (II) Natural radioactivity-Associated with mining and mineral processing of uranium and thorium baring mineral resources throughout the world where the radionuclides from the natural uranium and thorium decay series are found to pose concern for professional and public exposure. (III) Artificial radioactivity-This category covers mostly the long-lived nuclides generated by nuclear fission of the fuel used in nuclear power plants, research reactors and nuclear bomb tests. All three categories require a specific approach for laboratories to test their ability to analyze specific radio nuclides of interest in a variety of matrices. In this lecture I will give a compiled overview of the required radioanalytical skills, analysis sensitivity needed and radionuclides of interest, with more specific emphasis on QAQC of water sources and the recommended monitoring approach. And provide information on available reference materials and organizations/institutes that provide regular exercises for participating laboratories. I will also briefly communicate on the advantages and disadvantages of ISO/IEC 17025 accreditation for test laboratories, which is these days a prerequisite in national and international trade especially where foodstuffs and mineral products are concerned.

  18. Derivation of residual radioactive material guidelines for 13 radionuclides present in Operable Unit IV at Brookhaven National Laboratory, Upton, New York

    International Nuclear Information System (INIS)

    Faillace, E.; Nimmagadda, M.; Yu, C.

    1994-12-01

    Residual radioactive material guidelines for 13 radionuclides (americium-241; cobalt-60; cesium-137; europium-152, -154, and -155; plutonium-238, -239, and -240; strontium-90; and uranium-234, -235, and -238) were derived for Operable Unit (OU) IV at Brookhaven National Laboratory. This site has been identified for remedial action under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980, as amended by the Superfund Amendments and Reauthorization Act of 1986. Single-nuclide guidelines were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of OU IV should not exceed a dose constraint of 30 mrem/yr following remedial action for the current use and plausible future use scenarios or a dose limit of 100 mrem/yr for plausible but less likely future use scenarios. The US Department of Energy (DOE) residual radioactive material guideline computer code, RESRAD, was used in this evaluation; RESRAD implements the methodology described in the DOE manual for determining residual radioactive material guidelines. Four potential scenarios were considered; each assumed that, for a period of 1,000 years following remedial action, the site would be used without radiological restrictions. The four scenarios varied with regard to the type of site use, time spent at the site, and sources of food consumed

  19. Implementation of a metrology national network for radionuclides used in nuclear medicine; Implementacao de uma rede nacional de metrologia de radionuclideos utilizados em medicina nuclear

    Energy Technology Data Exchange (ETDEWEB)

    Santos, J.A. dos; Lopes, R.T. [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-Graduacao de Engenharia (COPPE)], e-mail: joyra@ird.gov.br, e-mail: ricardo@lin.ufrj.br; Iwahara, A.; Tauhata, L. [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Lab. Nacional de Metrologia das Radiacoes Ionizantes (LNMRI)], e-mail: iwahara@ird.gov.br, e-mail: tauhata@ird.gov.br; Nicoli, I.G.; Dias, C.M. [Comissao Nacional de Energia Nuclear (DIPLAN/CNEN-DF), Brasilia, DF (Brazil). Distrito do Planalto], e-mail: ieda@cnen.gov.br, e-mail: cintia@cnen.gov.br

    2003-07-01

    The Brazilian Laboratory for Metrology of Ionizing Radiation (LNMRI), of the Radioprotection and Dosimetry Institute, owned by the National Commission of Nuclear Energy (IRD/CNEN-RJ) has conducting since 1998, a comparison program for measurements of radiopharmaceuticals activities applied to patients at Nuclear Medicine sector aiming to the assessment the quality of those measurements. In the Rio de Janeiro state this program is successfully performed existing however the necessity to implement such program all over the country. This problem is being solved through the implementation of a reference laboratories network at several points in the brazilian territory. For the establishment and good working of the network the following factors must be observed: the radionuclide calibrators at the reference laboratories must be connected to the LNMRI; the operators must be trained by the staff or the LNMRI, and the quality guarantee must be assured through a comparison program. Presently, the network point placed in Brasilia is running and covering all the center-west region. The results obtained at this region show that the implementation of the metrology network is viable, important and achievable.

  20. A Cancun stake: to revitalize climate cooperation while improving transparency about national greenhouse gas emissions

    International Nuclear Information System (INIS)

    2010-12-01

    After having recalled the instruments which are available for the UNFCCC (United Nations Framework Convention on Climate Change) to ensure an as much as transparent as possible information transmission between states about greenhouse gas emissions, this article questions the way the Copenhagen agreement can be implemented while considering the discussions which took place. It draws lessons from other previous examples of international cooperation: WTO agreements, the Clean Development Mechanism. Three propositions are made in the perspective of the Cancun conference: to create a reliable world inventory of emissions, to organize cooperation with countries wishing to define statistics for their emission monitoring, and to reinforce transparency and control of measures (with the MRV criteria) which are subsidized by the international community

  1. Comparison of models used for national agricultural ammonia emission inventories in Europe

    DEFF Research Database (Denmark)

    Reidy, B; Webb, J; Misselbrook, T H

    2009-01-01

    Six N-flow models, used to calculate national ammonia (NH3) emissions from agriculture in different European countries, were compared using standard data sets. Scenarios for litter-based systems were run separately for beef cattle and for broilers, with three different levels of model...... of total ammoniacal-N (TAN) (±6% of the mean total), but large differences in NH3 emissions (±24% of the mean). These differences arose from the different approaches to TAN immobilization in litter, other N losses and mineralization in the models. As a result of those differences estimates of TAN available...... at spreading differed by a factor of almost 3. Results of the FF scenario for broilers produced a range of estimates of total changes in TAN (±9% of the mean total), and larger differences in the estimate of NH3 emissions (±17% of the mean). The different approaches among the models to TAN immobilization...

  2. Anthropogenic radionuclides in the environment

    Energy Technology Data Exchange (ETDEWEB)

    Hu, Q; Weng, J; Wang, J

    2007-11-15

    Studies of radionuclides in the environment have entered a new era with the renaissance of nuclear energy and associated fuel reprocessing, geological disposal of high-level nuclear wastes, and concerns about national security with respect to nuclear non-proliferation. This work presents an overview of anthropogenic radionuclide contamination in the environment, as well as the salient geochemical behavior of important radionuclides. We first discuss the following major anthropogenic sources and current development that contribute to the radionuclide contamination of the environment: (1) nuclear weapons program; (2) nuclear weapons testing; (3) nuclear power plants; (4) commercial fuel reprocessing; (5) geological repository of high-level nuclear wastes, and (6) nuclear accidents. Then, we summarize the geochemical behavior for radionuclides {sup 99}Tc, {sup 129}I, and {sup 237}Np, because of their complex geochemical behavior, long half-lives, and presumably high mobility in the environment. Biogeochemical cycling and environment risk assessment must take into account speciation of these redox-sensitive radionuclides.

  3. National greenhouse gas emissions baseline scenarios. Learning from experiences in developing countries

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-04-15

    This report reviews national approaches to preparing baseline scenarios of greenhouse-gas (GHG) emissions. It does so by describing and comparing in non-technical language existing practices and choices made by ten developing countries - Brazil, China, Ethiopia, India, Indonesia, Kenya, Mexico, South Africa, Thailand and Vietnam. The review focuses on a number of key elements, including model choices, transparency considerations, choices about underlying assumptions and challenges associated with data management. The aim is to improve overall understanding of baseline scenarios and facilitate their use for policy-making in developing countries more broadly. The findings are based on the results of a collaborative project involving a number of activities undertaken by the Danish Energy Agency, the Organisation for Economic Co-operation and Development (OECD) and the UNEP Risoe Centre (URC), including a series of workshops on the subject. The ten contributing countries account for approximately 40% of current global GHG emissions - a share that is expected to increase in the future. The breakdown of emissions by sector varies widely among these countries. In some countries, the energy sector is the leading source of emissions; for others, the land-use sector and/or agricultural sector dominate emissions. The report underscores some common technical and financial capacity gaps faced by developing countries when preparing baseline scenarios. It does not endeavour to propose guidelines for preparing baseline scenarios. Rather, it is hoped that the report will inform any future attempts at preparing such kind of guidelines. (Author)

  4. The effect of trade between China and the UK on national and global carbon dioxide emissions

    International Nuclear Information System (INIS)

    Li, You; Hewitt, C.N.

    2008-01-01

    We estimate the amount of carbon dioxide embodied in bi-lateral trade between the UK and China in 2004. Developing and applying the method of Shui and Harriss [2006. The role of CO 2 embodiment in US-China trade. Energy Policy 34, 4063-4068], the most recently available data on trade and CO 2 emissions have been updated and adjusted to calculate the CO 2 emissions embodied in the commodities traded between China and the UK. It was found that through trade with China, the UK reduced its CO 2 emissions by approximately 11% in 2004, compared with a non-trade scenario in which the same type and volume of goods are produced in the UK. In addition, due to the greater carbon-intensity and relatively less efficient production processes of Chinese industry, China-UK trade resulted in an additional 117 Mt of CO 2 to global CO 2 emissions in the same one year period, compared with a non-trade scenario in which the same type and volume of goods are produced in the UK. This represents an additional 19% to the reported national CO 2 emissions of the UK (555 Mt/y in 2004) and 0.4% of global emissions. These findings suggest that, through international trade, very significant environmental impacts can be shifted from one country to another, and that international trade can (but does not necessarily) result in globally increased greenhouse gas emissions. These results are additional to the environmental consequences of transporting goods, which are not robustly quantified here. (author)

  5. A national day with near zero emissions and its effect on primary and secondary pollutants

    Science.gov (United States)

    Levy, Ilan

    2013-10-01

    Traffic related air pollution is a major health concern in many countries. The potential costs and benefits of different abatement policies are usually estimated by either models, case studies or previously implemented intervention measures. Such estimations have, however, limited ability to predict the effect of a reduction in primary pollutants' emissions on secondary pollutants such as ozone, because of the nonlinear nature of the photochemical reactions. This study examines the short term effects of a drastic change in emissions on a national scale during the Jewish holiday of Day of Atonement (DA) in Israel. During the holiday nearly all anthropogenic emission sources are ceased for a period of 25 h, including all vehicles, commercial, industrial and recreational activities. DAs during the 15 years period of 1998-2012 are analyzed at three sites with respect to primary and secondary air pollutants, and in greater details for 2001. A dramatic decrease in primary pollutants emissions (83-98% in NO) causes an 8 ppbv increase in ozone at the urban core. Downwind (27 km), ozone decreases by only 5 ppbv. Nighttime O3 is shown to increase to 20 ppbv at the urban sites and 30 ppbv downwind. In spite of the striking reduction in emissions, changes in ozone are not greater than what is reported in the literature about less significant events like the ozone weekend effect. Changes in ambient pollution levels observed during DA provide some indication to the possible outcomes of a major change in anthropogenic emissions. These may be considered as the best case scenario for emissions reduction intervention measures and thus aid policy makers in evaluating potential benefits of such measures.

  6. Radionuclide decay data-evaluation and dissemination

    International Nuclear Information System (INIS)

    Helmer, R.G.

    1994-01-01

    There are many applications of nuclear chemistry and physics, as the variety of contents of this symposium demonstrate. Many of these applications require a knowledge of data on the decay of radionuclides, e.g., half-lives and radiation energies and emission probabilities. For over 50 years, people have been compiling and evaluating the measured data to obtain recommended values of these quantities. This has resulted in numerous sets of recommended values, many of which still have scientific, historical, or national reasons for existing. This history provides a background to the current situation which involves the coexistence of the Table of Radioactive isotopes, the ENSDF file and the Nuclear Data Sheets, the Table de Radionucleides, IAEA Coordinated Research Program results, the ENDF/B-VI decay data file, etc. Visions of the future include new styles of evaluations and feedback from interested users

  7. Carbon uptake by mature Amazon forests has mitigated Amazon nations' carbon emissions.

    Science.gov (United States)

    Phillips, Oliver L; Brienen, Roel J W

    2017-12-01

    Several independent lines of evidence suggest that Amazon forests have provided a significant carbon sink service, and also that the Amazon carbon sink in intact, mature forests may now be threatened as a result of different processes. There has however been no work done to quantify non-land-use-change forest carbon fluxes on a national basis within Amazonia, or to place these national fluxes and their possible changes in the context of the major anthropogenic carbon fluxes in the region. Here we present a first attempt to interpret results from ground-based monitoring of mature forest carbon fluxes in a biogeographically, politically, and temporally differentiated way. Specifically, using results from a large long-term network of forest plots, we estimate the Amazon biomass carbon balance over the last three decades for the different regions and nine nations of Amazonia, and evaluate the magnitude and trajectory of these differentiated balances in relation to major national anthropogenic carbon emissions. The sink of carbon into mature forests has been remarkably geographically ubiquitous across Amazonia, being substantial and persistent in each of the five biogeographic regions within Amazonia. Between 1980 and 2010, it has more than mitigated the fossil fuel emissions of every single national economy, except that of Venezuela. For most nations (Bolivia, Colombia, Ecuador, French Guiana, Guyana, Peru, Suriname) the sink has probably additionally mitigated all anthropogenic carbon emissions due to Amazon deforestation and other land use change. While the sink has weakened in some regions since 2000, our analysis suggests that Amazon nations which are able to conserve large areas of natural and semi-natural landscape still contribute globally-significant carbon sequestration. Mature forests across all of Amazonia have contributed significantly to mitigating climate change for decades. Yet Amazon nations have not directly benefited from providing this global scale

  8. Methodology for implementation of a national metrology net of radionuclides used in nuclear medicine; Metodologia para a implementacao de uma rede de referencia para metrologia de radiofarmacos no Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Joyra Amaral dos

    2004-01-15

    The National Laboratory for Ionizing Radiation Metrology, of the Institute of Radiation Protection and Dosimetry, of the National Commission on Nuclear Energy (IRD/CNEN), comes leading a comparison program for activity measurements of radiopharmaceuticals administered to patients in the Nuclear Medicine Services (NMS) with the purpose to promote the quality control. This work presents a quality assurance program for the performance of such measurements, evaluated in the comparison runs between hospitals and LNMRI, under the statistic point of view and the compliment of regulatory authority norms. The performance of the radionuclides {sup 67}Ga, {sup 123}I, {sup 131}I,{sup 99m}Tc and {sup 210}Tl were evaluated and {sup 201}TI have been standardized by absolute methods. Besides, it was established the traceability of the radioactivity standards used in nuclear medicine and a methodology for implementation of a national metrology net of radionuclides. The comparison results prove that the implementation of a radionuclide metrology net is viable, important and feasible. (author)

  9. Methane and nitrous oxide: Methods in national emissions inventories and options for control

    Energy Technology Data Exchange (ETDEWEB)

    Van Amstel, A.R. (ed.)

    1993-07-01

    The UN Framework Convention on Climate Change signed in Rio de Janeiro, Brazil, calls for the return of anthropogenic emissions of greenhouse gases to their 1990 levels by the year 2000 in industrialized countries. It also calls for a monitoring of the emissions of greenhouse gases. It is important that reliable and scientifically credible national inventories are available for the international negotiations. Therefore a consistent methodology and a transparent reporting format is needed. The title workshop had two main objectives: (1) to support the development a methodology and format for national emissions inventories of greenhouse gases by mid 1993, as coordinated by the Science Working Group of the IPCC and the OECD; and (2) the development of technical options for reduction of greenhouse gases and the assessment of the socio-economic feasibility of these options. The workshop consisted of key note overview presentations, and two rounds of working group sessions, each covering five parallel sessions on selected sources. In the first round of each working group session the literature, existing methods for methane and nitrous oxide inventories, and the OECD/IPCC guidelines have been addressed. Then, in the second round, options for emission reductions have been discussed, as well as their socio-economic implications. The methane sources discussed concern oil and gas, coal mining, ruminants, animal waste, landfills and sewage treatment, combustion and industry, rice production and wetlands, biomass burning. The nitrous oxide sources discussed are agricultural soils and combustion and industry. The proceedings on methane comprise 16 introductory papers and 7 papers on the results of the working groups, while in part two four introductory papers and two papers on the results of working groups on nitrous oxide are presented. In part three future emission reduction policy options are discussed. Finally, 16 poster contributions are included

  10. National inventories of air emissions in France: organisation and methodology - 8. edition - OMINEA, February 2011

    International Nuclear Information System (INIS)

    Fontelle, Jean-Pierre; Allemand, Nadine; Andre, Jean-Marc; Bastide, Aurelie; Chang, Jean-Pierre; Deflorenne, Emmanuel; Druart, Ariane; Gavel, Antoine; Gueguen, Celine; Jabot, Julien; Jacquier, Guillaume; Joya, Romain; Kessouar, Sabrina; Martinet, Yann; Mathias, Etienne; Nicco, Laetitia; Prouteau, Emilie; Serveau, Laetitia; Tuddenham, Mark; Vincent, Julien

    2011-01-01

    Usually, various methods are used to estimate emissions of atmospheric pollutants from anthropogenic or natural sources. These methods which are more or less specific, require large quantities of data to carry out what is commonly named 'emission inventories', 'cadastres' or 'registers' depending on characteristics of the collection in terms of spatial and sectoral resolution. The OMINEA report includes a description of the national inventory system of pollutant emissions into the atmosphere (SNIEPA) which deals with the following topics: organisation, break down of responsibilities and coverage. Technical operational arrangements are described and various elements relating to reference documents and definitions, control and quality assurance, estimation of uncertainties are provided. A description is given for each emitting source category and for several substances classified in the following topics: 'greenhouse gases', 'acidification and photochemical pollution', 'eutrophication', 'heavy metals', 'persistent organic pollutants', 'particulate matter', 'other'. The plan is based on the international reporting format defined by the United Nations within the framework of conventions on climate change and long range transboundary air pollution (sources categories listed in CRFI/NFR)

  11. National inventories of air emissions in France: organisation and methodology - 9. edition - OMINEA, February 2011

    International Nuclear Information System (INIS)

    Fontelle, Jean-Pierre; Andre, Jean-Marc; Bastide, Aurelie; Bort, Romain; Chang, Jean-Pierre; Deflorenne, Emmanuel; Druart, Ariane; Gavel, Antoine; Gueguen, Celine; Jabot, Julien; Jacquier, Guillaume; Jeannot, Coralie; Joya, Romain; Kessouar, Sabrina; Martinet, Yann; Mathias, Etienne; Nicco, Laetitia; Serveau, Laetitia; Tuddenham, Mark; Vasudeva, Divya; Vincent, Julien

    2012-01-01

    Usually, various methods are used to estimate emissions of atmospheric pollutants from anthropogenic or natural sources. These methods which are more or less specific, require large quantities of data to carry out what is commonly named 'emission inventories', 'cadastres' or 'registers' depending on characteristics of the collection in terms of spatial and sectoral resolution. The OMINEA report includes a description of the national inventory system of pollutant emissions into the atmosphere (SNIEPA) which deals with the following topics: organisation, break down of responsibilities and coverage. Technical operational arrangements are described and various elements relating to reference documents and definitions, control and quality assurance, estimation of uncertainties are provided. A description is given for each emitting source category and for several substances classified in the following topics: 'greenhouse gases', 'acidification and photochemical pollution', 'eutrophication', 'heavy metals', 'persistent organic pollutants', 'particulate matter', 'other'. The plan is based on the international reporting format defined by the United Nations within the framework of conventions on climate change and long range transboundary air pollution (sources categories listed in CRFI/NFR)

  12. 100 Years of radionuclide metrology

    International Nuclear Information System (INIS)

    Judge, S.M.; Arnold, D.; Chauvenet, B.; Collé, R.; De Felice, P.; García-Toraño, E.; Wätjen, U.

    2014-01-01

    The discipline of radionuclide metrology at national standards institutes started in 1913 with the certification by Curie, Rutherford and Meyer of the first primary standards of radium. In early years, radium was a valuable commodity and the aim of the standards was largely to facilitate trade. The focus later changed to providing standards for the new wide range of radionuclides, so that radioactivity could be used for healthcare and industrial applications while minimising the risk to patients, workers and the environment. National measurement institutes responded to the changing demands by developing new techniques for realising primary standards of radioactivity. Looking ahead, there are likely to be demands for standards for new radionuclides used in nuclear medicine, an expansion of the scope of the field into quantitative imaging to facilitate accurate patient dosimetry for nuclear medicine, and an increasing need for accurate standards for radioactive waste management and nuclear forensics. - Highlights: • The driving forces for the development of radionuclide metrology. • Radium standards to facilitate trade of this valuable commodity in the early years. • After 1950, focus changes to healthcare and industrial applications. • National Measurement Institutes develop new techniques, standards, and disseminate the best practice in measurement. • Challenges in nuclear medicine, radioactive waste management and nuclear forensics

  13. The effects of economic and political integration on power plants’ carbon emissions in the post-soviet transition nations

    Science.gov (United States)

    Jorgenson, Andrew K.; Longhofer, Wesley; Grant, Don; Sie, Amanda; Giedraitis, Vincentas

    2017-04-01

    The combustion of fossil fuels for electricity generation, which accounts for a significant share of the world’s CO2 emissions, varies by macro-regional context. Here we use multilevel regression modeling techniques to analyze CO2 emissions levels in the year 2009 for 1360 fossil-fuel power plants in the 25 post-Soviet transition nations in Central and Eastern Europe and Eurasia. We find that various facility-level factors are positively associated with plant-level emissions, including plant size, age, heat rate, capacity utilization rate, and coal as the primary fuel source. Results further indicate that plant-level emissions are lower, on average, in the transition nations that joined the European Union (EU), whose market reforms and environmental directives are relevant for emissions reductions. These negative associations between plant-level emissions and EU accession are larger for the nations that joined the EU in 2004 relative to those that joined in 2007. The findings also suggest that export-oriented development is positively associated with plant-level CO2 emissions in the transition nations. Our results highlight the importance in macro-regional assessments of the conjoint effects of political and economic integration for facility-level emissions.

  14. Electron Bernstein wave emission based diagnostic on National Spherical Torus Experiment (invited)

    International Nuclear Information System (INIS)

    Diem, S.; Taylor, G.; Caughman, John B.; Efthimion, P.C.; Kugel, H.; LeBlanc, B.; Preinhaelter, J.; Sabbagh, S.A.; Urban, J.

    2008-01-01

    National Spherical Torus Experiment (NSTX) is a spherical tokamak (ST) that operates with n(e) up to 10(20) m(-3) and B-T less than 0.6 T, cutting off low harmonic electron cyclotron (EC) emission widely used for T-e measurements on conventional aspect ratio tokamaks. The electron Bernstein wave (EBW) can propagate in ST plasmas and is emitted at EC harmonics. These properties suggest thermal EBW emission (EBE) may be used for local T-e measurements in the ST. Practically, a robust T-e(R,t) EBE diagnostic requires EBW transmission efficiencies of >90% for a wide range of plasma conditions. EBW emission and coupling physics were studied on NSTX with an obliquely viewing EBW to O-mode (B-X-O) diagnostic with two remotely steered antennas, coupled to absolutely calibrated radiometers. While T-e(R,t) measurements with EBW emission on NSTX were possible, they were challenged by several issues. Rapid fluctuations in edge n(e) scale length resulted in >20% changes in the low harmonic B-X-O transmission efficiency. Also, B-X-O transmission efficiency during H modes was observed to decay by a factor of 5-10 to less than a few percent. The B-X-O transmission behavior during H modes was reproduced by EBE simulations that predict that EBW collisional damping can significantly reduce emission when T-e < 30 eV inside the B-X-O mode conversion (MC) layer. Initial edge lithium conditioning experiments during H modes have shown that evaporated lithium can increase T-e inside the B-X-O MC layer, significantly increasing B-X-O transmission.

  15. Electron Bernstein Wave Emission Based Diagnostic on National Spherical Torus Experiment

    International Nuclear Information System (INIS)

    Diem, S.; Taylor, G.; Caughman, John B.; Efthimion, P.C.; Kugel, H.; LeBlanc, B.; Preinhaelter, J.; Sabbagh, S.A.; Urban, J.; Wilgen, John B.

    2008-01-01

    National Spherical Torus Experiment (NSTX) is a spherical tokamak (ST) that operates with n(e) up to 10(20) m(-3) and B(T) less than 0.6 T, cutting off low harmonic electron cyclotron (EC) emission widely used for T(e) measurements on conventional aspect ratio tokamaks. The electron Bernstein wave (EBW) can propagate in ST plasmas and is emitted at EC harmonics. These properties suggest thermal EBW emission (EBE) may be used for local T(e) measurements in the ST. Practically, a robust T(e)(R,t) EBE diagnostic requires EBW transmission efficiencies of >90% for a wide range of plasma conditions. EBW emission and coupling physics were studied on NSTX with an obliquely viewing EBW to O-mode (B-X-O) diagnostic with two remotely steered antennas, coupled to absolutely calibrated radiometers. While T(e)(R,t) measurements with EBW emission on NSTX were possible, they were challenged by several issues. Rapid fluctuations in edge n(e) scale length resulted in >20% changes in the low harmonic B-X-O transmission efficiency. Also, B-X-O transmission efficiency during H modes was observed to decay by a factor of 5-10 to less than a few percent. The B-X-O transmission behavior during H modes was reproduced by EBE simulations that predict that EBW collisional damping can significantly reduce emission when T(e)< 30 eV inside the B-X-O mode conversion (MC) layer. Initial edge lithium conditioning experiments during H modes have shown that evaporated lithium can increase T(e) inside the B-X-O MC layer, significantly increasing B-X-O transmission.

  16. A vector Wiener filter for dual-radionuclide imaging

    International Nuclear Information System (INIS)

    Links, J.M.; Prince, J.L.; Gupta, S.N.

    1996-01-01

    The routine use of a single radionuclide for patient imaging in nuclear medicine can be complemented by studies employing two tracers to examine two different processes in a single organ, most frequently by simultaneous imaging of both radionuclides in two different energy windows. In addition, simultaneous transmission/emission imaging with dual-radionuclides has been described, with one radionuclide used for the transmission study and a second for the emission study. There is thus currently considerable interest in dual-radionuclide imaging. A major problem with all dual-radionuclide imaging is the crosstalk between the two radionuclides. Such crosstalk frequently occurs, because scattered radiation from the higher energy radionuclide is detected in the lower energy window, and because the lower energy radionuclide may have higher energy emissions which are detected in the higher energy window. The authors have previously described the use of Fourier-based restoration filtering in single photon emission computed tomography (SPECT) and positron emission tomography (PET) to improve quantitative accuracy by designing a Wiener or other Fourier filter to partially restore the loss of contrast due to scatter and finite spatial resolution effects. The authors describe here the derivation and initial validation of an extension of such filtering for dual-radionuclide imaging that simultaneously (1) improves contrast in each radionuclide's direct image, (2) reduces image noise, and (3) reduces the crosstalk contribution from the other radionuclide. This filter is based on a vector version of the Wiener filter, which is shown to be superior [in the minimum mean square error (MMSE) sense] to the sequential application of separate crosstalk and restoration filters

  17. Dose Assessment of Los Alamos National Laboratory-Derived Residual Radionuclides in Soils within Tract A-18-2 for Land Conveyance and Transfer Decisions

    Energy Technology Data Exchange (ETDEWEB)

    Ruedig, Elizabeth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Whicker, Jeffrey Jay [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-08-07

    In 2017, soil sampling for radiological materials was conducted within Tract A-18-2 specifically for land conveyance decisions. Measurements of radionuclides in soil samples were evaluated against a recreational use scenario, and all measurements were below screening action levels for each radionuclide. The total estimated dose was less than 1 mrem/y (< 10 μSv/y) for a hypothetical recreational user (compared to a dose limit of 25 mrem/y (250 μSv/y)). Dose estimates were based on the 95% upper confidence limits for radionuclide concentrations within the Tract. Additionally, dose estimates less than 3 mrem/y are considered to be As Low As Reasonably Achievable, so no follow-up analysis was conducted. Release of this property is consistent with the requirements of DOE Order 458.1 and Policy 412.

  18. Criteria and air-toxic emissions from in-use automobiles in the National Low-Emission Vehicle program.

    Science.gov (United States)

    Baldauf, Rich W; Gabele, Pete; Crews, William; Snow, Richard; Cook, J Rich

    2005-09-01

    The U.S. Environmental Protection Agency (EPA) implemented a program to identify tailpipe emissions of criteria and air-toxic contaminants from in-use, light-duty low-emission vehicles (LEVs). EPA recruited 25 LEVs in 2002 and measured emissions on a chassis dynamometer using the cold-start urban dynamometer driving schedule of the Federal Test Procedure. The emissions measured included regulated pollutants, particulate matter, speciated hydrocarbon compounds, and carbonyl compounds. The results provided a comparison of emissions from real-world LEVs with emission standards for criteria and air-toxic compounds. Emission measurements indicated that a portion of the in-use fleet tested exceeded standards for the criteria gases. Real-time regulated and speciated hydrocarbon measurements demonstrated that the majority of emissions occurred during the initial phases of the cold-start portion of the urban dynamometer driving schedule. Overall, the study provided updated emission factor data for real-world, in-use operation of LEVs for improved emissions modeling and mobile source inventory development.

  19. Local actions to reduce greenhouse gas emissions in the context of national action plans

    International Nuclear Information System (INIS)

    Harvey, L.D.D.

    1995-01-01

    Municipalities can play a number of important roles to complement national actions to limit greenhouse gas emissions: (i) by facilitating comprehensive, city-wide building retrofit activities; (ii) by facilitating the development and/or expansion of community integrated energy systems involving district heating, district cooling, and cogeneration of electricity; and (iii) by promoting urban intensification to reduce the need to use the private automobile. Innovative institutional and financial mechanism are needed to overcome some of the persistent barriers to more efficient energy use in buildings and a number of concepts, which are currently being considered by the City of Toronto as part of its programme to reduce CO 2 emissions by 20% from the 1988 level by 2005, are discussed here. These concepts involve using public securitization funds to leverage private sector funds for energy efficiency retrofits and a number of measures to reduce financing and retrofit transaction costs. Even where surplus electricity generating capacity exists at the regional scale, reduced electricity demand can still result in avoided utility system costs if transmission bottlenecks and future transmission and transformer upgrade costs are reduced. Finally, given the need to replace or modify many of the existing commercial chillers due to the phase out of CFC's, a window of opportunity exists during the next few years to provide alternative, chlorocarbon-free district cooling systems based on absorption chillers using waste heat from electricity generation, with significant (30-65%) CO 2 emission savings. (au)

  20. Radionuclides in terrestrial ecosystems

    International Nuclear Information System (INIS)

    Allen, S.E.; Horrill, A.D.; Howard, B.J.; Lowe, V.P.W.; Parkinson, J.A.

    1983-07-01

    The subject is discussed under the headings: concentration and spatial distribution of radionuclides in grazed and ungrazed saltmarshes; incorporation of radionuclides by sheep grazing on an estuarine saltmarsh; inland transfer of radionuclides by birds feeding in the estuaries and saltmarshes at Ravenglass; radionuclides in contrasting types of coastal pastures and taken up by individual plant species found in west Cumbria; procedures developed and used for the measurement of alpha and gamma emitters in environmental materials. (U.K.)

  1. Potential for post-closure radionuclide redistribution due to biotic intrusion: aboveground biomass, litter production rates, and the distribution of root mass with depth at material disposal area G, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    French, Sean B.; Christensen, Candace; Jennings, Terry L.; Jaros, Christopher L.; Wykoff, David S.; Crowell, Kelly J.; Shuman, Rob

    2008-01-01

    Low-level radioactive waste (LLW) generated at the Los Alamos National Laboratories (LANL) is disposed of at LANL's Technical Area (T A) 54, Material Disposal Area (MDA) G. The ability of MDA G to safely contain radioactive waste during current and post-closure operations is evaluated as part of the facility's ongoing performance assessment (PA) and composite analysis (CA). Due to the potential for uptake and incorporation of radio nuclides into aboveground plant material, the PA and CA project that plant roots penetrating into buried waste may lead to releases of radionuclides into the accessible environment. The potential amount ofcontamination deposited on the ground surface due to plant intrusion into buried waste is a function of the quantity of litter generated by plants, as well as radionuclide concentrations within the litter. Radionuclide concentrations in plant litter is dependent on the distribution of root mass with depth and the efficiency with which radionuclides are extracted from contaminated soils by the plant's roots. In order to reduce uncertainties associated with the PA and CA for MDA G, surveys are being conducted to assess aboveground biomass, plant litter production rates, and root mass with depth for the four prominent vegetation types (grasses, forbs, shrubs and trees). The collection of aboveground biomass for grasses and forbs began in 2007. Additional sampling was conducted in October 2008 to measure root mass with depth and to collect additional aboveground biomass data for the types of grasses, forbs, shrubs, and trees that may become established at MDA G after the facility undergoes final closure, Biomass data will be used to estimate the future potential mass of contaminated plant litter fall, which could act as a latent conduit for radionuclide transport from the closed disposal area. Data collected are expected to reduce uncertainties associated with the PA and CA for MDA G and ultimately aid in the assessment and subsequent

  2. Radionuclides, inorganic constitutents, organic compounds, and bacteria in water from selected wells and springs from the southern boundary of the Idaho National Engineering Laboratory to the Hagerman Area, Idaho, 1992

    International Nuclear Information System (INIS)

    Bartholomay, R.C.; Edwards, D.D.; Campbell, L.J.

    1994-01-01

    The U.S. Geological Survey and the Idaho Department of Water Resources, in response to a request from the U.S. Department of Energy, sampled 18 sites as part of a long-term project to monitor water quality of the Snake River Plain aquifer from the southern boundary of the Idaho National Engineering Laboratory to the Hagerman area. Water samples were collected and analyzed for selected radionuclides, inorganic constituents, organic compounds, and bacteria. The samples were collected from 13 irrigation wells, 1 domestic well, 1 spring, 2 stock wells, and 1 public supply well. Quality assurance samples also were collected and analyzed. None of the samples analyzed for radionuclides, inorganic constituents, or organic compounds exceeded the established maximum contaminant levels for drinking water. Most of the radionuclide and inorganic constituent concentrations exceeded their respective reporting levels. Most of the samples analyzed for surfactants and dissolved organic carbon had concentrations that exceeded their reporting levels. None of the samples contained reportable concentrations of purgeable organic compounds or pesticides. Total coliform bacteria was present in nine samples

  3. Radionuclides, stable isotopes, inorganic constituents, and organic compounds in water from selected wells and springs from the southern boundary of the Idaho National Engineering Laboratory to the Hagerman area, Idaho, 1993

    Science.gov (United States)

    Bartholomay, Roy C.; Edwards, Daniel D.; Campbell, Linford J.

    1994-01-01

    The U.S. Geological Survey and the Idaho Department of Water Resources, in response to a request from the U.S. Department of Energy, sampled 19 sites as part of a long-term project to monitor water quality of the Snake River Plain aquifer from the southern boundary of the Idaho National Engineering Laboratory to the Hagerman area. Water samples were collected and analyzed for selected radionuclides, stable isotopes, inorganic constituents, and organic compounds. The samples were collected from seven irrigation wells, four domestic wells, two springs, one stock well, three dairy wells, one observation well, and one commercial well. Two quality assurance samples also were collected and analyzed. None of the radionuclides, inorganic constituents, or organic compounds exceeded the established maximum contaminant levels for drinking water. Most of the radionuclide and inorganic constituent concen- trations exceeded their respective laboratory reporting levels. All samples analyzed for surfactants and dissolved organic carbon had concentrations that exceeded their reporting level. Ethylbenzene concentrations exceeded the reporting level in one water sample.

  4. Radionuclides, inorganic constituents, organic compounds, and bacteria in water from selected wells and springs from the southern boundary of the Idaho National Engineering Laboratory to the Hagerman Area, Idaho, 1990

    International Nuclear Information System (INIS)

    Bartholomay, R.C.; Edwards, D.D.; Campbell, L.J.

    1992-03-01

    The US Geological Survey and the Idaho Department of Water Resources, in response to a request from the US Department of Energy, sampled 19 sites as part of a long-term project to monitor water quality of the Snake River Plain aquifer from the southern boundary of the Idaho National Engineering Laboratory to the Hagerman area. Water samples were collected and analyzed for manmade pollutants and naturally occurring constituents. The samples were collected from seven irrigation wells, five domestic wells, two springs, one stock well, two dairy wells, one observation well, and one commercial well. Two quality assurance samples also were collected and analyzed. The water samples were analyzed for selected radionuclides, inorganic constituents, organic compounds, and bacteria. None of the radionuclides, inorganic constituents, or organic compounds exceeded the established maximum contaminant levels for drinking water. Most of the radionuclide and inorganic constituent concentrations exceeded their respective reporting levels. All samples analyzed for surfactants and dissolved organic carbon had concentrations that exceeded their reporting level. Toluene concentrations exceeded the reporting level in one water sample. Two samples contained fecal coliform bacteria counts that exceeded established maximum contaminant levels for drinking water

  5. National intercomparison program applied to water radionuclide analysis in SEAMB - CRCN/NE, Brazil; Programa nacional de intercomparação aplicado a análises de radionuclídeos em água no SEAMB - CRCN/NE

    Energy Technology Data Exchange (ETDEWEB)

    Bastos, Thiago M. R.; Santos, Thiago O.; Neto, Alberto P.; Farias, Emerson E. G.; Filho, Crescêncio A. S.; França, Elvis J. De, E-mail: thiagomrbastos@gmail.com, E-mail: thiago_cbufpe@yahoo.com.br, E-mail: nibbering4@gmail.com, E-mail: emersonemiliano@yahoo.com.br, E-mail: candrade@cnen.gov.br, E-mail: ejfranca@cnen.gov.br [Centro Regional de Ciências Nucleares do Nordeste (CRCN-NE/CNEN-PE), Recife, PE (Brazil)

    2017-07-01

    Water is essential for mankind in its most diverse uses and an evaluation of its quality is necessary, especially when used for human consumption. The Brazilian Ministry of Health established through the Ordinance 36 in 1990 the standards and norms of water potability, and among the parameters to be monitored are the concentrations of activities present in the water bodies. Given the importance of water as one of the main ways of exposure to natural radionuclide emissions due to its frequent ingestion, by providing man with higher natural radiation doses than those normally received by terrestrial radiation, it is necessary the continuous radiological control of waters used for consumption. The existence of laboratories that have certified quality in the analysis of these radioisotopes in water is essential and for this, programs have been created that seek to integrate the results of analysis of environmental samples of water for the determination of radionuclides at the national level, such as the National Intercomparison Program (PNI), promoted by the Institute of Radioprotection and Dosimetry (IRD) of which the Regional Nuclear Science Center of the Northeast (CRCN-NE) is a member since 2011. Until the year 2016, were reported to IRD, the program manager, for statistical evaluation and for analytical performance, 17 analyzes that presented average values of 1,67BqL{sup -1} for {sup 60}Co, 3,712 Bq L{sup -1} for {sup 65}Zn, 7,812 Bq L{sup -1} for {sup 1}'0{sup 6}Ru, 3,06 Bq L{sup -1} for {sup 133}Ba, 1,19 Bq L{sup -1} for the {sup 134}Cs and 1,50 Bq L{sup -1} for the {sup 137}Cs. These analysis were reported by the PNI, certifying the analytical capacity of the Environmental Monitoring Service of the Regional Center of Nuclear Sciences Northeastern Brazil in the determination of radioisotopes in water by Gamma Spectrometry using Hyperpure Germanium - HPGe detectors.

  6. Relating β+ radionuclides' properties by order theory

    International Nuclear Information System (INIS)

    Quintero, N.Y.; Guillermo Restrepo; Cohen, I.M.; Universidad Tecnologica Nacional, Buenos Aires

    2013-01-01

    We studied 27 β + radionuclides taking into account some of their variants encoding information of their production, such as integral yield, threshold energy and energy of projectiles used to generate them; these radionuclides are of current use in clinical diagnostic imaging by positron emission tomography (PET). The study was conducted based on physical, physico-chemical, nuclear, dosimetric and quantum properties, which characterise the β + radionuclides selected, with the aim of finding meaningful relationships among them. In order to accomplish this objective the mathematical methodology known as formal concept analysis was employed. We obtained a set of logical assertions (rules) classified as implications and associations, for the set of β + radionuclides considered. Some of them show that low mass defect is related to high and medium values of maximum β + energy, and with even parity and low mean lives; all these parameters are associated to the dose received by a patient subjected to a PET analysis. (author)

  7. Impact of inter-sectoral trade on national and global CO2 emissions: An empirical analysis of China and US

    International Nuclear Information System (INIS)

    Guo Jie; Zou Lele; Wei Yiming

    2010-01-01

    This paper attempts to discuss the CO 2 emissions embodied in Sino-US international trade using a sector approach. Based on an input-output model established in this study, we quantify the impact of Sino-US international trade on national and global CO 2 emissions. Our initial findings reveal that: In 2005, the US reduced 190.13 Mt CO 2 emissions through the consumption of imported goods from China, while increasing global CO 2 emissions by about 515.25 Mt. Similarly, China reduced 178.62 Mt CO 2 emissions through the consumption of US goods, while reducing global CO 2 emissions by 129.93 Mt. Sino-US international trade increased global CO 2 emissions by 385.32 Mt as a whole, of which the Chemical, Fabricated Metal Products, Non-metallic Mineral Products and Transportation Equipment sectors contributed an 86.71% share. Therefore, we suggest that accelerating the adjustment of China's trade structure and export of US advanced technologies and experience related to clean production and energy efficiency to China as the way to reduce the negative impact of Sino-US trade on national and global CO 2 emissions. This behavior should take into account the processing and manufacturing industries as a priority, especially the Chemical, Fabricated Metal Products, Non-metallic Mineral Products and Transportation Equipment sectors.

  8. International marine and aviation bunker fuel. Trends, ranking of countries and comparison with national CO2 emission

    International Nuclear Information System (INIS)

    Olivier, J.G.J.; Peters, J.A.H.W.

    1999-01-01

    This report summarises and characterises fuel consumption and associated CO2 emissions from international transport based on energy statistics compiled by the International Energy Agency (IEA). Shares in 1990 and 1970-1995 trends in national and global bunker fuel consumption and associated CO2 emissions are analysed for marine and air transport. Also, the global total of international transport emissions are compared with national emissions and domestic transport emissions. During the last 25 years the average global annual increase was for marine bunkers about 0.8% and for aviation emissions about 3.3%. Annual variations per country of marine bunker fuel use larger than of aviation fuel use, sometimes more than 50%. However, the distinction between fuel use for domestic and for international aviation is more difficult to monitor. The dominant fuel in marine bunker fuel consumption is residual fuel oil ('heavy fuel oil'). The share of diesel oil has slowly increased from 11% in 1970 to 20% in 1990. Aviation fuels sold are predominantly jet fuel ('jet kerosene'). The small share of aviation gasoline is slowly decreasing: from about 4% in 1970 to 1.3% in 1990. Carbon dioxide emissions from combustion of international marine bunker fuels and aviation contributed in 1990 globally about 1.8% and 2.4% expressed as percentage of global total anthropogenic emissions (excluding deforestation). However, aviation emissions include an unknown part of domestic aviation. When comparing with total transport emissions, then international transport has a share of 20%. For both marine and aviation bunker fuel, the Top-10 of largest consuming countries account for about 2/3 of the global total; the Top-25 countries cover already 85% or more of global total CO2 emissions

  9. Quantifying the uncertainties of China's emission inventory for industrial sources: From national to provincial and city scales

    Science.gov (United States)

    Zhao, Yu; Zhou, Yaduan; Qiu, Liping; Zhang, Jie

    2017-09-01

    A comprehensive uncertainty analysis was conducted on emission inventories for industrial sources at national (China), provincial (Jiangsu), and city (Nanjing) scales for 2012. Based on various methods and data sources, Monte-Carlo simulation was applied at sector level for national inventory, and at plant level (whenever possible) for provincial and city inventories. The uncertainties of national inventory were estimated at -17-37% (expressed as 95% confidence intervals, CIs), -21-35%, -19-34%, -29-40%, -22-47%, -21-54%, -33-84%, and -32-92% for SO2, NOX, CO, TSP (total suspended particles), PM10, PM2.5, black carbon (BC), and organic carbon (OC) emissions respectively for the whole country. At provincial and city levels, the uncertainties of corresponding pollutant emissions were estimated at -15-18%, -18-33%, -16-37%, -20-30%, -23-45%, -26-50%, -33-79%, and -33-71% for Jiangsu, and -17-22%, -10-33%, -23-75%, -19-36%, -23-41%, -28-48%, -45-82%, and -34-96% for Nanjing, respectively. Emission factors (or associated parameters) were identified as the biggest contributors to the uncertainties of emissions for most source categories except iron & steel production in the national inventory. Compared to national one, uncertainties of total emissions in the provincial and city-scale inventories were not significantly reduced for most species with an exception of SO2. For power and other industrial boilers, the uncertainties were reduced, and the plant-specific parameters played more important roles to the uncertainties. Much larger PM10 and PM2.5 emissions for Jiangsu were estimated in this provincial inventory than other studies, implying the big discrepancies on data sources of emission factors and activity data between local and national inventories. Although the uncertainty analysis of bottom-up emission inventories at national and local scales partly supported the ;top-down; estimates using observation and/or chemistry transport models, detailed investigations and

  10. Limit of the radionuclides in granite

    International Nuclear Information System (INIS)

    Wang Shaling; Jiang Rangrong

    2003-01-01

    Granite is an important sort of building materials. Their radionuclide contents are limited by the national standard GB6566-2001 just as other building materials. This standard divides them into main materials and decorative materials, and relaxes the limit of the latter obviously. Owing to the consideration of public dose limit and environment protection, this method needs discussion. Otherwise, red granite contains high radionuclide contents relatively, especially the sort of Indian Red, and need be paid more attention

  11. Naturally occurring radionuclides in food

    International Nuclear Information System (INIS)

    Djujic, I.

    1995-01-01

    The naturally occurring radionuclides are the major source of radiation exposure to humans. The principal way of natural radiation exposure is the inhalation of 222 Rn decay products (about 85% of the total). The remainder is equally divided between internally deposited radionuclides, cosmic and terrestrial sources. In the present study, the content of 40 K, 210 Pb, 226 Ra, 230 Th, 232 Th and 238 U in representative food samples (milk, pork, beef, potatoes, wheat and corn flour) and samples of different food items that do not represent entire national production but provide interesting additional data for approximative calculation of naturally occurring radionuclide intake is presented. Daily weight of food eaten, participation of food groups, as well as daily intake by food of mentioned naturally occurring radionuclides in the Serbian diet was obtained on the base of house hold budget surveys. The result obtained for daily intake estimates in mBq for Serbian population are 78.1 ( 40 K), 38.2( 210 Pb), 52.3( 226 Ra), 2.0( 230 Th) and 12.5( 238 U). (author)

  12. Integrated Evaluation of Cost, Emissions, and Resource Potential for Algal Biofuels at the National Scale

    Energy Technology Data Exchange (ETDEWEB)

    Davis, Ryan; Fishman, Daniel; Frank, Edward D.; Johnson, Michael C.; Jones, Susanne B.; Kinchin, Christopher; Skaggs, Richard; Venteris, Erik R.; Wigmosta, Mark S.

    2014-04-21

    Costs, emissions, and resource availability were modeled for the production of 5 billion gallons yr-1 (5 BGY) of renewable diesel in the United States from Chlorella biomass by hydrothermal liquefaction (HTL). The HTL model utilized data from a continuous 1-L reactor including catalytic hydrothermal gasification of the aqueous phase, and catalytic hydrotreatment of the HTL oil. A biophysical algae growth model coupled with weather and pond simulations predicted biomass productivity from experimental growth parameters, allowing site-by-site and temporal prediction of biomass production. The 5 BGY scale required geographically and climatically distributed sites. Even though screening down to 5 BGY significantly reduced spatial and temporal variability, site-to-site, season-to-season, and inter-annual variations in productivity affected economic and environmental performance. Performance metrics based on annual average or peak productivity were inadequate; temporally and spatially explicit computations allowed more rigorous analysis of these dynamic systems. For example, 3-season operation with a winter shutdown was favored to avoid high greenhouse gas emissions, and economic performance was harmed by underutilized equipment during slow-growth periods. Thus, analysis of algal biofuel pathways must combine spatiotemporal resource assessment, economic analysis, and environmental analysis integrated over many sites when assessing national scale performance.

  13. Integrated evaluation of cost, emissions, and resource potential for algal biofuels at the national scale.

    Science.gov (United States)

    Davis, Ryan E; Fishman, Daniel B; Frank, Edward D; Johnson, Michael C; Jones, Susanne B; Kinchin, Christopher M; Skaggs, Richard L; Venteris, Erik R; Wigmosta, Mark S

    2014-05-20

    Costs, emissions, and resource availability were modeled for the production of 5 billion gallons yr(-1) (5 BGY) of renewable diesel in the United States from Chlorella biomass by hydrothermal liquefaction (HTL). The HTL model utilized data from a continuous 1-L reactor including catalytic hydrothermal gasification of the aqueous phase, and catalytic hydrotreatment of the HTL oil. A biophysical algae growth model coupled with weather and pond simulations predicted biomass productivity from experimental growth parameters, allowing site-by-site and temporal prediction of biomass production. The 5 BGY scale required geographically and climatically distributed sites. Even though screening down to 5 BGY significantly reduced spatial and temporal variability, site-to-site, season-to-season, and interannual variations in productivity affected economic and environmental performance. Performance metrics based on annual average or peak productivity were inadequate; temporally and spatially explicit computations allowed more rigorous analysis of these dynamic systems. For example, 3-season operation with a winter shutdown was favored to avoid high greenhouse gas emissions, but economic performance was harmed by underutilized equipment during slow-growth periods. Thus, analysis of algal biofuel pathways must combine spatiotemporal resource assessment, economic analysis, and environmental analysis integrated over many sites when assessing national scale performance.

  14. Speciation analysis of radionuclides

    International Nuclear Information System (INIS)

    Salbu, B.

    2010-01-01

    Full text: Naturally occurring and artificially produced radionuclides in the environment can be present in different physico-chemical forms (i. e. radionuclide species) varying in size (nominal molecular mass), charge properties and valence, oxidation state, structure and morphology, density, complexing ability etc. Low molecular mass (LMM) species are believed to be mobile and potentially bioavailable, while high molecular mass (HMM) species such as colloids, polymers, pseudocolloids and particles are considered inert. Due to time dependent transformation processes such as mobilization of radionuclide species from solid phases or interactions of mobile and reactive radionuclide species with components in soils and sediments, however, the original distribution of radionuclides deposited in ecosystems will change over time and influence the ecosystem behaviour. To assess the environmental impact from radionuclide contamination, information on radionuclide species deposited, interactions within affected ecosystems and the time-dependent distribution of radionuclide species influencing mobility and biological uptake is essential. The development of speciation techniques to characterize radionuclide species in waters, soils and sediments should therefore be essential for improving the prediction power of impact and risk assessment models. The present paper reviews fractionation techniques which should be utilised for radionuclide speciation purposes. (author)

  15. Interpretation of Series National Standards of China on “Greenhouse Gas Emissions Accounting and Reporting for Enterprises”

    Science.gov (United States)

    Chen, Liang; Zong, Jianfang; Guo, Huiting; Sun, Liang; Liu, Mei

    2018-05-01

    Standardization is playing an increasingly important role in reducing greenhouse gas emission and in climatic change adaptation, especially in the “three” greenhouse gas emission aspects (measurement, report, verification). Standardization has become one of the most important ways in mitigating the global climate change. Standardization Administration of China (SAC) has taken many productive measures in actively promoting standardization work to cope with climate change. In April 2014, SAC officially approved the establishment of “National Carbon Emission Management Standardization Technical Committee” In November 2015, SAC officially issued the first 11 national standards on carbon management including > and the requirements of the greenhouse gas emissions accounting and reporting in 10 sectors including power generation, power grid, iron and steel, chemical engineering, electrolytic aluminum, magnesium smelting, plate glass, cement, ceramics and civil aviation, which proposes unified requirements of “what to calculate and how to calculate” the greenhouse gas emission for enterprises. This paper focuses on the detailed interpretation of the main contents of the first 11 national standards, so as to provide technical supports for users of the standards and to comprehensively promote the emission reduction of greenhouse gas at the enterprise level.

  16. Advancing national greenhouse gas inventories for agriculture in developing countries: improving activity data, emission factors and software technology

    International Nuclear Information System (INIS)

    Ogle, Stephen M; Hartman, Melannie; Spencer, Shannon; Buendia, Leandro; Butterbach-Bahl, Klaus; Breidt, F Jay; Yagi, Kazuyuki; Nayamuth, Rasack; Wirth, Tom; Smith, Pete

    2013-01-01

    Developing countries face many challenges when constructing national inventories of greenhouse gas (GHG) emissions, such as lack of activity data, insufficient measurements for deriving country-specific emission factors, and a limited basis for assessing GHG mitigation options. Emissions from agricultural production are often significant sources in developing countries, particularly soil nitrous oxide, and livestock enteric and manure methane, in addition to wetland rice methane. Consequently, estimating GHG emissions from agriculture is an important part of constructing developing country inventories. While the challenges may seem insurmountable, there are ways forward such as: (a) efficiently using resources to compile activity data by combining censuses and surveys; (b) using a tiered approach to measure emissions at appropriately selected sites, coupled with modeling to derive country-specific emission factors; and (c) using advanced software systems to guide compilers through the inventory process. With a concerted effort by compilers and assistance through capacity-building efforts, developing country compilers could produce transparent, accurate, complete, consistent and comparable inventories, as recommended by the IPCC (Intergovernmental Panel on Climate Change). In turn, the resulting inventories would provide the foundation for robust GHG mitigation analyses and allow for the development of nationally appropriate mitigation actions and low emission development strategies. (letter)

  17. Denmark's national inventory report 2010. Emission inventories 1990-2008 - submitted under the United Nations framework convention on climate change and the Kyoto Protocol

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Ole-Kenneth; Lyck, E; Hjorth Mikkelsen, M [and others

    2010-05-15

    This report is Denmark's National Inventory Report 2010. The report contains information on Denmark's emission inventories for all years' from 1990 to 2008 for CO{sub 2}, CH{sub 4}, N{sub 2}O, HFCs, PFCs and SF{sub 6}, NO{sub x}, CO, NMVOC, SO{sub 2}. (Author)

  18. Denmark's national inventory report 2011. Emission inventories 1990-2009 - submitted under the United Nations framework convention on climate change and the Kyoto Protocol

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Ole-Kenneth; Hjorth Mikkelsen, M; Hoffmann, L [and others

    2011-05-15

    This report is Denmark's National Inventory Report 2011. The report contains information on Denmark's emission inventories for all years' from 1990 to 2009 for CO{sub 2}, CH{sub 4}, N{sub 2}O, HFCs, PFCs and SF{sub 6}, NO{sub x}, CO, NMVOC, SO{sub 2}. (Author)

  19. Denmark's national inventory report 2011. Emission inventories 1990-2009 - submitted under the United Nations framework convention on climate change and the Kyoto Protocol

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Ole-Kenneth; Hjorth Mikkelsen, M.; Hoffmann, L. (and others)

    2011-05-15

    This report is Denmark's National Inventory Report 2011. The report contains information on Denmark's emission inventories for all years' from 1990 to 2009 for CO{sub 2}, CH{sub 4}, N{sub 2}O, HFCs, PFCs and SF{sub 6}, NO{sub x}, CO, NMVOC, SO{sub 2}. (Author)

  20. Denmark's national inventory report 2010. Emission inventories 1990-2008 - submitted under the United Nations framework convention on climate change and the Kyoto Protocol

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Ole-Kenneth; Lyck, E.; Hjorth Mikkelsen, M. (and others)

    2010-05-15

    This report is Denmark's National Inventory Report 2010. The report contains information on Denmark's emission inventories for all years' from 1990 to 2008 for CO{sub 2}, CH{sub 4}, N{sub 2}O, HFCs, PFCs and SF{sub 6}, NO{sub x}, CO, NMVOC, SO{sub 2}. (Author)

  1. Denmark's national inventory report 2012. Emission inventories 1990-2010 - submitted under the United Nations Framework Convention on Climate Change and the Kyoto Protocol

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Ole-Kenneth; Hjorth Mikkelsen, M.; Hoffmann, L. (and others)

    2012-05-15

    This report is Denmark's National Inventory Report 2012. The report contains information on Denmark's emission inventories for all years' from 1990 to 2010 for CO{sub 2}, CH{sub 4}, N{sub 2}O, HFCs, PFCs and SF{sub 6}, NO{sub x}, CO, NMVOC, SO{sub 2}. (Author)

  2. Denmark's national inventory report 2009. Emission inventories 1990-2007 - submitted under the United Nations framework convention on climate change

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Ole-Kenneth; Lyck, E.; Hjorth Mikkelsen, M. (and others)

    2009-04-15

    This report is Denmark's National Inventory Report 2009. The report contains information on Denmark's emission inventories for all years' from 1990 to 2007 for CO{sub 2}, CH{sub 4}, N{sub 2}O, HFCs, PFCs and SF{sub 6}, NO{sub X}, CO, NMVOC, SO{sub 2}. (au)

  3. Denmark's national inventory report 2012. Emission inventories 1990-2010 - submitted under the United Nations Framework Convention on Climate Change and the Kyoto Protocol

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Ole-Kenneth; Hjorth Mikkelsen, M; Hoffmann, L [and others

    2012-05-15

    This report is Denmark's National Inventory Report 2012. The report contains information on Denmark's emission inventories for all years' from 1990 to 2010 for CO{sub 2}, CH{sub 4}, N{sub 2}O, HFCs, PFCs and SF{sub 6}, NO{sub x}, CO, NMVOC, SO{sub 2}. (Author)

  4. Denmark's national inventory report 2013. Emission inventories 1990-2011 - submitted under the United Nations Framework Convention on Climate Change and the Kyoto Protocol

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Ole-Kenneth; Plejdrup, M.S.; Winther, M. [and others

    2013-05-15

    This report is Denmark's National Inventory Report 2013. The report contains information on Denmark's emission inventories for all years' from 1990 to 2011 for CO{sub 2}, CH{sub 4}, N{sub 2}O, HFCs, PFCs and SF{sub 6}, NO{sub x}, CO, NMVOC, SO{sub 2}. (Author)

  5. {sup 134}Cs emission probabilities determination by gamma spectrometry

    Energy Technology Data Exchange (ETDEWEB)

    Almeida, M.C.M. de, E-mail: candida@cnen.gov.br [Comissão Nacional de Energia Nuclear (DINOR/CNEN), Riode Janeiro, RJ (Brazil); Poledna, R.; Delgado, J.U.; Silva, R.L.; Araujo, M.T.; Silva, C.J. da [Instituto de Radioproteção e Dosimetria (LNMRI/IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    The National Laboratory for Ionizing Radiation Metrology (LNMRI/IRD/CNEN) of Rio de Janeiro performed primary and secondary standardization of different radionuclides reaching satisfactory uncertainties. A solution of {sup 134}Cs radionuclide was purchased from commercial supplier to emission probabilities determination of some of its energies. {sup 134}Cs is a beta gamma emitter with 754 days of half-life. This radionuclide is used as standard in environmental, water and food control. It is also important to germanium detector calibration.The gamma emission probabilities (Pγ) were determined mainly for some energies of the {sup 134}Cs by efficiency curve method and the Pγ absolute uncertainties obtained were below 1% (k=1). (author)

  6. Quantitative radionuclide angiocardiography

    International Nuclear Information System (INIS)

    Scholz, P.M.; Rerych, S.K.; Moran, J.F.; Newman, G.E.; Douglas, J.M.; Sabiston, D.C. Jr.; Jones, R.H.

    1980-01-01

    This study introduces a new method for calculating actual left ventricular volumes and cardiac output from data recorded during a single transit of a radionuclide bolus through the heart, and describes in detail current radionuclide angiocardiography methodology. A group of 64 healthy adults with a wide age range were studied to define the normal range of hemodynamic parameters determined by the technique. Radionuclide angiocardiograms were performed in patients undergoing cardiac catherization to validate the measurements. In 33 patients studied by both techniques on the same day, a close correlation was documented for measurement of ejection fraction and end-diastolic volume. To validate the method of volumetric cardiac output calcuation, 33 simultaneous radionuclide and indocyanine green dye determinations of cardiac output were performed in 18 normal young adults. These independent comparisons of radionuclide measurements with two separate methods document that initial transit radionuclide angiocardiography accurately assesses left ventricular function

  7. Radionuclide brain scanning

    International Nuclear Information System (INIS)

    Abdel-Dayem, H.

    1992-01-01

    At one stage of medical imaging development, radionuclide brain scanning was the only technique available for imaging of the brain. Advent of CT and MRI pushed it to the background. It regained some of the grounds lost to ''allied advances'' with the introduction of brain perfusion radiopharmaceuticals. Positron emission tomography is a promising functional imaging modality that at present will remain as a research tool in special centres in developed countries. However, clinically useful developments will gradually percolate from PET to SPECT. The non-nuclear imaging methods are totally instrument dependent; they are somewhat like escalators, which can go that far and no further. Nuclear imaging has an unlimited scope for advance because of the new developments in radiopharmaceuticals. As the introduction of a radiopharmaceutical is less costly than buying new instruments, the recent advances in nuclear imaging are gradually perfusing through the developing countries also. Therefore, it is essential to follow very closely PET developments because what is research today might become routine tomorrow

  8. Radionuclide brain scanning

    Energy Technology Data Exchange (ETDEWEB)

    Abdel-Dayem, H

    1993-12-31

    At one stage of medical imaging development, radionuclide brain scanning was the only technique available for imaging of the brain. Advent of CT and MRI pushed it to the background. It regained some of the grounds lost to ``allied advances`` with the introduction of brain perfusion radiopharmaceuticals. Positron emission tomography is a promising functional imaging modality that at present will remain as a research tool in special centres in developed countries. However, clinically useful developments will gradually percolate from PET to SPECT. The non-nuclear imaging methods are totally instrument dependent; they are somewhat like escalators, which can go that far and no further. Nuclear imaging has an unlimited scope for advance because of the new developments in radiopharmaceuticals. As the introduction of a radiopharmaceutical is less costly than buying new instruments, the recent advances in nuclear imaging are gradually perfusing through the developing countries also. Therefore, it is essential to follow very closely PET developments because what is research today might become routine tomorrow

  9. National trajectories of carbon emissions: analysis of proposals to foster the transition to low-carbon economies

    International Nuclear Information System (INIS)

    Kinzig, A.P.; Kammen, D.M.

    1998-01-01

    In this paper we develop a framework for analyzing carbon dioxide (CO 2 ) emissions trajectories from the energy and industrial sectors of the world's nations under various policy options. A robust conclusion of our analysis is that early action by both developed and developing nations will be required to hold atmospheric CO 2 at or below doubled pre-industrial levels and incentives for renewed investments in energy-sector technologies are a required component of early action. We therefore develop and examine an international emissions regime that: (a) in the short-term 'jump starts' the political and project-implementation process by providing incentives to exploit profitable or low-cost carbon reduction opportunities; (b) in the near- and medium-term addresses the inequities resulting from historic imbalances in greenhouse-gas emissions while promoting efficient pathways for carbon reduction; and (c) in the long-term recognizes the equal rights of individuals to exploit the services of the atmosphere and pursue a reasonable standard of living in a low-carbon economy. We present and analyze a proposal to promote near-term activity in carbon reduction and energy innovation through a revitalized program of international joint implementation (JI) projects for carbon emissions reduction or carbon sequestration projects. Under our proposal, JI partner nations both receive full credit for carbon reductions that can be 'banked' and applied at a later date toward national emissions quotas in the climate convention. A finite program lifetime provides further impetus counting' of credits results in only modest additional cumulative carbon emissions relative to a similar scenario without cooperative partnerships. This 'JI banking' plan promotes critically needed scientific and institutional experience and innovation, initiates cost-effective carbon reductions, and provides vital national flexibility in meeting eventual targets. (author)

  10. The ENSDF based radionuclide source for MCNP

    International Nuclear Information System (INIS)

    Berlizov, A.N.; Tryshyn, V.V.

    2003-01-01

    A utility for generating source code of the Source subroutine of MCNP (a general Monte Carlo NxParticle transport code) on the basis of ENSDF (Evaluated Nuclear Structure Data File) is described. The generated code performs statistical simulation of processes, accompanying radioactive decay of a chosen radionuclide through a specified decay branch, providing characteristics of emitted correlated particles on its output. At modeling the following processes are taken into account: emission of continuum energy electrons at beta - -decay to different exited levels of a daughter nucleus; annihilation photon emission accompanying beta + -decay; gamma-ray emission; emission of discrete energy electrons resulted from internal conversion process on atomic K- and L I,II,III -shells; K and LX-ray emission at single and double fluorescence, accompanying electron capture and internal conversion processes. Number of emitted particles, their types, energies and emission times are sampled according to characteristics of a decay scheme of a particular radionuclide as well as characteristics of atomic shells of mother and daughter nuclei. Angular correlations, calculated for a particular combination of nuclear level spins, mixing ratios and gamma-ray multipolarities, are taken into account at sampling of directional cosines of emitted gamma-rays. The paper contains examples of spectrometry system response simulation at measurements with real radionuclide sources. (authors)

  11. National Emission Standards for Hazardous Air Pollutants Calendar Year 2001; TOPICAL

    International Nuclear Information System (INIS)

    Y. E. Townsend

    2002-01-01

    The Nevada Test Site (NTS) is operated by the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Operations Office (NNSA/NV) as the site for nuclear weapons testing, now limited to readiness activities, experiments in support of the national Stockpile Stewardship Program, and the activities listed below. Located in Nye County, Nevada, the site's southeast corner is about 88 km (55 mi) northwest of the major population center, Las Vegas, Nevada. The NTS covers about 3,561 km2 (1,375 mi2), an area larger than Rhode Island. Its size is 46 to 56 km (28 to 35 mi) east to west and from 64 to 88 km (40 to 55 mi) north to south. The NTS is surrounded, except on the south side, by public exclusion areas (Nellis Air Force Range[NAFR]) that provide another 24 to 104 km (15 to 65 mi) between the NTS and public lands (Figure 1.0). The NTS is characterized by desert valley and Great Basin mountain topography, with a climate, flora, and fauna typical of the southwest deserts. Population density within 150 km (93 mi) of the NTS is only about 0.2 persons per square kilometer, excluding the Las Vegas area. Restricted access, low population density in the surrounding area, and extended wind transport times are advantageous factors for the activities conducted at the NTS. Surface waters are scarce on the NTS, and slow-moving groundwater is present hundreds to thousands of feet below the land surface. The sources of radionuclides include current and previous activities conducted on the NTS (Figure 2.0). The NTS was the primary location for testing of nuclear explosives in the Continental U.S. between 1951 and 1992. Historical testing above or at ground surface has included (1) atmospheric testing in the 1950s and early 1960s, (2) earth-cratering experiments, and (3) open-air nuclear reactor and rocket engine testing. Since the mid-1950s, testing of nuclear explosive devices has occurred underground in drilled vertical holes or in mined tunnels (DOE 1996a

  12. RADIOLOGICAL EMISSIONS AND ENVIRONMENTAL MONITORING FOR BROOKHAV EN NATIONAL LABORATORY, 1947 - 1961.

    Energy Technology Data Exchange (ETDEWEB)

    MEINHOLD,C.B.; MEINHOLD,A.F.(EDITED BY BOND,P.D.)

    2001-05-30

    Brookhaven National Laboratory (BNL) has monitored its releases to the environment since its inception in 1947. From 1962 to 1966 and from 1971 to the present, annual reports,were published that recorded the emissions and releases to the environment from Laboratory operations. In 1998, a report was written to summarize the environmental data for the years 1967 to 1970. One of the purposes of the current report is to complete BNL's environmental history by covering the period from 1948 through 1961. The activities in 1947 were primarily organizational and there is no information on the use of radiation at the Laboratory before 1948. An additional objective of this report is to provide environmental data to the Agency for Toxic Substances and Disease Registry (ATSDR). The report does not provide an estimate of the doses associated with BNL operations. The report is comprised of two parts. The first part is a summary of emissions, releases, and environmental monitoring information including a discussion of the uncertainties in these data. Part two contains the detailed information on the approach taken to estimate the releases from the fuel cartridge failures at the Brookhaven Graphite Research Reactor (BGRR). A series of appendices present more detailed information on these events in tabular form. The approach in this report is to be reasonable, conservative, (pessimistic), and transparent in estimating releases from fuel cartridge ruptures. Clearly, reactor stack monitoring records and more extensive records would have greatly improved this effort, but in accordance with Atomic Energy Commission (AEC) Appendix 0230 Annex C-9, many of the detailed records from this time were not retained.

  13. Radioecology, emissions and immissions

    International Nuclear Information System (INIS)

    Tschurlovits, M.

    1988-01-01

    7 contributions are presented on radionuclide emissions from particular nuclear installations, on radionuclide migration and measurements in the environment, on the equipment of a particular laboratory and on setting limiting values. All of them are in INIS scope and are treated separately. (qui)

  14. Marine biogeochemistry of radionuclides

    International Nuclear Information System (INIS)

    Fowler, S.W.

    1997-01-01

    Radionuclides entering the ocean from runoff, fallout, or deliberate release rapidly become involved in marine biogeochemical cycles. Sources, sinks and transport of radionuclides and analogue elements are discussed with emphasis placed on how these elements interact with marine organisms. Water, food and sediments are the source terms from which marine biota acquire radionuclides. Uptake from water occurs by surface adsorption, absorption across body surfaces, or a combination of both. Radionuclides ingested with food are either assimilated into tissue or excreted. The relative importance of the food and water pathway in uptake varies with the radionuclide and the conditions under which exposure occurs. Evidence suggests that, compared to the water and food pathways, bioavailability of sediment-bound radionuclides is low. Bioaccumulation processes are controlled by many environmental and intrinsic factors including exposure time, physical-chemical form of the radionuclide, salinity, temperature, competitive effects with other elements, organism size, physiology, life cycle and feeding habits. Once accumulated, radionuclides are transported actively by vertical and horizontal movements of organisms and passively by release of biogenic products, e.g., soluble excreta, feces, molts and eggs. Through feeding activities, particles containing radionuclides are ''packaged'' into larger aggregates which are redistributed upon release. Most radionuclides are not irreversibly bound to such particles but are remineralized as they sink and/or decompose. In the pelagic zones, sinking aggregates can further scavenge particle-reactive elements thus removing them from the surface layers and transporting them to depth. Evidence from both radiotracer experiments and in situ sediment trap studies is presented which illustrates the importance of biological scavenging in controlling the distribution of radionuclides in the water column. (author)

  15. Emission probability determination of {sup 133}Ba by the sum-peak method

    Energy Technology Data Exchange (ETDEWEB)

    Silva, R.L. da; Almeida, M.C.M. de; Delgado, J.U.; Poledna, R.; Araujo, M.T.F.; Trindade, O.L.; Veras, E.V. de; Santos, A.; Rangel, J.; Ferreira Filho, A.L., E-mail: ronaldo@ird.gov.br, E-mail: marcandida@yahoo.com.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2016-07-01

    The National Laboratory of Metrology Ionizing Radiation (LNMRI/IRD/CNEN) has several measurement methods in order to ensure low uncertainties about the results. Through gamma spectrometry analysis by sum-peak absolute method they were performed the standardization of {sup 133}Ba activity and your emission probability determination of different energies with reduced uncertainties. The advantages of radionuclides calibrations by absolute method are accuracy, low uncertainties and is not necessary the use of radionuclides reference standards. {sup 133}Ba is used in research laboratories on calibration detectors in different work areas. The uncertainties for the activity and for the emission probability results are lower than 1%. (author)

  16. Comparison of models used for national agricultural ammonia emission inventories in Europe: Litter-based manure systems

    NARCIS (Netherlands)

    Reidy, B.; Webb, J.; Misselbrook, T.H.; Menzi, H.; Luesink, H.H.; Hutchings, N.J.; Eurich-Menden, B.; Dohler, H.; Dammgen, U.

    2009-01-01

    Six N-flow models, used to calculate national ammonia (NH3) emissions from agriculture in different European countries, were compared using standard data sets. Scenarios for litter-based systems were run separately for beef cattle and for broilers, with three different levels of model

  17. 76 FR 52737 - Oil and Natural Gas Sector: New Source Performance Standards and National Emission Standards for...

    Science.gov (United States)

    2011-08-23

    ... quality impacts? D. What are the water quality and solid waste impacts? E. What are the secondary impacts... Significantly Affect Energy Supply, Distribution, or Use I. National Technology Transfer and Advancement Act J... Achievable Emission Rate lb Pounds LDAR Leak Detection and Repair MACT Maximum Achievable Control Technology...

  18. What causes the differences between national estimates of carbon emissions from forest management and large-scale models?

    NARCIS (Netherlands)

    Groen, T.A.; Verkerk, P.J.; Böttcher, H.; Grassi, G.; Cienciala, E.; Black, K.G.; Fortin, M.J.; Koethke, M.; Lethonen, A.; Nabuurs, G.J.; Petrova, L.; Blujdea, V.

    2013-01-01

    Under the United Nations Framework Convention for Climate Change all Parties have to report on carbon emissions and removals from the forestry sector. Each Party can use its own approach and country specific data for this. Independently, large-scale models exist (e.g. EFISCEN and G4M as used in this

  19. What causes differences between national estimates of forest management carbon emissions and removals compared to estimates of large - scale models?

    NARCIS (Netherlands)

    Groen, T.A.; Verkerk, P.J.; Böttcher, H.; Grassi, G.; Cienciala, E.; Black, K.G.; Fortin, M.; Köthke, M.; Lehtonen, A.; Nabuurs, G.J; Petrova, L.; Blujdea, V.

    2013-01-01

    Under the United Nations Framework Convention for Climate Change all Parties have to report on carbon emissions and removals from the forestry sector. Each Party can use its own approach and country specific data for this. Independently, large-scale models exist (e.g. EFISCEN and G4M as used in this

  20. Development of a transportable system for radionuclide analysis

    International Nuclear Information System (INIS)

    Cunningham, W.C.; Anderson, D.L.; Lamont, W.H.; South, P.K.; Rury, M.A.; Beachley, G.M.; Ondov, J.M.

    2008-01-01

    Transportable radioanalytical systems were assembled and tested for quantitative determination of γ-emitting radionuclides and screening of β- emitting radionuclides. Standard operating procedures (SOPs), including instructions for assembly, disassembly, operation, sample collection and analysis, and all other procedures needed, were developed. Foods, as well as National Institute of Standards and Technology, International Atomic Energy Agency, and in-house Reference Materials were analyzed. An SOP for γ-emitting radionuclides was successfully tested at 3 locations. (author)

  1. Positron emitting radionuclides for South Africa

    International Nuclear Information System (INIS)

    Wynchbank, S.; Van der Walt, T.N.; Sharpey-Shafer, J.

    2004-01-01

    Full text: In South Africa there are currently two projects underway to supply and utilise positron emitting radionuclides for imaging in clinical nuclear medicine facilities. The advantages and applications of such radio nuclides are numerous and well known. However the premier initial application will be to employ 1BF, at first in the compound fluorine-18 fluorodeoxyglucose ( 18 F)-FDG, for patients with cancers and neoplasms. The two projects are sited at iThemba LABS, where production of a generator supplying 66 Ga and the provision of ( 18 F]-FDG, are in an advanced state of planning; the former already fully financed by the Innovation Fund of the National Research Foundation. The two positron emitting radionuclides, 18 F and 68 Ge, will be produced using a cyclotron induced reaction on 1802 and Ga, respectively, at iThemba LABS. The 68 Ge/ 68 Ga generator consists of an anion exchanger loaded with 68 Ge, which decays to 68 Ga. The resulting radiopharmaceuticals, ( 18 F]-FDG and 68 Ga citrate, will be produced by the Radionuclide Production Group of iThemba LABS, using well described methods. However the structures and processes to be used in the generator to provide 68 Ga are novel and will be explained. Initially provision of the CBF]-FDG will be to selected clinical medicine facilities in the Western Cape and Gauteng. It should be noted that the logistical problems of providing this radiopharmaceutical (which are much complicated by its short half life of 109.7 min) to Gauteng, were shown to be surmountable in the 1970s, by a regular delivery of 18 F between Gauteng and Cape Town, after the advent of a commercial service using jet aircraft. The obvious requirement that there should be appropriate nuclear medicine facilities to image patients, at the sites to which the positron emitting radiopharmaceuticals will be supplied, has been addressed. Proposed solutions will be outlined, in terms of a dedicated positron emission tomography (PET) camera and a gamma

  2. Radionuclides in terrestrial ecosystems

    International Nuclear Information System (INIS)

    Bocock, K.L.

    1981-01-01

    This report summarizes information on the distribution and movement of radionuclides in semi-natural terrestrial ecosystems in north-west England with particular emphasis on inputs to, and outputs from ecosystems; on plant and soil aspects; and on radionuclides in fallout and in discharges by the nuclear industry. (author)

  3. Water, soil, crops and radionuclides. Studies on the behavior of radionuclides in the terrestrial environments

    International Nuclear Information System (INIS)

    Uchida, Shigeo

    2008-01-01

    In order to predict the migration of artificially-produced radionuclides into a human body and its radiation dose rates of human body and to decrease the exposed radiation doses of human body, the behavior of radionuclides in the environment must be elucidated. In National Institute of Radiological Sciences (NIRS), the environmental radioecological research group of Nakaminato Laboratory for Marine Radioecology has progressed the survey and research on the behavior of artificially-produced radionuclides in the terrestrial environment. This article describes the research results (the radioactivity of water, soil, and crops) made so far at Nakaminato Laboratory for Marine Radioecology. (M.H.)

  4. Producing remote sensing-based emission estimates of prescribed burning in the contiguous United States for the U.S. Environmental Protection Agency 2011 National Emissions Inventory

    Science.gov (United States)

    McCarty, J. L.; Pouliot, G. A.; Soja, A. J.; Miller, M. E.; Rao, T.

    2013-12-01

    Prescribed fires in agricultural landscapes generally produce smaller burned areas than wildland fires but are important contributors to emissions impacting air quality and human health. Currently, there are a variety of available satellite-based estimates of crop residue burning, including the NOAA/NESDIS Hazard Mapping System (HMS) the Satellite Mapping Automated Reanalysis Tool for Fire Incident Reconciliation (SMARTFIRE 2), the Moderate Resolution Imaging Spectroradiometer (MODIS) Official Burned Area Product (MCD45A1)), the MODIS Direct Broadcast Burned Area Product (MCD64A1) the MODIS Active Fire Product (MCD14ML), and a regionally-tuned 8-day cropland differenced Normalized Burn Ratio product for the contiguous U.S. The purpose of this NASA-funded research was to refine the regionally-tuned product utilizing higher spatial resolution crop type data from the USDA NASS Cropland Data Layer and burned area training data from field work and high resolution commercial satellite data to improve the U.S. Environmental Protection Agency's (EPA) National Emissions Inventory (NEI). The final product delivered to the EPA included a detailed database of 25 different atmospheric emissions at the county level, emission distributions by crop type and seasonality, and GIS data. The resulting emission databases were shared with the U.S. EPA and regional offices, the National Wildfire Coordinating Group (NWGC) Smoke Committee, and all 48 states in the contiguous U.S., with detailed error estimations for Wyoming and Indiana and detailed analyses of results for Florida, Minnesota, North Dakota, Oklahoma, and Oregon. This work also provided opportunities in discovering the different needs of federal and state partners, including the various geospatial abilities and platforms across the many users and how to incorporate expert air quality, policy, and land management knowledge into quantitative earth observation-based estimations of prescribed fire emissions. Finally, this work

  5. A Delphi study to establish national cost-effectiveness research priorities for positron emission tomography

    International Nuclear Information System (INIS)

    Robert, Glenn; Milne, Ruairidh

    1999-01-01

    Objective: This study aimed to determine the key cost-effectiveness research questions relating to positron emission tomography (PET) in the UK. Methods: A systematic literature review was conducted to establish the existing knowledge base relating to the cost-effectiveness of PET in the various conditions for which it has been proposed. A three-round postal Delphi study of relevant individuals was used to determine the key cost-effectiveness research questions relating to PET in the UK. The content and structure of the Delphi study was informed by the results of the literature review. Results: The most important cost-effectiveness research priorities for the National Health Service (NHS) relating to PET were in the clinical areas of lung cancer, breast cancer and the assessment of myocardial viability. Gamma camera PET using coincidence imaging was highlighted as a modality whose clinical role needed to be determined urgently. Conclusion: Underlying the cost-effectiveness research priorities which were established is the need for evidence that the use of the various PET modalities as a diagnostic technique will alter patient management as compared to existing diagnostic strategies. The findings of the project provide a contemporary overview of the potential role for PET in the NHS and will be relevant to other countries

  6. Positron emission tomography

    International Nuclear Information System (INIS)

    Iio, Masahiro

    1982-01-01

    Utilization of positron emission tomography was reviewed in relation to construction and planned construction of small-size medical cyclotrons, planned construction of positron cameras and utilization of short-lived radionuclides. (Chiba, N.)

  7. Quantitative estimation of infarct size by simultaneous dual radionuclide single photon emission computed tomography: comparison with peak serum creatine kinase activity

    International Nuclear Information System (INIS)

    Kawaguchi, K.; Sone, T.; Tsuboi, H.; Sassa, H.; Okumura, K.; Hashimoto, H.; Ito, T.; Satake, T.

    1991-01-01

    To test the hypothesis that simultaneous dual energy single photon emission computed tomography (SPECT) with technetium-99m (99mTc) pyrophosphate and thallium-201 (201TI) can provide an accurate estimate of the size of myocardial infarction and to assess the correlation between infarct size and peak serum creatine kinase activity, 165 patients with acute myocardial infarction underwent SPECT 3.2 +/- 1.3 (SD) days after the onset of acute myocardial infarction. In the present study, the difference in the intensity of 99mTc-pyrophosphate accumulation was assumed to be attributable to difference in the volume of infarcted myocardium, and the infarct volume was corrected by the ratio of the myocardial activity to the osseous activity to quantify the intensity of 99mTc-pyrophosphate accumulation. The correlation of measured infarct volume with peak serum creatine kinase activity was significant (r = 0.60, p less than 0.01). There was also a significant linear correlation between the corrected infarct volume and peak serum creatine kinase activity (r = 0.71, p less than 0.01). Subgroup analysis showed a high correlation between corrected volume and peak creatine kinase activity in patients with anterior infarctions (r = 0.75, p less than 0.01) but a poor correlation in patients with inferior or posterior infarctions (r = 0.50, p less than 0.01). In both the early reperfusion and the no reperfusion groups, a good correlation was found between corrected infarct volume and peak serum creatine kinase activity (r = 0.76 and r = 0.76, respectively; p less than 0.01)

  8. Emission computed tomography

    International Nuclear Information System (INIS)

    Ott, R.J.

    1986-01-01

    Emission Computed Tomography is a technique used for producing single or multiple cross-sectional images of the distribution of radionuclide labelled agents in vivo. The techniques of Single Photon Emission Computed Tomography (SPECT) and Positron Emission Tomography (PET) are described with particular regard to the function of the detectors used to produce images and the computer techniques used to build up images. (UK)

  9. Dose Assessment of Los Alamos National Laboratory-Derived Residual Radionuclides in Soils within C Tracts (C-2, C-3, and C-4) for Land Transfer Decisions

    Energy Technology Data Exchange (ETDEWEB)

    Gillis, Jessica M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Whicker, Jeffrey J.

    2016-01-26

    Three separate Sampling and Analysis Plans (SAPs) were prepared for tracts C-2, C-3, and C-4. The objective of sampling was to confirm, within the stated statistical confidence limits, that the mean levels of potential radioactive residual contamination in soils in the C Tracts are documented, in appropriate units, and are below the 15 mrem/y (150 μSv/y) Screening Action Levels (SALs). Results show that radionuclide concentration upper-bound 95% confidence levels were close to background levels, with the exception of Pu-239 and Cs-137 being slightly elevated above background, and all measurements were below the ALs and meet the real property release criteria for future construction or recreational use. A follow-up ALARA analysis showed that the costs of cleanup of the soil in areas of elevated concentration and confirmatory sampling would far exceed any benefit from dose reduction.

  10. Comparison of models used for national agricultural ammonia emission inventories in Europe: Litter-based manure systems

    Science.gov (United States)

    Reidy, B.; Webb, J.; Misselbrook, T. H.; Menzi, H.; Luesink, H. H.; Hutchings, N. J.; Eurich-Menden, B.; Döhler, H.; Dämmgen, U.

    Six N-flow models, used to calculate national ammonia (NH 3) emissions from agriculture in different European countries, were compared using standard data sets. Scenarios for litter-based systems were run separately for beef cattle and for broilers, with three different levels of model standardisation: (a) standardized inputs to all models (FF scenario); (b) standard N excretion, but national values for emission factors (EFs) (FN scenario); (c) national values for N excretion and EFs (NN scenario). Results of the FF scenario for beef cattle produced very similar estimates of total losses of total ammoniacal-N (TAN) (±6% of the mean total), but large differences in NH 3 emissions (±24% of the mean). These differences arose from the different approaches to TAN immobilization in litter, other N losses and mineralization in the models. As a result of those differences estimates of TAN available at spreading differed by a factor of almost 3. Results of the FF scenario for broilers produced a range of estimates of total changes in TAN (±9% of the mean total), and larger differences in the estimate of NH 3 emissions (±17% of the mean). The different approaches among the models to TAN immobilization, other N losses and mineralization, produced estimates of TAN available at spreading which differed by a factor of almost 1.7. The differences in estimates of NH 3 emissions decreased as estimates of immobilization and other N losses increased. Since immobilization and denitrification depend also on the C:N ratio in manure, there would be advantages to include C flows in mass-flow models. This would also provide an integrated model for the estimation of emissions of methane, non-methane VOCs and carbon dioxide. Estimation of these would also enable an estimate of mass loss, calculation of the N and TAN concentrations in litter-based manures and further validation of model outputs.

  11. Greenhouse Gas Emission Intensities for the Livestock Sector in Indonesia, Based on the National Specific Data

    Directory of Open Access Journals (Sweden)

    Eska Nugrahaeningtyas

    2018-06-01

    Full Text Available The aims of this study were to calculate greenhouse gas (GHG emissions and to identify the trends of GHG emission intensity, based on meat production from the livestock sector in Indonesia, which had not been done before. The total emissions from the livestock sector from 2000 to 2015 in Indonesia were calculated using the 2006 Intergovernmental Panel on Climate Change Guideline (2006 IPCC GL using Tier 1 and Tier 2, with its default values and some of the country specific data that were found in the grey literature. During 2000 to 2015, the change from the Tier 1 to Tier 2 methods resulted in an approximately 7.39% emission decrease from enteric fermentation and a 4.24% increase from manure management, which resulted in a 4.98% decrease in the total emissions. The shared emission from manure management increased by about 9% and 6% using Tier 1 and Tier 2, respectively. In contrast with the total emissions, the overall emission intensity in Indonesia decreased (up to 60.77% for swine, showing that the livestock productivity in Indonesia has become more efficient. In order to meet the meat demand with less GHG emissions, chicken farming is one option to be developed. The increased emission and share from manure management indicated that manure management system needs to be of concern, especially for beef cattle and swine.

  12. Radionuclide therapy practice and facilities in Europe

    International Nuclear Information System (INIS)

    Hoefnagel, C.A.; Clarke, S.E.M.; Fischer, M.; Chatal, J.F.; Lewington, V.J.; Nilsson, S.; Troncone, L.; Vieira, M.R.

    1999-01-01

    Using a questionnaire the EANM Task Group Radionuclide Therapy in 1993 collected data on the current practice of radionuclide therapy in European countries. Subsequently, at the request of the EANM Executive Committee, the EANM Radionuclide Therapy Committee has made an inventory of the distribution of facilities for radionuclide therapy and undertaken an assessment of the total number of patients treated throughout Europe and of the types of treatment provides, with the aim of supporting the development of policy to adjust the available capacity to the needs by the year 2000. For this purpose, a second, more detailed questionnaire was sent out the members and national advisors of the Committee (see below), who gathered the data for each country that was a member of the EANM at the time. It is concluded that a wide bariation in therapy practice exists across Europe, particularly in the utilisation of radionuclide therapy, the requirement and availability of proper isolation facilities and the background training of those undertaking therapy. More uniform guidelines and legislation are required, although changes in legislation may have a significant impact in some countries. Although there is wide variation in the therapies used in each country, one the whole it appears that there is an underutilisation of nuclear medicine as a therapeutic modality. A rapidly increasing role may be expected, in particular for oncological indications requiring high-dose radionuclide treatment. Therefore there is an urgent need for a greater number of isolation beds in dedicated centers throughout Europe

  13. Process for encapsulating radionuclides

    International Nuclear Information System (INIS)

    Brownell, L.E.; Isaacson, R.E.

    1976-01-01

    Radionuclides are immobilized in virtually an insoluble form by reacting at a temperature of at least 90 0 C as an aqueous alkaline mixture having a solution pH of at least 10, containing a source of silicon, the radionuclide waste, and a metal cation. The molar ratio of silicon to the metal cation is on the order of unity to produce a gel from which complex metalosilicates crystallize to entrap the radionuclides within the resultant condensed crystal lattice. The product is a silicious stone-like material which is virtually insoluble and nonleachable in alkaline or neutral environment. One embodiment provides for the formation of the complex metalo-silicates, such as synthetic pollucite, by gel formation with subsequent calcination to the solid product; another embodiment utilizes a hydrothermal process, either above ground or deep within basalt caverns, at greater than atmospheric pressures and a temperature between 90 and 500 0 C to form complex metalo-silicates, such as strontium aluminosilicate. Another embodiment provides for the formation of complex metalo-silicates, such as synthetic pollucite, by slurrying an alkaline mixture of bentonite or kaolinite with a source of silicon and the radionuclide waste in salt form. In each of the embodiments a mobile system is achieved whereby the metalo-silicate constituents reorient into a condensed crystal lattice forming a cage structure with the condensed metalo-silicate lattice which completely surrounds the radionuclide and traps the radionuclide therein; thus rendering the radionuclide virtually insoluble

  14. Foodstuffs, radionuclides, monitoring

    International Nuclear Information System (INIS)

    Denisikov, A.I.

    2000-01-01

    Radionuclide contamination of water and food stuffs as a result of the Chernobyl accident and permissible contents of 90 Sr and 137 Cs are considered in brief. A method of radiation monitoring of food stuffs and water for the radionuclides mentioned is suggested. The method permits employment of the simplest and cheapest radiometric equipment for analysis, whole the high degree of radionuclide concentration using fiber sorbents permits using the instrumentation without expensive shields against external radiation. A description of ion-exchange unit for radiation monitoring of liquid samples of food stuffs or water, is provided [ru

  15. Generator for radionuclide

    International Nuclear Information System (INIS)

    Weisner, P.S.; Forrest, T.R.F.

    1985-01-01

    This invention provides a radionuclide generator of the kind in which a parent radionuclide, adsorbed on a column of particulate material, generates a daughter radionuclide which is periodically removed from the column. This invention is particularly concerned with technetium generators using single collection vials. The generator comprises a column, a first reservoir for the eluent, a second reservoir to contain the volume of eluent required for a single elution, and means connecting the first reservoir to the second reservoir and the second reservoir to the column. Such a generator is particularly suitable for operation by vacuum elution

  16. Industrial Process Cooling Towers: National Emission Standards for Hazardous Air Pollutants

    Science.gov (United States)

    Standards limiting discharge of chromium compound air emissions from industrial process cooling towers (IPCT's). Includes rule history, Federal Registry citations, implementation information and additional resources.

  17. Innovative methodology for intercomparison of radionuclide calibrators using short half-life in situ prepared radioactive sources

    International Nuclear Information System (INIS)

    Oliveira, P. A.; Santos, J. A. M.

    2014-01-01

    Purpose: An original radionuclide calibrator method for activity determination is presented. The method could be used for intercomparison surveys for short half-life radioactive sources used in Nuclear Medicine, such as 99m Tc or most positron emission tomography radiopharmaceuticals. Methods: By evaluation of the resulting net optical density (netOD) using a standardized scanning method of irradiated Gafchromic XRQA2 film, a comparison of the netOD measurement with a previously determined calibration curve can be made and the difference between the tested radionuclide calibrator and a radionuclide calibrator used as reference device can be calculated. To estimate the total expected measurement uncertainties, a careful analysis of the methodology, for the case of 99m Tc, was performed: reproducibility determination, scanning conditions, and possible fadeout effects. Since every factor of the activity measurement procedure can influence the final result, the method also evaluates correct syringe positioning inside the radionuclide calibrator. Results: As an alternative to using a calibrated source sent to the surveyed site, which requires a relatively long half-life of the nuclide, or sending a portable calibrated radionuclide calibrator, the proposed method uses a source preparedin situ. An indirect activity determination is achieved by the irradiation of a radiochromic film using 99m Tc under strictly controlled conditions, and cumulated activity calculation from the initial activity and total irradiation time. The irradiated Gafchromic film and the irradiator, without the source, can then be sent to a National Metrology Institute for evaluation of the results. Conclusions: The methodology described in this paper showed to have a good potential for accurate (3%) radionuclide calibrators intercomparison studies for 99m Tc between Nuclear Medicine centers without source transfer and can easily be adapted to other short half-life radionuclides

  18. Effects of the updated national emission regulation in China on circulating fluidized bed boilers and the solutions to meet them.

    Science.gov (United States)

    Li, Jingji; Yang, Hairui; Wu, Yuxin; Lv, Junfu; Yue, Guangxi

    2013-06-18

    The advantage of circulating fluidized bed (CFB) boilers in China is their ability to utilize low rank coal with low cost emission control. However, the new National Emission Regulation (NER) issued in early 2012 brings much more stringent challenges on the CFB industries, which also causes much attention from other countries. Based on the principle of a CFB boiler and previous operating experience, it is possible for the CFB boilers to meet the new NER and maintain the advantage of low cost emission control, while, more influences should be considered in their design and operation. To meet the requirement of the new NER, the fly ash collector should adopt a bag house or combination of electrostatic precipitator and bag filter to ensure dust emissions of less than 30 mg · Nm(-3). For SO2 emission control, the bed temperature should be strictly lower than 900 °C to maintain high reactivity and pores. The limestone particle size distribution should be ranged within a special scope to optimize the residence time and gas-solid reaction. At the same time, the injecting point should be optimized to ensure fast contact of lime with oxygen. In such conditions, the desulfurization efficiency could be increased more than 90%. For lower sulfur content fuels (emissions lower than that of the new NER, 100 mg · Nm(-3). For fuels with sulfur content higher than 1.5%, some simplified systems for flue gas desulfurization, such as flash dryer absorber (FDA), are needed. And the NOx emissions of a CFB can be controlled to less than 100 mg · Nm(-3) without any equipment at a bed temperature lower than 900 °C for fuels with low volatiles content (emission of CFB is very low for the new NER due to its innate property.

  19. Denmark's national inventory report 2006 - Submitted under the United Nations framework convention on climate change, 1990-2004. Emission inventories

    International Nuclear Information System (INIS)

    Illerup, J.B.; Lyck, E.; Nielsen, Ole-Kenneth

    2006-08-01

    This report is Denmark's National Inventory Report reported to the Conference of the Parties under the United Nations Framework Convention on Climate Change (UNFCCC) due by 15 April 2006. The report contains information on Denmark's inventories for all years' from 1990 to 2004 for CO 2 , CH 4 , N 2 O, HFCs, PFCs and SF 6 , CO, NMVOC, SO 2 . (au)

  20. Denmark's national inventory report. Submitted under the United Nations framework convention on climate change, 1990-2001. Emission inventories

    International Nuclear Information System (INIS)

    Illerup, J.B.; Lyck, E.; Nielsen, M.; Winther, M.; Hjort Mikkelsen, M.

    2003-01-01

    This report is Denmark's National Inventory Report reported to the Conference of the Parties under the United Nations Framework Convention on Climate Change (UNFCCC) due bye 15 April 2003. The report contains information on Denmark's inventories for all years' from 1990 to 2001 for CO 2 , CH 4 , N 2 O, CO, NMVOC, SO 2 , HFCs, PFCs and SF 6 . (au)

  1. Dosimetry of incorporated transuranic radionuclides

    International Nuclear Information System (INIS)

    Loessner, V.

    1983-01-01

    Modern in vivo and in vitro techniques for detecting transuranic radionuclides within the human body are described with special emphasis on multiparameter measuring methods developed at the National Board of Nuclear Safety and Radiation Protection. Furthermore, problems related to calibration and interpretation of measuring data are discussed and new methods presented for the calculation of committed dose equivalents on the basis of data from ICRP Publication 30. Also included is an introductory chapter on radiobiological fundamentals of intake, translocation and metabolism of these nuclides. (author)

  2. Dietary intake of natural radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Smith-Briggs, J L; Bradley, E J [National Radiological Protection Board, Chilton (UK)

    1984-09-01

    The levels of the natural radionuclides, radium-226, lead-210 and polonium-210 were measured in food samples collected for a National Food Survey, thus reflecting current consumption patterns in the UK. Daily intakes of radium-226, lead-210 and inferred values of polonium-210 were calculated for 20 food groups. From these data, the annual effective dose equivalents from radium-226, lead-210 and polonium-210 in the UK diet were estimated to be 3..mu..Sv, 41..mu..Sv and 13..mu..Sv respectively.

  3. Dietary intake of natural radionuclides

    International Nuclear Information System (INIS)

    Smith-Briggs, J.L.; Bradley, E.J.

    1984-01-01

    The levels of the natural radionuclides, radium-226, lead-210 and polonium-210 were measured in food samples collected for a National Food Survey, thus reflecting current consumption patterns in the UK. Daily intakes of radium-226, lead-210 and inferred values of polonium-210 were calculated for 20 food groups. From these data, the annual effective dose equivalents from radium-226, lead-210 and polonium-210 in the UK diet were estimated to be 3μSv, 41μSv and 13μSv respectively. (U.K.)

  4. Antifouling biocides in German marinas: Exposure assessment and calculation of national consumption and emission.

    Science.gov (United States)

    Daehne, Dagmar; Fürle, Constanze; Thomsen, Anja; Watermann, Burkard; Feibicke, Michael

    2017-09-01

    The authorization of biocidal antifouling products for leisure boats is the subject of the European Union Biocides Regulation 528/2012. National specifics may be regarded by the member states in their assessment of environmental risks. The aim of this survey was to collect corresponding data and to create a database for the environmental risk assessment of antifouling active substances in German surface waters. Water concentrations of current antifouling active substances and selected breakdown products were measured in a single-sampling campaign covering 50 marinas at inland and coastal areas. Increased levels were found for Zn, Cu, and cybutryne. For the latter, the maximum allowable concentration according to Directive 2013/39/EU was exceeded at 5 marinas. For Cu, local environmental quality standards were exceeded at 10 marinas. Base data on the total boat inventory in Germany were lacking until now. For that reason, a nationwide survey of mooring berths was conducted by use of aerial photos. About 206 000 mooring berths obviously used by boats with a potential antifouling application were counted. The blind spot of very small marinas was estimated at 20 000 berths. Seventy-one percent of berths were located at freshwater sites, illustrating the importance of navigable inland waterways for leisure boat activities and underlining the need for a customized exposure assessment in these areas. Moreover, the national consumption of all antifouling products for leisure boats was calculated. The total amount of 794 tonnes/annum (t/a) consisted of 179 t/a of inorganic Cu compounds, 19 t/a of organic cobiocides, and 49.5 t/a of Zn. With regard to weight proportion, 141 t/a Cu and 40 t/a Zn were consumed. Assuming an emission ratio of 50% during service life, 70.5 t/a of Cu amounted to 15% of all external sources for Cu release to German surface waters. These figures highlight the need for mitigation measures. Integr Environ Assess Manag 2017;13:892-905. © 2017 The

  5. Table of radionuclides (Vol. 4 - A = 133 to 252)

    International Nuclear Information System (INIS)

    Be, M.M.; Chiste, V.; Dulieu, Ch.; Browne, E.; Chechev, V.; Kuzmenko, N.; Kondev, F.G.; Luca, A.; Galan, M.; Pearce, A.; Huang, X.

    2008-01-01

    This monograph is one of several published in a series by the Bureau International des Poids et Mesures (BIPM) on behalf of the Comite Consultatif des Rayonnements Ionisants (CCRI), previously known as the Comite Consultatif pour les Etalons de Mesure des Rayonnements Ionisants (CCEMRI). The aim of this series of publications is to review topics that are of importance for the measurement of ionizing radiation and especially of radioactivity, in particular those techniques normally used by participants in international comparisons. It is hoped that these publications will prove to be useful reference volumes both for those who are already engaged in this field and for those who are approaching such measurements for the first time. The purpose of this monograph, number 4 in the series, is to present the recommended values of nuclear and decay data for a wide range of radionuclides. Activity measurements for more than fifty-five of these radionuclides have already been the subject of comparisons under the auspices of Section II (dedicated to the Measurement of radionuclides) of the CCRI. The material for this monograph is now covered in four volumes. The first two volumes contain the primary recommended data relating to half-lives, decay modes, x-rays, gamma-rays, electron emissions; alpha- and beta-particle transitions and emissions, and their uncertainties for a set of sixty-eight radionuclides, Volume I for those radionuclides with mass number up to and including 150 and Volume 2 for those radionuclides with mass number over 150. Volume 3 contains the equivalent data for twenty-six additional radionuclides as listed and reevaluations for 125 Sb and 153 Sm while Volume 4 contains the data for a further thirty-one radionuclides with re-evaluation for 226 Ra. The data have been collated and evaluated by an international working group (Decay Data Evaluation Project) led by the LNE-LNHB. The evaluators have agreed on the methodologies to be used and the CD-ROM included

  6. Idaho radionuclide exposure study: Literature review

    International Nuclear Information System (INIS)

    Baker, E.G.; Freeman, H.D.; Hartley, J.N.

    1987-10-01

    Phosphate ores contain elevated levels of natural radioactivity, some of which is released to the environment during processing or use of solid byproducts. The effect of radionuclides from Idaho phosphate processing operations on the local communities has been the subject of much research and study. The literature is reviewed in this report. Two primary radionuclide pathways to the environment have been studied in detail: (1) airborne release of volatile radionuclides, primarily 210 Po, from calciner stacks at the two elemental phosphorus plants; and (2) use of byproduct slag as an aggregate for construction in Soda Springs and Pocatello. Despite the research, there is still no clear understanding of the population dose from radionuclide emissions, effluents, and solid wastes from phosphate processing plants. Two other potential radionuclide pathways to the environment have been identified: radon exhalation from phosphogypsum and ore piles and contamination of surface and ground waters. Recommendations on further study needed to develop a data base for a complete risk assssment are given in the report

  7. Marine energy consumption, national economic activity, and greenhouse gas emissions from international shipping

    International Nuclear Information System (INIS)

    Chang, Ching-Chih

    2012-01-01

    The causal relationships among marine energy consumption, greenhouse gas emissions from international shipping, and economic growth for Kyoto Protocol Annex I countries for the period of 1990 to 2006 are discussed. The real gross domestic product is used as a proxy for economic activity. The United States is also discussed because it was the main global polluter before 2006. The co-integration methodology and an error-correction model are used to examine the causal relationships. The empirical results show that marine energy consumption and GDP are the main factors of increased GHG emissions in the short-run, and that economic activity significantly increased emissions in the long-run. Emissions from shipping are more closely related to marine energy consumption than to economic activity. Hence, policies for mitigating greenhouse gas emissions from marine shipping need to focus on greater energy efficiency in the design of ship engines and hulls. - Highlights: ► Energy consumption and GDP are the main causes to increased GHG emissions in the shipping industry. ► Emissions from shipping are more closely related to energy consumption than to GDP. ► Policies to mitigate GHG emissions from shipping industry should focus on the engine and hull design.

  8. Radionuclides in analytical chemistry

    International Nuclear Information System (INIS)

    Tousset, J.

    1984-01-01

    Applications of radionuclides in analytical chemistry are reviewed in this article: tracers, radioactive sources and activation analysis. Examples are given in all these fields and it is concluded that these methods should be used more widely [fr

  9. Radionuclide Basics: Iodine

    Science.gov (United States)

    ... Centers Radiation Protection Contact Us Share Radionuclide Basics: Iodine Iodine (chemical symbol I) is a chemical element. ... in the environment Iodine sources Iodine and health Iodine in the Environment All 37 isotopes of iodine ...

  10. Trends in cyclotrons for radionuclide production

    International Nuclear Information System (INIS)

    Vera Ruiz, H.; Lambrecht, R.M.

    1999-01-01

    The IAEA recently concluded a worldwide survey of the cyclotrons used for radionuclide production. Most of the institutions responded to the questionnaire. The responses identified technical, utilisation and administrative information for 206 cyclotrons. Compiled data includes the characteristics, performance and popularity of each of the different commercial cyclotrons. Over 20 cyclotrons are scheduled for installation in 1998. The expansion in the number of cyclotron installations during the last decade was driven by the advent of advances in medical imaging instrumentation (namely, positron emission tomography (PET), and more recently by 511 KeV emission tomography); introduction of user friendly compact medical cyclotrons; and recent governmental decisions that permit reimbursement for cyclotron radiopharmaceutical studies by the government or insurance companies. The priorities for the production of clinical, commercial and research radionuclides were identified. The emphasis is on radionuclides used for medical diagnosis with SPET (e.g. 123 I, 201 Tl) and PET (e.g. 11 C, 13 N, 15 O, 18 F) radiopharmaceuticals, and for individualized patient radiation treatment planning (e.g. 64 Cu, 86 Y, 124 I) with PET. There is an emerging trend to advance the cyclotron as an alternative method to nuclear reactors for the production of neutron-rich radionuclides (e.g. 64 Cu, 103 Pd, 186 Re) needed for therapeutic applications. (authors)

  11. Assessment of radionuclide databases in CAP88 mainframe version 1.0 and Windows-based version 3.0.

    Science.gov (United States)

    LaBone, Elizabeth D; Farfán, Eduardo B; Lee, Patricia L; Jannik, G Timothy; Donnelly, Elizabeth H; Foley, Trevor Q

    2009-09-01

    In this study the radionuclide databases for two versions of the Clean Air Act Assessment Package-1988 (CAP88) computer model were assessed in detail. CAP88 estimates radiation dose and the risk of health effects to human populations from radionuclide emissions to air. This program is used by several U.S. Department of Energy (DOE) facilities to comply with National Emission Standards for Hazardous Air Pollutants regulations. CAP88 Mainframe, referred to as version 1.0 on the U.S. Environmental Protection Agency Web site (http://www.epa.gov/radiation/assessment/CAP88/), was the very first CAP88 version released in 1988. Some DOE facilities including the Savannah River Site still employ this version (1.0) while others use the more user-friendly personal computer Windows-based version 3.0 released in December 2007. Version 1.0 uses the program RADRISK based on International Commission on Radiological Protection Publication 30 as its radionuclide database. Version 3.0 uses half-life, dose, and risk factor values based on Federal Guidance Report 13. Differences in these values could cause different results for the same input exposure data (same scenario), depending on which version of CAP88 is used. Consequently, the differences between the two versions are being assessed in detail at Savannah River National Laboratory. The version 1.0 and 3.0 database files contain 496 and 838 radionuclides, respectively, and though one would expect the newer version to include all the 496 radionuclides, 35 radionuclides are listed in version 1.0 that are not included in version 3.0. The majority of these has either extremely short or long half-lives or is no longer in production; however, some of the short-lived radionuclides might produce progeny of great interest at DOE sites. In addition, 122 radionuclides were found to have different half-lives in the two versions, with 21 over 3 percent different and 12 over 10 percent different.

  12. Abscess detection with radionuclides

    International Nuclear Information System (INIS)

    Alavi, J.B.

    1988-01-01

    Radionuclide studies may aid in the diagnosis and localization of intra-abdominal infections. Despite the introduction of new radiographic and ultrasound methods, there are several clinical situations in which radionuclide scans have proved useful. Those include detection of postoperative intra-abdominal abscess, evaluation of liver abscess, differentiation between pancreatic pseudocyst or abscess, evaluation of fever of unknown origin, and evaluation of inflammatory bowel disease. Each clinical situation is discussed separately here

  13. Denmark's national inventory report 2008 - Submitted under the United Nations framework convention on climate change, 1990-2006. Emission inventories

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Ole-Kenneth; Lyck, E; Hjorth Mikkelsen, M [and others

    2008-05-15

    This report is Denmark's National Inventory Report reported to the Conference of the Parties under the United Nations Framework Convention on Climate Change (UNFCCC) due by 15 April 2008. The report contains information on Denmark's inventories for all years' from 1990 to 2006 for CO{sub 2}, CH{sub 4}, N{sub 2}O, HFC{sub s}, PFC{sub s} and SF{sub 6}, CO, NMVOC, SO{sub 2}. (au)

  14. National Medical Cyclotron

    International Nuclear Information System (INIS)

    Boyd, Rex.

    1991-01-01

    The National Medical Cyclotron, under construction at Sydney's Royal Prince Alfred Hospital(RPAH) is to be operated by the Australian Nuclear Science and Technology Organization in collaboration with the hospital. Its main purpose is to produce radioisotopes on commercial basis for distribution to hospitals through Australia as well as short-lived radioisotopes (2 minutes to 2 hours) for immediate application at RPAH in Positron Emission Tomography, to study the dynamics of human physiology and metabolism in organs, bones and soft tissues. A list of the principal cyclotron-produced radionuclides is provided. ills

  15. Radionuclide and Heavy Metal Concentrations in Fish from the Confluences of Major Canyons That Cross Los Alamos National Laboratory Lands with the Rio Grande

    International Nuclear Information System (INIS)

    Kraig, D.H.; Naranjo, L. Jr.; Mullen, M.A.; Fresquez, P.R.

    1999-01-01

    Bottom-feeding fish--catfish, suckers, and carp--that were collected from the confluences of some of the major canyons that cross LANL lands with the Rio Grande (RG) exhibited similar radionuclide (with the exception of 90 Sr), and nonradionuclide concentrations to fish collected upstream of any potential LANL contamination sources. Strontium-90 concentrations in fish from LANL canyons/RG may be associated with LANL operations; however, the concentrations of 90 Sr in fish decrease to background concentrations further downstream of LANL at CR. And, based on the most conservative assumptions (a 95% source term and maximum consumption rate), LANL operations do not result in significant doses to the general public from consuming fish along the length of the RG as it passes through the eastern edge of LANL lands to CR. Moreover, since over 85% of the doses were a result of 90 Sr detected in the muscle plus bone portions of the fish and most of the 90 Sr is associated with the bone, the doses to people that consume only the edible portions of the fish (muscle only), would be significantly lower

  16. Stochastic approach for radionuclides quantification

    Science.gov (United States)

    Clement, A.; Saurel, N.; Perrin, G.

    2018-01-01

    Gamma spectrometry is a passive non-destructive assay used to quantify radionuclides present in more or less complex objects. Basic methods using empirical calibration with a standard in order to quantify the activity of nuclear materials by determining the calibration coefficient are useless on non-reproducible, complex and single nuclear objects such as waste packages. Package specifications as composition or geometry change from one package to another and involve a high variability of objects. Current quantification process uses numerical modelling of the measured scene with few available data such as geometry or composition. These data are density, material, screen, geometric shape, matrix composition, matrix and source distribution. Some of them are strongly dependent on package data knowledge and operator backgrounds. The French Commissariat à l'Energie Atomique (CEA) is developing a new methodology to quantify nuclear materials in waste packages and waste drums without operator adjustment and internal package configuration knowledge. This method suggests combining a global stochastic approach which uses, among others, surrogate models available to simulate the gamma attenuation behaviour, a Bayesian approach which considers conditional probability densities of problem inputs, and Markov Chains Monte Carlo algorithms (MCMC) which solve inverse problems, with gamma ray emission radionuclide spectrum, and outside dimensions of interest objects. The methodology is testing to quantify actinide activity in different kind of matrix, composition, and configuration of sources standard in terms of actinide masses, locations and distributions. Activity uncertainties are taken into account by this adjustment methodology.

  17. Radionuclide accumulations in Clinch River fish

    International Nuclear Information System (INIS)

    Oakes, T.W.; Easterly, C.E.; Shank, K.E.

    1976-01-01

    Fish samples were collected from several locations above Melton Hill Dam, which is upstream from the liquid effluent release point of the Oak Ridge National Laboratory. The sampling locations were chosen to determine the accumulation of natural and man-made radionuclides in fish from areas in the Clinch River not influenced by the Laboratory's liquid effluents. Bass, carp, crappie, shad, bluegill, and other sunfish were collected; ten fish per species were composited to form a single sample for each location. The gamma-emitting radionuclide concentrations were determined by gamma-ray spectroscopy. Estimates of radiological dose to man subsequent to ingestion of these fish are made

  18. 76 FR 15553 - National Emission Standards for Hazardous Air Pollutants for Area Sources: Industrial, Commercial...

    Science.gov (United States)

    2011-03-21

    ... firms to operate and maintain the emissions control systems. Consistent with the legislative history, we... stores/malls, laundries, apartments, restaurants, and hotels/motels. The institutional boiler source...

  19. National Emissions Inventory, U.S., 2014, EPA/OAR/OAQPS/AQAD

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web service contains layers that depict annual emissions for 2014 at the facility and county level for the following criterial pollutants: CO, Lead, NH3, NOx,...

  20. National Emissions Inventory, U.S., 2011, EPA/OAR/OAQPS/AQAD

    Data.gov (United States)

    U.S. Environmental Protection Agency — This web service contains layers that depict annual emissions for 2011 at the facility and county level for the following criterial pollutants: CO, Lead, NH3, NOx,...

  1. Denmark's national inventory report 2005 - submitted under the United Nations frameword convention on climate change. 1990-2003. Emission Inventories

    International Nuclear Information System (INIS)

    Illerup, J.B.

    2005-01-01

    This report is Denmkark's National Inventory Report (NIR) due by 15 April 2005 to the United Nations Framework Convention on Climate Change (UNFCCC). the report contains information on Denmark's inventories for all years from 1990 to 2003. The structure of the report is in accordance with the UNFCCC Guidelines on reporting and review and the report includes detailed information on the inventories for all years from the base year to the year of the current annual inventory submission, in order to ensure the transparency of the inventory. (au)

  2. Radionuclide methods application in cardiac studies

    International Nuclear Information System (INIS)

    Kotina, E.D.; Ploskikh, V.A.; Babin, A.V.

    2013-01-01

    Radionuclide methods are one of the most modern methods of functional diagnostics of diseases of the cardio-vascular system that requires the use of mathematical methods of processing and analysis of data obtained during the investigation. Study is carried out by means of one-photon emission computed tomography (SPECT). Mathematical methods and software for SPECT data processing are developed. This software allows defining physiologically meaningful indicators for cardiac studies

  3. Background concentrations of selected radionuclides, organic compounds, and chemical constituents in ground water in the vicinity of the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Orr, B.R.; Cecil, L.D.; Knobel, L.L.

    1991-01-01

    Background concentrations of radionuclides, organic compounds, and other chemical constituents in water in the Snake River Plain aquifer in Idaho were estimated from groundwater sample analyses. Detectable concentrations of transuranic elements should not be present in water from the Snake River Plain aquifer. Background concentrations of tritium generally range from 75 to 150 pCi/L. Strontium-90 and iodine-129 concentrations generally are 0 and from 0.05 pCi/L, respectively. At the INEL, comparison of the mean and median concentrations of tritium, strontium-90, and iodine-129 indicates that operations locally have affected concentrations in groundwater. Gross alpha-particle and beta-particle radioactivity in water from the Snake River Plain aquifer ranges from 0 to 5 pCi/L and 0 to 8 pCi/L, respectively. Background gamma radiation in groundwater is attributed to cesium-137, cobalt-60, and potassium-40. Cesium-137 and cobalt-60 concentrations generally are zero in groundwater at the INEL. Naturally occurring concentrations of potassium-40 probably are about 300 pCi/L. Background concentrations of organic compounds in water from the Snake River Plain aquifer generally are less than 0.2 microg/L. Background arsenic and chromium concentrations both are about 2 to 3 microg/L. Barium concentrations are from about 50 to about 70 microg/L. Lead and mercury concentrations generally are less than 5 microg/L and 0.1 microg/L, respectively. Cadmium, selenium, and silver concentrations generally are less than 1 microg/L. Nitrate concentrations range from 0 to about 1.4 mg/L

  4. Investigation of rare earth natural radionuclide in Gannan region, Jiangxi province

    International Nuclear Information System (INIS)

    Liu Huiping; Zhong Minglong; Hu Yongmei

    2014-01-01

    In order to identify the types, level and migration law of natural radionuclide in ionic rare earth during its development and utilization process, the natural radionuclide in raw ore, waste residues and wastewater of south ionic rare of Gannan region, Jiangxi province were investigated. The results showed that: the natural radionuclide in rare earth raw ore in An'yuan and Longnan is with high content, in which the specific activities of natural U, 226 Ra and 232 Th are 3.69 × l0 4 , 8.33 × l0 3 and 3,40 × l0 3 Bq/ kg respectively; And the specific activities of the acid-soluble slag are 2.58 × l0 4 , 2.81 × l0 4 and 2.75 × l0 4 Bq/kg respectively; The radioactive level of natural U and 232 Th in some rare earth tailings, and the specific activity of natural U in the neutralizing slag of some individual enterprises is higher than national standards' exemption level (1000 Bq/kg). Also, the total content of Th and U in the efflux wastewater of some rare earth enterprises efflux wastewater are higher than the national emission standards limit (0.1 mg/L). (authors)

  5. Radioactive air emissions 1992 summary

    International Nuclear Information System (INIS)

    Wahl, L.

    1993-10-01

    This report summarizes, by radionuclide or product and by emitting facility, the Laboratory's 1992 radioactive air emissions. In 1992, the total activity of radionuclides emitted into the air from Laboratory stacks was approximately 73,500 Ci. This was an increase over the activity of the total 1991 radioactive air emissions, which was approximately 62,400 Ci. Total 1992 Laboratory emissions of each radionuclide or product are summarized by tables and graphs in the first section of this report. Compared to 1991 radioactive air emissions, total tritium activity was decreased, total plutonium activity was decreased, total uranium activity was decreased, total mixed fission product activity was increased, total 41 Ar activity was decreased, total gaseous/mixed activation product (except 41 Ar) activity was increased, total particulate/vapor activation product activity was increased, and total 32 P activity was decreased. Radioactive emissions from specific facilities are detailed in this report. Each section provides 1992 data on a single radionuclide or product and is further divided by emitting facility. For each facility from which a particular radionuclide or product was emitted, a bar chart displays the air emissions of each radionuclide or product from each facility over the 12 reporting periods of 1992, a line chart shows the trend in total emissions of that radionuclide or product from that facility for the past three years, the greatest activity during the 1990--1992 period is discussed, and unexpected or unusual results are noted

  6. 77 FR 14324 - National Volatile Organic Compound Emission Standards for Aerosol Coatings-Addition of Dimethyl...

    Science.gov (United States)

    2012-03-09

    .... National Technology Transfer and Advancement Act Section 12(d) of the National Technology Transfer and... information claimed to be confidential business information (CBI) or other information whose disclosure is... That Significantly Affect Energy Supply, Distribution, or Use I. National Technology Transfer and...

  7. Radionuclide fixation mechanisms in rocks

    International Nuclear Information System (INIS)

    Nakashima, S.

    1991-01-01

    In the safety evaluation of the radioactive waste disposal in geological environment, the mass balance equation for radionuclide migration is given. The sorption of radionuclides by geological formations is conventionally represented by the retardation of the radionuclides as compared with water movement. In order to quantify the sorption of radionuclides by rocks and sediments, the distribution ratio is used. In order to study quantitatively the long term behavior of waste radionuclides in geological environment, besides the distribution ratio concept in short term, slower radionuclide retention reaction involving mineral transformation should be considered. The development of microspectroscopic method for long term reaction path modeling, the behavior of iron during granite and water interaction, the reduction precipitation of radionuclides, radionuclide migration pathways, and the representative scheme of radionuclide migration and fixation in rocks are discussed. (K.I.)

  8. Radionuclide transfer from contaminated field to crops

    International Nuclear Information System (INIS)

    Ohmomo, Yoichiro; Tanaka, Giichiro

    1987-03-01

    Since the policy for land disposal of radioactive wastes were proposed, the importance of terrestrial radioecology has been re-recognized in Japan. The National Institute of Radiological Sciences (NIRS) held a Two-Day Seminar concerning terrestrial transfer of radionuclides. This is a compilation of papers presented at the seminar. The purpose of the seminar is twofold: firstly, to raise basic problems concerning transfer of not only radionuclides but also elements into crops, as well as to present NIRS's studies on radionuclide transfer; and secondly, to discuss in depth the topics about possible transfer of I-129 into rice plant arising from the commercial fuel reprocessing plant, the construction of which is under planning. Finally, general discussion of further issues on radioecology is given. (Namekawa, K.)

  9. Estimating national landfill methane emissions: an application of the 2006 Intergovernmental Panel on Climate Change Waste Model in Panama.

    Science.gov (United States)

    Weitz, Melissa; Coburn, Jeffrey B; Salinas, Edgar

    2008-05-01

    This paper estimates national methane emissions from solid waste disposal sites in Panama over the time period 1990-2020 using both the 2006 Intergovernmental Panel on Climate Change (IPCC) Waste Model spreadsheet and the default emissions estimate approach presented in the 1996 IPCC Good Practice Guidelines. The IPCC Waste Model has the ability to calculate emissions from a variety of solid waste disposal site types, taking into account country- or region-specific waste composition and climate information, and can be used with a limited amount of data. Countries with detailed data can also run the model with country-specific values. The paper discusses methane emissions from solid waste disposal; explains the differences between the two methodologies in terms of data needs, assumptions, and results; describes solid waste disposal circumstances in Panama; and presents the results of this analysis. It also demonstrates the Waste Model's ability to incorporate landfill gas recovery data and to make projections. The former default method methane emissions estimates are 25 Gg in 1994, and range from 23.1 Gg in 1990 to a projected 37.5 Gg in 2020. The Waste Model estimates are 26.7 Gg in 1994, ranging from 24.6 Gg in 1990 to 41.6 Gg in 2020. Emissions estimates for Panama produced by the new model were, on average, 8% higher than estimates produced by the former default methodology. The increased estimate can be attributed to the inclusion of all solid waste disposal in Panama (as opposed to only disposal in managed landfills), but the increase was offset somewhat by the different default factors and regional waste values between the 1996 and 2006 IPCC guidelines, and the use of the first-order decay model with a time delay for waste degradation in the IPCC Waste Model.

  10. Can EC and UK national methane emission inventories be verified using high precision stable isotope data?

    International Nuclear Information System (INIS)

    Lowry, D.; Holmes, C.W.; Nisbet, E.G.; Rata, N.D.

    2002-01-01

    The main anthropogenic sources of methane in industrialised countries (landfill/waste treatment, gas storage and distribution, coal) are far easier to reduce than CO 2 sources and the implementation of reduction strategies is potentially profitable. Statistical databases of methane emissions need independent external verification and carbon isotope data provide one way of estimating the expected source mix for each country if the main source types have been characterised isotopically. Using this method each country participating in the CORINAIR 94 database has been assigned an expected isotopic value for its emissions. The averaged δ 13 C of methane emitted from the CORINAIR region of Europe, based on total emissions of each country is -55.4 per mille for 1994. This European source mix can be verified using trajectory analysis for air samples collected at background stations. Methane emissions from the UK, and particularly the London region, have undergone more detailed analysis using data collected at the Royal Holloway site on the western fringe of London. If the latest emissions inventory figures are correct then the modelled isotopic change in the UK source mix is from -48.4 per mille in 1990 to -50.7 per mille in 1997. This represents a reduction in emissions of 25% over a 7-year period, important in meeting proposed UK greenhouse gas reduction targets. These changes can be tested by the isotopic analysis of air samples at carefully selected coastal background and interior sites. Regular sampling and isotopic analysis coupled with back trajectory analysis from a range of sites could provide an important tool for monitoring and verification of EC and UK methane emissions in the run-up to 2010. (author)

  11. Radioactivity: radionuclides in foods

    International Nuclear Information System (INIS)

    Simpson, R.E.; Baratta, E.J.; Jelinek, C.F.

    1977-01-01

    The results are summarized of the analysis for strontium-90, cesium-137, iodine-131, ruthenium-106, and potassium-40, a naturally occurring radionuclide, in samples of total diet and selected import commodities in the foods compliance program of the Food and Drug Administration. On the basis of the radionuclide intake guidelines established by the Federal Radiation Council (FRC), the low content of radionuclides found in the total diet samples for fiscal years 1973 and 1974 demonstrates the need for surveillance only at the present level. The low levels of radionuclides found in a limited number of edible imported commodities indicate that their contribution to the total diet would not increase the levels of these radionuclides above those recommended for only periodic surveillance by the FRC. The potassium levels, determined from potassium-40 activity, found in meats and fish agree with the value for normal muscle tissue for the reference man reported by the International Commission on Radiation Protection. Of the other commodities, nuts contained the highest levels, while sugar, beverages, and processed foods contained the lowest levels of potassium. Although cesium and potassium are chemical analogs with similar metabolic properties, because of their variable content in some leafy samples as a result of surface contamination, a correlation between cesium-137 levels and the cesium-137-to-potassium ratio was inconclusive

  12. The evolution of emissions trading in the EU. Tensions between national trading schemes and the proposed EU directive

    International Nuclear Information System (INIS)

    Boemare, Catherine; Quirion, Philippe; Sorrell, Steve

    2003-12-01

    The EU is pioneering the development of greenhouse gas emissions trading, but there is a tension between the 'top-down' and 'bottom-up' evolution of trading schemes. While the Commission is introducing a European emissions trading scheme (EU ETS) in 2005, several member states have already introduced negotiated agreements that include trading arrangements. Typically, these national schemes have a wider scope than the proposed EU directive and allow firms to use relative rather than absolute targets. The coexistence of 'top-down' and 'bottom-up' trading schemes may create some complex problems of policy interaction. This paper explores the potential interactions between the EU ETS and the negotiated agreements in France and UK and uses these to illustrate some important generic issues. The paper first describes the proposed EU directive, outlines the UK and French policies and compares their main features to the EU ETS. It then discusses how the national and European policies may interact in practice. Four issues are highlighted, namely, double regulation, double counting of emission reductions, equivalence of effort and linking trading schemes. The paper concludes with some recommendations for the future development of UK and French climate policy

  13. Chinese companies’ awareness and perceptions of the Emissions Trading Scheme (ETS): Evidence from a national survey in China

    International Nuclear Information System (INIS)

    Yang, Lin; Li, Fengyu; Zhang, Xian

    2016-01-01

    China announced the launch of a national Emissions Trading Scheme (ETS) in 2017; however, companies appear show little enthusiasm for participation in the ETS in China. This paper identifies the factors affecting companies’ awareness and perceptions of ETS by conducting a national survey based on an online questionnaire from May to November 2015 in seven carbon trading pilots. The results indicate that companies’ attitudes towards the ETS are positively influenced by government regulations and policy, public relations management and estimated economic benefit. Of these, public relations management is the decisive factor and estimated economic benefit is confirmed to be a relatively weak predictor. A company's environmental and energy strategy exerts insignificant effects on its preference for the ETS, although the sampled companies are very willing to save energy and reduce emissions. There exists an inverted U-shape relationship between a company's level of mitigation technologies and its attitudes towards the ETS. The carbon price fails to stimulate companies to upgrade mitigation technologies. The majority of companies treat participation in the ETS only as a means of improving ties with governments, as well as of earning a good social reputation, rather than as a cost-effective mechanism to mitigate greenhouse gas emissions. - Highlights: • This paper provides a timely study of companies’ awareness of ETS in China. • ETS is not approved by companies as a cost-effective mitigation tool. • External pressure is the most important indicator. • Carbon price fails to promote companies to upgrade mitigation technologies.

  14. MercNet: A national monitoring network to assess responses to changing mercury emissions in the United States

    Science.gov (United States)

    Schmeltz, D.; Evers, D.C.; Driscoll, C.T.; Artz, R.; Cohen, M.; Gay, D.; Haeuber, R.; Krabbenhoft, D.P.; Mason, R.; Morris, K.; Wiener, J.G.

    2011-01-01

    A partnership of federal and state agencies, tribes, industry, and scientists from academic research and environmental organizations is establishing a national, policy-relevant mercury monitoring network, called MercNet, to address key questions concerning changes in anthropogenic mercury emissions and deposition, associated linkages to ecosystem effects, and recovery from mercury contamination. This network would quantify mercury in the atmosphere, land, water, and biota in terrestrial, freshwater, and coastal ecosystems to provide a national scientific capability for evaluating the benefits and effectiveness of emission controls. Program development began with two workshops, convened to establish network goals, to select key indicators for monitoring, to propose a geographic network of monitoring sites, and to design a monitoring plan. MercNet relies strongly on multi-institutional partnerships to secure the capabilities and comprehensive data that are needed to develop, calibrate, and refine predictive mercury models and to guide effective management. Ongoing collaborative efforts include the: (1) development of regional multi-media databases on mercury in the Laurentian Great Lakes, northeastern United States, and eastern Canada; (2) syntheses and reporting of these data for the scientific and policy communities; and (3) evaluation of potential monitoring sites. The MercNet approach could be applied to the development of other monitoring programs, such as emerging efforts to monitor and assess global mercury emission controls. ?? 2011 Springer Science+Business Media, LLC (outside the USA).

  15. Production of radionuclides with generators

    International Nuclear Information System (INIS)

    Khujaev, S.; Egamediev, S.Kh.

    2004-01-01

    (75-85%) independently of the 99 Mo activity (250 - 1000 mCi) at the beginning and the end (up to 15 days) of the period of use. 188 W- 188 Re generator. 188 Re (T 1/2 =16.9 hours, β - m ax=2.12 MeV; γ=155 keV, 15%) is currently attractive radionuclide for radiotherapeutic applications. Rhenium-188 is produced by decay of tungsten-188 (T 1/2 =69.4 d) which can be produced by double neutron capture on enriched 188 W targets with high neutron flux. The specific activity of 188 W is reached up to 2 Ci/g. The optimal conditions for separation of 188 Re from the parent nuclide 188 W are studied. It is shown that the optimal separation condition is using acid-treated aluminium-oxide column to adsorb 188 W as isopolytungstate at pH solution of 2-4. 188 Re is eluted with 0.9% NaCl solution. The characteristics of the sodium perrhenate obtained from our generator are: radiochemical purity is 99.8%; pH 4.0-6.0; yield of 188 Re is 70-75%; breakthrough of 188 W is less than 10 -3 %. 68 Ge- 68 Ga generator. The nuclide 68 Ga (T 1/2 =68.3 min) produced by the electron capture decay of 68 Ge (T 1/2 =288 d) is useful for calibrating positron emission tomography (PET) systems. The 68 Ge is normally produced by both 66 Zn(α,2n) 68 Ge and 69 Ga(p,2n) 68 Ge nuclear reactions. The separation of daughter 68 Ga from parent 68 Ge on both aluminium oxide and tin dioxide are studied. In case of tin dioxide the optimal separation of daughter 68 Ga from parent 68 Ge can be achieved by using 1 M HCl as the eluent. It is shown that the tin dioxide - 1 M HCl generator system provides high yields of 68 Ga (75-80%) with low levels of breakthrough of 68 Ge (2 · 10 -4 %). However, the obtained final product - 68 Ga eluate in 1 M HCl can not be used for direct preparation of radiopharmaceuticals. In case of aluminium oxide we have found that preliminary annealing of aluminium oxide at 1000 deg C provides the best conditions for separation of 68 Ge- 68 Ga radionuclide chain in 0.1 M hydrochloric acid

  16. Comparative analysis of greenhouse gas emissions between scenarios - Contribution of the Experts Group - National Debate on Energy Transition

    International Nuclear Information System (INIS)

    Salomon, Thierry

    2013-01-01

    Within the frame of the French national debate on energy transition, this document briefly presents and comments calculations of greenhouse gas emissions according to 11 scenarios associated with 4 pathways: electrification and de-carbonation (NegaTEP), steady demand and diversification (Ancre DIV), efficiency and diversification (Ademe), and energy saving and phasing out nuclear (Negawatt). These pathways and scenarios are analysed in terms of greenhouse gas emissions and with respect to the objective of a factor-4 reduction by 2050. Emission data for 1990 and 2011 are recalled, as well as France commitments. The author outlines that only four scenarios reach this factor-4 objective as far as CO 2 combustion is concerned, that a factor 2 seems to be possible for some specific sectors (agriculture and wastes). He notices significant decreases in industrial processes since 1990, that only 2 scenarios and 2 pathways reach the factor-4 as far as all greenhouse gases are concerned. When taking energy demand into account, no scenario is able to reach the factor-4 without any strong policy of energy saving. Two conditions are therefore identified to reach this factor: a significant decrease of energy demand, and an action on all emission sources

  17. Radionuclides in house dust

    CERN Document Server

    Fry, F A; Green, N; Hammond, D J

    1985-01-01

    Discharges of radionuclides from the British Nuclear Fuel plc (BNFL) reprocessing plant at Sellafield in Cumbria have led to elevated concentrations radionuclides in the local environment. The major routes of exposure of the public are kept under review by the appropriate Government departments and monitoring is carried out both by the departments and by BNFL itself. Recently, there has been increasing public concern about general environmental contamination resulting from the discharges and, in particular, about possible exposure of members of the public by routes not previously investigated in detail. One such postulated route of exposure that has attracted the interest of the public, the press and Parliament arises from the presence of radionuclides within houses. In view of this obvious and widespread concern, the Board has undertaken a sampling programme in a few communities in Cumbria to assess the radiological significance of this source of exposure. From the results of our study, we conclude that, alt...

  18. Inverse modelling of national and European CH4 emissions using the atmospheric zoom model TM5

    Directory of Open Access Journals (Sweden)

    P. Bergamaschi

    2005-01-01

    Full Text Available A synthesis inversion based on the atmospheric zoom model TM5 is used to derive top-down estimates of CH4 emissions from individual European countries for the year 2001. We employ a model zoom over Europe with 1° × 1° resolution that is two-way nested into the global model domain (with resolution of 6° × 4°. This approach ensures consistent boundary conditions for the zoom domain and thus European top-down estimates consistent with global CH4 observations. The TM5 model, driven by ECMWF analyses, simulates synoptic scale events at most European and global sites fairly well, and the use of high-frequency observations allows exploiting the information content of individual synoptic events. A detailed source attribution is presented for a comprehensive set of 56 monitoring sites, assigning the atmospheric signal to the emissions of individual European countries and larger global regions. The available observational data put significant constraints on emissions from different regions. Within Europe, in particular several Western European countries are well constrained. The inversion results suggest up to 50-90% higher anthropogenic CH4 emissions in 2001 for Germany, France and UK compared to reported UNFCCC values (EEA, 2003. A recent revision of the German inventory, however, resulted in an increase of reported CH4 emissions by 68.5% (EEA, 2004, being now in very good agreement with our top-down estimate. The top-down estimate for Finland is distinctly smaller than the a priori estimate, suggesting much smaller CH4 emissions from Finnish wetlands than derived from the bottom-up inventory. The EU-15 totals are relatively close to UNFCCC values (within 4-30% and appear very robust for different inversion scenarios.

  19. National CO2 emissions trading in European perspective; Nationale CO2-emissiehandel in Europees perspectief

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-06-01

    This report is the reaction of the Social and economic council (SER) in the Netherlands to the request of the Dutch Ministry of Housing, Spatial Planning en Environment (VROM) to formulate an advice on the final report of the Committee CO2 Trade (a.k.a the Vogtlander Committee). This Committee has drafted a proposal for a CO2 emission trade system in the Netherlands. The SER has also taken into account the proposal of the European Committee on a guideline for CO2 emission trade in the European Union (EU)

  20. Radionuclides in foods

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains data on the levels of radionuclides in the UK foodchain. Most data derive from monitoring programmes that exist around nuclear sites, and in some cases date back to the 1960s. Some comparative data from site operator and government-run programmes are included. Data from monitoring undertaken after the Chernobyl accident are summarised. General monitoring of the foodchain for both artificial and natural radionuclides, and the results of relevant government-sponsored research are also described. The report includes basic information on radioactivity in the environment, radiation protection standards and describes what measures are taken to routinely monitor the foodchain and assess public risk. (Author)

  1. Targeted Radionuclide Therapy

    Directory of Open Access Journals (Sweden)

    David Cheng

    2011-10-01

    Full Text Available Targeted radiotherapy is an evolving and promising modality of cancer treatment. The killing of cancer cells is achieved with the use of biological vectors and appropriate radionuclides. Among the many advantages of this approach are its selectiveness in delivering the radiation to the target, relatively less severe and infrequent side effects, and the possibility of assessing the uptake by the tumor prior to the therapy. Several different radiopharmaceuticals are currently being used by various administration routes and targeting mechanisms. This article aims to briefly review the current status of targeted radiotherapy as well as to outline the advantages and disadvantages of radionuclides used for this purpose.

  2. Targeted Radionuclide Therapy

    Energy Technology Data Exchange (ETDEWEB)

    Ersahin, Devrim, E-mail: devrimersahin@yahoo.com; Doddamane, Indukala; Cheng, David [Department of Diagnostic Radiology, School of Medicine, Yale University, 333 Cedar St., New Haven, CT 06520 (United States)

    2011-10-11

    Targeted radiotherapy is an evolving and promising modality of cancer treatment. The killing of cancer cells is achieved with the use of biological vectors and appropriate radionuclides. Among the many advantages of this approach are its selectiveness in delivering the radiation to the target, relatively less severe and infrequent side effects, and the possibility of assessing the uptake by the tumor prior to the therapy. Several different radiopharmaceuticals are currently being used by various administration routes and targeting mechanisms. This article aims to briefly review the current status of targeted radiotherapy as well as to outline the advantages and disadvantages of radionuclides used for this purpose.

  3. Radionuclide deposition control

    International Nuclear Information System (INIS)

    1980-01-01

    A method is described for controlling the deposition, on to the surfaces of reactor components, of the radionuclides manganese-54, cobalt-58 and cobalt-60 from a liquid stream containing the radionuclides. The method consists of disposing a getter material (nickel) in the liquid stream, and a non-getter material (tantalum, tungsten or molybdenum) as a coating on the surfaces where deposition is not desired. The process is described with special reference to its use in the coolant circuit in sodium cooled fast breeder reactors. (U.K.)

  4. Radionuclide examination in rheumatology

    International Nuclear Information System (INIS)

    Streda, A.; Kolar, J.; Valesova, M.

    1984-01-01

    On the basis of twenty years of experience with the use of radionuclides in bone and articular rheumatic diseases indications for such examinations are summed up. The main advantage of the use of radionuclide methods is that they bring forward early diagnosis of tissue reconstruction which can thus be detected at the stage of microstructural changes. They also provide earlier and more reliable detection of the degree of the pathological process than is provided by X-ray examination. In some cases scintiscan may also be found useful as a method for following up the results of treatment of rheumatic diseases. (author)

  5. Targeted Radionuclide Therapy

    International Nuclear Information System (INIS)

    Ersahin, Devrim; Doddamane, Indukala; Cheng, David

    2011-01-01

    Targeted radiotherapy is an evolving and promising modality of cancer treatment. The killing of cancer cells is achieved with the use of biological vectors and appropriate radionuclides. Among the many advantages of this approach are its selectiveness in delivering the radiation to the target, relatively less severe and infrequent side effects, and the possibility of assessing the uptake by the tumor prior to the therapy. Several different radiopharmaceuticals are currently being used by various administration routes and targeting mechanisms. This article aims to briefly review the current status of targeted radiotherapy as well as to outline the advantages and disadvantages of radionuclides used for this purpose

  6. 76 FR 35806 - Amendments to National Emission Standards for Hazardous Air Pollutants for Area Sources: Plating...

    Science.gov (United States)

    2011-06-20

    ...., Washington, DC. The Public Reading Room is open from 8:30 a.m. to 4:30 p.m. Eastern Standard Time (EST... parties interested in commenting must do so at this time. For further information, please see the... chromium anodizing sources, as those sources are subject to 40 CFR part 63, subpart N, ``Chromium Emissions...

  7. 76 FR 76259 - National Emissions Standards for Hazardous Air Pollutants: Primary Aluminum Reduction Plants

    Science.gov (United States)

    2011-12-06

    ... Emissions From Maleic Anhydride Plants, Ethylbenzene/Styrene Plants, Benzene Storage Vessels, Benzene...). The rule is applicable to facilities with affected sources associated with the production of aluminum... are subject to the requirements of this NESHAP: 14 primary aluminum production plants and one carbon...

  8. 76 FR 28318 - National Emission Standards for Hazardous Air Pollutants From the Portland Cement Manufacturing...

    Science.gov (United States)

    2011-05-17

    ... Cement Manufacturing Industry and Standards of Performance for Portland Cement Plants AGENCY... Emission Standards for Hazardous Air Pollutants from the Portland Cement Manufacturing Industry Response to... by the Portland Cement Industry and the New Source Performance Standards for Portland Cement Plants...

  9. 78 FR 7487 - National Emission Standards for Hazardous Air Pollutants for Area Sources: Industrial, Commercial...

    Science.gov (United States)

    2013-02-01

    ... small coal-fired units (i.e., with a design heat input capacity of less than 10 MMBtu/hr) are subject to... existing area source coal-fired boilers with heat input capacity of 10 MMBtu/hr or greater may need to... most emissions from area source boilers, two pollutants emitted by coal-fired boilers, POM as 7-PAH and...

  10. Methodology and emission scenarios employed in the development of the National Energy Strategy

    International Nuclear Information System (INIS)

    Fisher, R.E.

    1992-01-01

    This paper describes the steps taken to model the National Energy Strategy (NES). It provides an overview of the NES process including the models used for the project. The National Energy Strategy Environmental Analysis Model (NESEAM), which was used in analyzing environmental impacts, is discussed. The structure of NESEAM, as well as results and analyses are presented

  11. 75 FR 41991 - Amendments to National Emission Standards for Hazardous Air Pollutants: Area Source Standards for...

    Science.gov (United States)

    2010-07-20

    ... Technology Transfer and Advancement Act Section 12(d) of the National Technology Transfer and Advancement Act... confidential business information (CBI) or other information whose disclosure is restricted by statute. Do not... Concerning Regulations That Significantly Affect Energy Supply, Distribution, or Use I. National Technology...

  12. CO{sub 2} emissions trading. A study on the conditions and necessities for starting national emissions trading; CO{sub 2} -paeaestoekauppa. Selvitys kansallisen paeaestoekaupan kaeyttoeoenoton edellytyksistae sekae siinae huomioitavista seikoista

    Energy Technology Data Exchange (ETDEWEB)

    Maeaettae, K.

    2000-02-01

    This study analyses the applicability of emissions trading as a means of steering climate policy. Attention is paid to limiting carbon dioxide emissions in particular at national level. The model used in the implementation of national CO{sub 2} emissions trading are the emissions trading schemes applied in the United States, especially the trading in sulphur dioxide allowances, included in their Acid Rain Programme. All schemes applied until now are studied in order to specify what kinds of hindrances there could be to the well-functioning of emissions trading and also to map out what kinds of institutional innovations have been developed in practice to improve emissions trading. This study excludes the joint implementation procedure and the clean development mechanism. In fact, international control related to climate policy has been left to minor attention in other respects, too. In addition to the subjects mentioned above, this study also describes the terminological and legal framework within which emissions trading is to be practised. In this connection, it has been considered necessary to deal with technical legislative details, since, as it has been stated in relation to emissions trading, 'the devil is likely to be in details'. Thus this study discusses, among others, issues pertaining to the construing of. the criterion for an emission quota, i.e. what is actually traded in emissions trading, how the emission quotas and rights can be used (e.g. the emission deposit and emission derivatives), what kinds of provisions should be laid down on eligibility to emissions trading or on who can participate in emissions trading, what should be the validity period of an emission right, what would be the most appropriate way to organise the administrative control of emissions trading, and what kinds of sanctions should be laid down for infringements related to emissions trading. This study has been carried out by examining mainly U.S. literature on this

  13. Oak Ridge Reservation Environmental Protection Rad Neshaps Radionuclide Inventory Web Database and Rad Neshaps Source and Dose Database.

    Science.gov (United States)

    Scofield, Patricia A; Smith, Linda L; Johnson, David N

    2017-07-01

    The U.S. Environmental Protection Agency promulgated national emission standards for emissions of radionuclides other than radon from US Department of Energy facilities in Chapter 40 of the Code of Federal Regulations (CFR) 61, Subpart H. This regulatory standard limits the annual effective dose that any member of the public can receive from Department of Energy facilities to 0.1 mSv. As defined in the preamble of the final rule, all of the facilities on the Oak Ridge Reservation, i.e., the Y-12 National Security Complex, Oak Ridge National Laboratory, East Tennessee Technology Park, and any other U.S. Department of Energy operations on Oak Ridge Reservation, combined, must meet the annual dose limit of 0.1 mSv. At Oak Ridge National Laboratory, there are monitored sources and numerous unmonitored sources. To maintain radiological source and inventory information for these unmonitored sources, e.g., laboratory hoods, equipment exhausts, and room exhausts not currently venting to monitored stacks on the Oak Ridge National Laboratory campus, the Environmental Protection Rad NESHAPs Inventory Web Database was developed. This database is updated annually and is used to compile emissions data for the annual Radionuclide National Emission Standards for Hazardous Air Pollutants (Rad NESHAPs) report required by 40 CFR 61.94. It also provides supporting documentation for facility compliance audits. In addition, a Rad NESHAPs source and dose database was developed to import the source and dose summary data from Clean Air Act Assessment Package-1988 computer model files. This database provides Oak Ridge Reservation and facility-specific source inventory; doses associated with each source and facility; and total doses for the Oak Ridge Reservation dose.

  14. Taking radionuclides to heart

    International Nuclear Information System (INIS)

    Kleynhans, P.H.T.; Lotter, M.G.; Van Aswegen, A.; Minnaar, P.C.; Iturralde, M.; Herbst, C.P.; Marx, D.

    1980-01-01

    Ischaemic heart disease is a main cause of death in South Africa. Non-invasive ECG gated radionuclide bloodpool imaging plays an increasingly useful role in the evalution of the function of the heart as a pump, and the extent of heart muscle perfusion defects is further pinpointed by invasive krypton-81m studies to improve patient management

  15. Soil burden by radionuclides

    International Nuclear Information System (INIS)

    Blum, W.E.H.; Wenzel, W.W.

    1989-01-01

    Natural radioactivity - half-lifes and radiation type of man-made nuclides, radionuclide behaviour in soils, effects on soil condition and soil functions are described. The only mode of decontamination is by decay and thus primarily dependent on the half-life of nuclides

  16. Radionuclides in house dust

    Energy Technology Data Exchange (ETDEWEB)

    Fry, F A; Green, N; Dodd, N J; Hammond, D J

    1985-04-01

    Discharges of radionuclides from the British Nuclear Fuel plc (BNFL) reprocessing plant at Sellafield in Cumbria have led to elevated concentrations radionuclides in the local environment. The major routes of exposure of the public are kept under review by the appropriate authorising Government departments and monitoring is carried out both by the departments and by BNFL itself. Recently, there has been increasing public concern about general environmental contamination resulting from the discharges and, in particular, about possible exposure of members of the public by routes not previously investigated in detail. One such postulated route of exposure that has attracted the interest of the public, the press and Parliament arises from the presence of radionuclides within houses. In view of this obvious and widespread concern, the Board has undertaken a sampling programme in a few communities in Cumbria to assess the radiological significance of this source of exposure. From the results of our study, we conclude that, although radionuclides originating rom the BNFL site can be detected in house dust, this source of contamination is a negligible route of exposure for members of the public in West Cumbria. This report presents the results of the Board's study of house dust in twenty homes in Cumbria during the spring and summer of 1984. A more intensive investigation is being carried out by Imperial College. (author)

  17. Radionuclide body function imager

    International Nuclear Information System (INIS)

    Stoddart, H.F.

    1983-01-01

    A transverse radionuclide scan field imaging apparatus is claimed. It comprises: a plurality of highly focused closely laterally adjacent collimators arranged inwardly focused in an array which surrounds a scan field, each collimator being moveable relative to its adjacent collimator; means for rotating the array about the scan field and means for imparting travel to the collimators

  18. A national inventory of greenhouse gas (GHG), criteria air contaminants (CAC) and hydrogen sulphide (H2S) emissions by the upstream oil and gas industry : volume 1, overview of the GHG emissions inventory : technical report

    International Nuclear Information System (INIS)

    2004-09-01

    A detailed inventory of greenhouse gas (GHG) emissions from the upstream oil and gas sector in Canada was presented along with explanations of the methodologies and data sources used. This report is based on previous work done on methane and volatile organic compound emissions from the upstream oil and gas sector for the period of 1990 to 1995, but it includes key improvements in identifying primary types of emissions sources such as emissions from fuel combustion, flaring, venting, fugitive equipment leaks and accidental releases. It also includes criteria air contaminants and hydrogen sulfide emissions, an analysis of GHG emission intensities and a change in the definition of volatile organic compounds from comprising all non-methane hydrocarbons to comprising all non-methane and non-ethane hydrocarbons. The report covers portions of the upstream oil and gas industry in Canada plus the natural gas transmission and natural gas distribution industries with reference to well drilling, oil production, and natural gas production, processing, transmission and distribution. Accidents and equipment failures are also included. The report reveals the total GHG emissions by source type, sub-sector, facility type and sub-type for the year 2000 at the national level. In 2000, the total carbon dioxide equivalent GHG emissions from the entire oil and gas sector were 101,211 kilo tonnes. For the upstream oil and gas sector alone, total GHG emissions were 84,355 kilo tonnes, representing 12 per cent of Canada's total national emissions of GHGs in 2000. This is an increase of about 25 per cent from 1995 levels. The biggest primary source of these emissions is fuel combustion, which accounts for 40.8 per cent of the total. This report also includes a provincial breakdown of GHG emissions for the natural gas transmission, storage and distribution sub-sectors in Canada for the year 2000. refs., tabs., figs

  19. Radionuclide releases to the Columbia River from Hanford Operations, 1944--1971

    International Nuclear Information System (INIS)

    Heeb, C.M.; Bates, D.J.

    1994-05-01

    The purpose of the Hanford Environmental Dose Reconstruction (HEDR) Project is to estimate the radiation dose that individuals could have received as a result of radionuclide emissions since 1944 from the Hanford Site. One source of radionuclide releases to the Columbia River was from production reactor operations. This report provides a quantitative estimate of the amount of radioactivity released each month (1944--1971) to the Columbia River from eleven radionuclides as well as from gross beta activity

  20. Assessing Multiple Pathways for Achieving China’s National Emissions Reduction Target

    Directory of Open Access Journals (Sweden)

    Mingyue Wang

    2018-06-01

    Full Text Available In order to achieve China’s target of carbon intensity emissions reduction in 2030, there is a need to identify a scientific pathway and feasible strategies. In this study, we used stochastic frontier analysis method of energy efficiency, incorporating energy structure, economic structure, human capital, capital stock and potential energy efficiency to identify an efficient pathway for achieving emissions reduction target. We set up 96 scenarios including single factor scenarios and multi-factors combination scenarios for the simulation. The effects of each scenario on achieving the carbon intensity reduction target are then evaluated. It is found that: (1 Potential energy efficiency has the greatest contribution to the carbon intensity emissions reduction target; (2 they are unlikely to reach the 2030 carbon intensity reduction target of 60% by only optimizing a single factor; (3 in order to achieve the 2030 target, several aspects have to be adjusted: the fossil fuel ratio must be lower than 80%, and its average growth rate must be decreased by 2.2%; the service sector ratio in GDP must be higher than 58.3%, while the growth rate of non-service sectors must be lowered by 2.4%; and both human capital and capital stock must achieve and maintain a stable growth rate and a 1% increase annually in energy efficiency. Finally, the specific recommendations of this research were discussed, including constantly improved energy efficiency; the upgrading of China’s industrial structure must be accelerated; emissions reduction must be done at the root of energy sources; multi-level input mechanisms in overall levels of education and training to cultivate the human capital stock must be established; investment in emerging equipment and accelerate the closure of backward production capacity to accumulate capital stock.

  1. Radionuclide transfer from soil to plants

    International Nuclear Information System (INIS)

    Teufel, D.; Steinhilber-Schwab, B.; Hoepfner, U.; Ratka, R.; Sand, H. van de; Franke, B.

    1979-01-01

    The planned nuclear reprocessing plant (NEZ) Gorleben will fundamentally differ from actually operating nuclear power plants with regard to its radioactive emissions because relatively long-life isotopes will play a greater role in the emissions. The longevity of the radionuclides emitted in the planned NEZ implies that there will be an accumulation of radionuclides in the surroundings of the plant and long-term effects of the plant on the environment will get higher significance. As radionuclides mainly reach milk and meat via the food of farm animals the transfer of cesium and strontium from the ground into plants was amply investigated. The results show that the correlation calculations are suitable to describe the effect of different parameters on the transfer factor. They are not suited for a forecast of the transfer conditions on a certain location for the reasons explained before. Location-specific measurements seem to be indispensable for these purposes. Besides the greenhouse tests open air measurements of fall-out nuclides with and without elimination of external contamination seem to represent a realistic possibility for the determination of transfer factors. Great attention has to be paid in this kind of tests to the growth conditions (especially fertilization) which have to be accurately registered. (orig./MG) [de

  2. Sources of anthropogenic radionuclides in the environment: a review

    International Nuclear Information System (INIS)

    Hu Qinhong; Weng Jianqing; Wang Jinsheng

    2010-01-01

    Studies of radionuclides in the environment have entered a new era with the renaissance of nuclear energy and associated fuel reprocessing, geological disposal of high-level nuclear wastes, and concerns about national security with respect to nuclear non-proliferation. This work presents an overview on sources of anthropogenic radionuclides in the environment, as well as a brief discussion of salient geochemical behavior of important radionuclides. We first discuss the following major anthropogenic sources and current developments that have lead, or could potentially contribute, to the radionuclide contamination of the environment: (1) nuclear weapons program; (2) nuclear weapons testing; (3) nuclear power plants; (4) uranium mining and milling; (5) commercial fuel reprocessing; (6) geological repository of high-level nuclear wastes that include radionuclides might be released in the future, and (7) nuclear accidents. Then, we briefly summarize the inventory of radionuclides 99 Tc and 129 I, as well as geochemical behavior for radionuclides 99 Tc, 129 I, and 237 Np, because of their complex geochemical behavior, long half-lives, and presumably high mobility in the environment; biogeochemical cycling and environment risk assessment must take into account speciation of these redox-sensitive radionuclides.

  3. Potential Emissions of Tritium in Air from Wells on the Nevada National Security Site

    International Nuclear Information System (INIS)

    Warren, R.

    2012-01-01

    This slide-show discusses the Nevada National Security Site (NNSS) and tritium in the groundwater. It describes the wells and boreholes and potential airflow from these sources. Monitoring of selected wells is discussed and preliminary results are presented

  4. 76 FR 72769 - National Emissions Standards for Hazardous Air Pollutants: Mineral Wool Production and Wool...

    Science.gov (United States)

    2011-11-25

    .... \\4\\ Cement Kiln Recycling Coalition v. EPA, 255 F.3d 855 (DC Cir. 2001) (per curiam). \\5\\ National... insulation and bonded heavy- density products.'' The MACT rule for the Wool Fiberglass Manufacturing source...

  5. Carbon inequality at the sub-national scale: A case study of provincial-level inequality in CO{sub 2} emissions in China 1997-2007

    Energy Technology Data Exchange (ETDEWEB)

    Clarke-Sather, Afton, E-mail: Afton.Clarke-Sather@colorado.edu [Scientific Information Center for Resources and Environment, Lanzhou Branch of the National Science Library, Chinese Academy of Sciences, 8 Middle Tianshui Road, Lanzhou 730000 (China); Department of Geography, University of Colorado, Boulder, 260 UCB, Boulder, CO 80309 (United States); Qu Jiansheng [Scientific Information Center for Resources and Environment, Lanzhou Branch of the National Science Library, Chinese Academy of Sciences, 8 Middle Tianshui Road, Lanzhou 730000 (China); MOE Key Laboratory of Western China' s Environmental Systems, Research School of Arid Environment and Climate Change, Lanzhou University, Lanzhou (China); Wang Qin [MOE Key Laboratory of Western China' s Environmental Systems, Research School of Arid Environment and Climate Change, Lanzhou University, Lanzhou (China); Zeng Jingjing [Scientific Information Center for Resources and Environment, Lanzhou Branch of the National Science Library, Chinese Academy of Sciences, 8 Middle Tianshui Road, Lanzhou 730000 (China); Li Yan [MOE Key Laboratory of Western China' s Environmental Systems, Research School of Arid Environment and Climate Change, Lanzhou University, Lanzhou (China)

    2011-09-15

    This study asks whether sub-national inequalities in carbon dioxide (CO{sub 2}) emissions mirror international patterns in carbon inequality using the case study of China. Several studies have examined global-level carbon inequality; however, such approaches have not been used on a sub-national scale. This study examines inter-provincial inequality in CO{sub 2} emissions within China using common measures of inequality (coefficient of variation, Gini Index, Theil Index) to analyze provincial-level data derived from the IPCC reference approach for the years 1997-2007. It decomposes CO{sub 2} emissions inequality into its inter-regional and intra-regional components. Patterns of per capita CO{sub 2} emissions inequality in China appear superficially similar to, though slightly lower than, per capita income inequality. However, decomposing these inequalities reveals different patterns. While inter-provincial income inequality is highly regional in character, inter-provincial CO{sub 2} emissions inequality is primarily intra-regional. While apparently similar, global patterns in CO{sub 2} emissions are not mirrored at the sub-national scale. - Highlights: > Carbon inequality is different in character within China than at global scale. > Interprovincial CO{sub 2} emissions inequality in China is slightly lower than income inequality. > Interprovincial GDP inequality in China is regional in character. > Interprovincial CO{sub 2} emissions inequality in China is not regional in character.

  6. Carbon inequality at the sub-national scale: A case study of provincial-level inequality in CO2 emissions in China 1997-2007

    International Nuclear Information System (INIS)

    Clarke-Sather, Afton; Qu Jiansheng; Wang Qin; Zeng Jingjing; Li Yan

    2011-01-01

    This study asks whether sub-national inequalities in carbon dioxide (CO 2 ) emissions mirror international patterns in carbon inequality using the case study of China. Several studies have examined global-level carbon inequality; however, such approaches have not been used on a sub-national scale. This study examines inter-provincial inequality in CO 2 emissions within China using common measures of inequality (coefficient of variation, Gini Index, Theil Index) to analyze provincial-level data derived from the IPCC reference approach for the years 1997-2007. It decomposes CO 2 emissions inequality into its inter-regional and intra-regional components. Patterns of per capita CO 2 emissions inequality in China appear superficially similar to, though slightly lower than, per capita income inequality. However, decomposing these inequalities reveals different patterns. While inter-provincial income inequality is highly regional in character, inter-provincial CO 2 emissions inequality is primarily intra-regional. While apparently similar, global patterns in CO 2 emissions are not mirrored at the sub-national scale. - Highlights: → Carbon inequality is different in character within China than at global scale. → Interprovincial CO 2 emissions inequality in China is slightly lower than income inequality. → Interprovincial GDP inequality in China is regional in character. → Interprovincial CO 2 emissions inequality in China is not regional in character.

  7. Calibration of radionuclides with decay trough beta emission or electron capture by liquid scintillation technique; Calibracao de radionuclideos que decaem por emissao beta ou por captura eletronica pela tecnica de cintilacao liquida

    Energy Technology Data Exchange (ETDEWEB)

    Loureiro, Jamir dos Santos

    2000-02-01

    In this work is reported a methodology a methodology for pure beta and electron capture radionuclides standardization, suing liquid scintillation technique. In this sense the CIEMAT/NIST method, recently utilized by international laboratories, was implemented and the lack in the Laboratorio Nacional das Radiacoes Ionizantes - LNMRI, of the Comissao Nacional de Energia Nuclear - CNEN, for adequate methodology to standardize this kind if radionuclides was filled, fact that was not present with alpha and gamma radionuclides. The implementation procedure evaluation was provided by concentration activity determination of the following radionuclides: {sup 14} C and {sup 90} Sr, pure beta emitters; {sup 55} Fe, electron capture decay; {sup 204} Tl, electron capture and beta decay and {sup 60} Co, beta-gamma emitter. In this way, a careful analysis of the implementation procedure with these radionuclides types, ranging on a broad energy spectral, was possible. To check the calibration results, intercomparisons among our measurements of these radionuclides and the reference values of the CIEMAT/Spain laboratory were provided. To check the calibration results, intercomparisons among our measurements of these radionuclides and the reference values of the CIEMAT/Spain laboratory were provided. Besides this intercomparisons, one was provided with a {sup 204} Tl solution, utilized in the international comparison recently promoted by BIPM, and another one with a {sup 60} C solution calibrated in LNMRI/CNEN previously by a relative calibration system, with a well type pressurized ionization chamber, and an absolute beta-gamma coincidence system, with a pill-box type proportional counter 4 {pi} geometry, coupled with a scintillator system with a sodium iodide cristal of 4x4 inches. The comparisons among LNMRI/CNEN results and the reference values, showed a small deviation of 1,32% for {sup 14} C, 0,40% for {sup 60} Co, 1,12% for {sup 55} Fe, 0,10% for {sup 90} Sr and 0,73% for {sup

  8. Alternative radionuclides for using in oil exploratory tools - PIG TAG

    International Nuclear Information System (INIS)

    Pereira Junior, Robson da Costa; Estrada, Julio Jose da Silva; Delgado, Jose Ubiratan; Pinho, Adaugoberto Soares de; Oliveira, Estela Maria de

    2011-01-01

    The ionizing radiations are present from prospecting to production of oil or gas, using a variety of techniques with radioactive sources. The radioactive tracer (pip tag) is a technique in which is placed a mark in different depths of the well that is being profiled. This marker is done generally with gamma emitter 60 Co which activity until 74 kBq (2 μCi). The purpose of this marker is to identify places of interest of investigations or where will be blast the rock that has been identified as potential hydrocarbon deposits. Currently, these radioactive markers are obtained in the international market in the form of metallic solid sources. However, there are some difficulties in the importation of material, ranging from the permission by the regulatory organization (CNEN) to the customs costs, through the attendance criteria set out in international and national standards related to the transport of radioactive material. These import processes, therefore, involve high costs and delays in having the products. This work aims to develop a methodology that makes possible the preparation of alternative radioactive sources in the country in order to supply the growing demand for this market in a shorter time and with less cost. For this purpose, are being evaluated not only the appropriate support for the markers as well as the possibility of replacement 60 Co by other radionuclides that can perform the same functional properly. This replacement will be based on technical parameters such as energy, half-life, and activity and emission intensity, according to the characteristics of each radionuclide to be evaluated. The production of radioactive markers will be made at the National Laboratory for Metrology of Ionizing Radiation of the Institute of Radioprotection and Dosimetry (IRD), while the field tests had been performed in an industry located in the region of Macae-RJ, which is specialized in marking and profiling of wells oil in deep waters. (author)

  9. Enhancement of mode-converted electron Bernstein wave emission during National Spherical Torus Experiment H-mode plasmas

    International Nuclear Information System (INIS)

    Taylor, G.; Efthimion, P.C.; Jones, B.; Le Blanc, B.P.; Maingi, R.

    2002-01-01

    A sudden, threefold increase in emission from fundamental electrostatic electron Bernstein waves (EBW) which mode convert and tunnel to the electromagnetic X-mode has been observed during high energy and particle confinement (H-mode) transitions in the National Spherical Torus Experiment (NSTX) plasma [M. Ono, S. Kaye, M. Peng et al., in Proceedings of the 17th IAEA Fusion Energy Conference (IAEA, Vienna, Austria, 1999), Vol. 3, p. 1135]. The mode-converted EBW emission viewed normal to the magnetic field on the plasma midplane increases when the density profile steepens in the vicinity of the mode conversion layer, which is located in the plasma scrape off. The measured conversion efficiency during the H-mode is consistent with the calculated EBW to X-mode conversion efficiency derived using edge density data. Calculations indicate that there may also be a small residual contribution to the measured X-mode electromagnetic radiation from polarization-scrambled, O-mode emission, converted from EBWs

  10. A recommended approach to the National Pollutant Release Inventory (NPRI) for the upstream oil and gas industry : 2002 : CAC emissions

    International Nuclear Information System (INIS)

    2003-04-01

    The National Pollutant Release Inventory (NPRI) is a database of annual releases to air, water, land and off-site transfers of 273 specified pollutants. Environment Canada requires that the NPRI be reported annually. Criteria Air Contaminants (CAC) had to be reported for the first time in 2002. Air pollutants that contribute to the formation of ground level ozone and smog are included in the definition of CAC, along with any eye or respiratory irritants to both humans and animals. The substances of special interest to the petroleum industry are: oxides of nitrogen, sulphur dioxide, carbon monoxide, volatile organic compounds, total particulate matter, and particulate matters. This guide is intended to provide member companies of Canadian Association of Petroleum Producers (CAPP), operating upstream oil and gas facilities, with readily available data to determine the amount of CAC emissions released from their processes and equipment. Companies using these guidelines will be able to compare the performance of various upstream oil and gas companies more readily because the data is consistent. The scope of the project was described in section 1, and the sources of CAC emissions were identified in section 2. The reporting threshold was discussed in section 3. Data required for collection was outlined in section 4. Section 5 outlines how CAC emission quantities are determined. Calculation examples were provided in section 6 and definitions provided in section 7. 11 tabs., 1 fig

  11. Undertaking high impact strategies: The role of national efficiency measures in long-term energy and emission reduction in steel making

    International Nuclear Information System (INIS)

    Xu, Tengfang; Karali, Nihan; Sathaye, Jayant

    2014-01-01

    Highlights: • Evaluate long-term effects of national energy efficiency in steel making. • Use bottom-up optimization for projection in China, India and the U.S. • The effects include changes in steel production, energy use, emissions, and costs. • Three emission targets induce different structural changes and investments. • Projected energy and CO 2 intensity declines in each country from 2010 to 2050. - Abstract: In this paper, we applied bottom-up linear optimization modeling to analyze long-term national impacts of implementing energy efficiency measures on energy savings, CO 2 -emission reduction, production, and costs of steel making in China, India, and the U.S. We first established two base scenarios representing business-as-usual steel production for each country from 2010 to 2050; Base scenario (in which no efficiency measure is available) and Base-E scenario (in which efficiency measures are available), and model scenarios representing various emission-reduction targets that affects production, annual energy use and costs with the goal of cost minimization. A higher emission-reduction target generally induces larger structural changes and increased investments in nation-wide efficiency measures, in addition to autonomous improvement expected in the Base scenario. Given the same emission-reduction target compared to the base scenario, intensity of annual energy use and emissions exhibits declining trends in each country from year 2010 to 2050. While a higher emission-reduction target result in more energy reduction from the base scenario, such reduction can become more expensive to achieve. The results advance our understanding of long-term effects of national energy efficiency applications under different sets of emission-reduction targets for steel sectors in the three major economies, and provide useful implications for high impact strategies to manage production structures, production costs, energy use, and emission reduction in steel making

  12. Radionuclide cardiography in medical practice

    International Nuclear Information System (INIS)

    Strangfeld, D.; Mohnike, W.; Schmidt, J.; Heine, H.; Correns, H.J.

    1986-01-01

    This publication is a compendium on all aspects of radionuclide diagnostics concerning cardiovascular system diseases. Starting with introductory remarks on the control of cardiovascular diseases the contribution of radionuclide cardiology to functional cardiovascular diagnostics as well as pathophysiological and pathobiochemical aspects of radiocardiography are outlined. Radiopharmaceuticals used in radiocardiography, physical and technical problems in application of radionuclides and their measuring techniques are discussed. In individual chapters radionuclide ventriculography, myocardial scintiscanning, circulatory diagnostics, radionuclide diagnostics of arterial hypertension, of thrombosis and in vitro diagnostics of thrombophilia are treated in the framework of clinical medicine

  13. Table of radionuclides (Vol. 5 - A = 22 to 244)

    International Nuclear Information System (INIS)

    Be, M.M.; Chiste, V.; Dulieu, C.; Mougeot, X.; Browne, E.; Chechev, V.; Kuzmenko, N.; Kondev, F.; Luca, A.; Galan, M.; Arinc, A.; Huang, X.

    2010-01-01

    This monograph is one of several published in a series by the Bureau International des Poids et Mesures (BIPM) on behalf of the Comite Consultatif des Rayonnements Ionisants (CCRI), previously known as the Comite Consultatif pour les Etalons de Mesure des Rayonnements Ionisants (CCEMRI). The aim of this series of publications is to review topics that are of importance for the measurement of ionizing radiation and especially of radioactivity, in particular those techniques normally used by participants in international comparisons. It is hoped that these publications will prove to be useful reference volumes both for those who are already engaged in this field and for those who are approaching such measurements for the first time. The purpose of this monograph is to present the recommended values of nuclear and decay data for a wide range of radionuclides. Activity measurements for more than forty of these radionuclides have already been the subject of comparisons under the auspices of Section II of the CCRI. The material for this monograph is now covered in four volumes. The first two volumes contain the primary recommended data relating to half-lives, decay modes, x-rays, gamma-rays, electron emissions; alpha- and beta-particle transitions and emissions, and their uncertainties for a set of sixty-eight radionuclides: Volume 1 for those radionuclides with mass number up to and including 150, and Volume 2 for those radionuclides with mass number over 150. Volume 3 contains the equivalent data for twenty-six additional radionuclides and re-evaluations for 125 Sb and 153 Sm; Volume 4 contains the data for a further thirty-one radionuclides with re-evaluation for 226 Ra while the present Volume 5 includes 17 new radionuclide evaluations and 8 re-evaluations of previous data as identified in the contents page. The data have been collated and evaluated by an international working group (Decay Data Evaluation Project) led by the LNE-LNHB. The evaluators have agreed on the

  14. Estimates of global, regional, and national annual CO{sub 2} emissions from fossil-fuel burning, hydraulic cement production, and gas flaring: 1950--1992

    Energy Technology Data Exchange (ETDEWEB)

    Boden, T.A.; Marland, G. [Oak Ridge National Lab., TN (United States); Andres, R.J. [University of Alaska, Fairbanks, AK (United States). Inst. of Northern Engineering

    1995-12-01

    This document describes the compilation, content, and format of the most comprehensive C0{sub 2}-emissions database currently available. The database includes global, regional, and national annual estimates of C0{sub 2} emissions resulting from fossil-fuel burning, cement manufacturing, and gas flaring in oil fields for 1950--92 as well as the energy production, consumption, and trade data used for these estimates. The methods of Marland and Rotty (1983) are used to calculate these emission estimates. For the first time, the methods and data used to calculate CO, emissions from gas flaring are presented. This C0{sub 2}-emissions database is useful for carbon-cycle research, provides estimates of the rate at which fossil-fuel combustion has released C0{sub 2} to the atmosphere, and offers baseline estimates for those countries compiling 1990 C0{sub 2}-emissions inventories.

  15. EBS Radionuclide Transport Abstraction

    International Nuclear Information System (INIS)

    J. Prouty

    2006-01-01

    The purpose of this report is to develop and analyze the engineered barrier system (EBS) radionuclide transport abstraction model, consistent with Level I and Level II model validation, as identified in Technical Work Plan for: Near-Field Environment and Transport: Engineered Barrier System: Radionuclide Transport Abstraction Model Report Integration (BSC 2005 [DIRS 173617]). The EBS radionuclide transport abstraction (or EBS RT Abstraction) is the conceptual model used in the total system performance assessment (TSPA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ). The EBS RT Abstraction conceptual model consists of two main components: a flow model and a transport model. Both models are developed mathematically from first principles in order to show explicitly what assumptions, simplifications, and approximations are incorporated into the models used in the TSPA. The flow model defines the pathways for water flow in the EBS and specifies how the flow rate is computed in each pathway. Input to this model includes the seepage flux into a drift. The seepage flux is potentially split by the drip shield, with some (or all) of the flux being diverted by the drip shield and some passing through breaches in the drip shield that might result from corrosion or seismic damage. The flux through drip shield breaches is potentially split by the waste package, with some (or all) of the flux being diverted by the waste package and some passing through waste package breaches that might result from corrosion or seismic damage. Neither the drip shield nor the waste package survives an igneous intrusion, so the flux splitting submodel is not used in the igneous scenario class. The flow model is validated in an independent model validation technical review. The drip shield and waste package flux splitting algorithms are developed and validated using experimental data. The transport model considers advective transport and diffusive transport

  16. EBS Radionuclide Transport Abstraction

    Energy Technology Data Exchange (ETDEWEB)

    J. Prouty

    2006-07-14

    The purpose of this report is to develop and analyze the engineered barrier system (EBS) radionuclide transport abstraction model, consistent with Level I and Level II model validation, as identified in Technical Work Plan for: Near-Field Environment and Transport: Engineered Barrier System: Radionuclide Transport Abstraction Model Report Integration (BSC 2005 [DIRS 173617]). The EBS radionuclide transport abstraction (or EBS RT Abstraction) is the conceptual model used in the total system performance assessment (TSPA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ). The EBS RT Abstraction conceptual model consists of two main components: a flow model and a transport model. Both models are developed mathematically from first principles in order to show explicitly what assumptions, simplifications, and approximations are incorporated into the models used in the TSPA. The flow model defines the pathways for water flow in the EBS and specifies how the flow rate is computed in each pathway. Input to this model includes the seepage flux into a drift. The seepage flux is potentially split by the drip shield, with some (or all) of the flux being diverted by the drip shield and some passing through breaches in the drip shield that might result from corrosion or seismic damage. The flux through drip shield breaches is potentially split by the waste package, with some (or all) of the flux being diverted by the waste package and some passing through waste package breaches that might result from corrosion or seismic damage. Neither the drip shield nor the waste package survives an igneous intrusion, so the flux splitting submodel is not used in the igneous scenario class. The flow model is validated in an independent model validation technical review. The drip shield and waste package flux splitting algorithms are developed and validated using experimental data. The transport model considers advective transport and diffusive transport

  17. EBS Radionuclide Transport Abstraction

    International Nuclear Information System (INIS)

    Schreiner, R.

    2001-01-01

    The purpose of this work is to develop the Engineered Barrier System (EBS) radionuclide transport abstraction model, as directed by a written development plan (CRWMS M and O 1999a). This abstraction is the conceptual model that will be used to determine the rate of release of radionuclides from the EBS to the unsaturated zone (UZ) in the total system performance assessment-license application (TSPA-LA). In particular, this model will be used to quantify the time-dependent radionuclide releases from a failed waste package (WP) and their subsequent transport through the EBS to the emplacement drift wall/UZ interface. The development of this conceptual model will allow Performance Assessment Operations (PAO) and its Engineered Barrier Performance Department to provide a more detailed and complete EBS flow and transport abstraction. The results from this conceptual model will allow PA0 to address portions of the key technical issues (KTIs) presented in three NRC Issue Resolution Status Reports (IRSRs): (1) the Evolution of the Near-Field Environment (ENFE), Revision 2 (NRC 1999a), (2) the Container Life and Source Term (CLST), Revision 2 (NRC 1999b), and (3) the Thermal Effects on Flow (TEF), Revision 1 (NRC 1998). The conceptual model for flow and transport in the EBS will be referred to as the ''EBS RT Abstraction'' in this analysis/modeling report (AMR). The scope of this abstraction and report is limited to flow and transport processes. More specifically, this AMR does not discuss elements of the TSPA-SR and TSPA-LA that relate to the EBS but are discussed in other AMRs. These elements include corrosion processes, radionuclide solubility limits, waste form dissolution rates and concentrations of colloidal particles that are generally represented as boundary conditions or input parameters for the EBS RT Abstraction. In effect, this AMR provides the algorithms for transporting radionuclides using the flow geometry and radionuclide concentrations determined by other

  18. Initial Radionuclide Inventories

    Energy Technology Data Exchange (ETDEWEB)

    H. Miller

    2004-09-19

    The purpose of this analysis is to provide an initial radionuclide inventory (in grams per waste package) and associated uncertainty distributions for use in the Total System Performance Assessment for the License Application (TSPA-LA) in support of the license application for the repository at Yucca Mountain, Nevada. This document is intended for use in postclosure analysis only. Bounding waste stream information and data were collected that capture probable limits. For commercially generated waste, this analysis considers alternative waste stream projections to bound the characteristics of wastes likely to be encountered using arrival scenarios that potentially impact the commercial spent nuclear fuel (CSNF) waste stream. For TSPA-LA, this radionuclide inventory analysis considers U.S. Department of Energy (DOE) high-level radioactive waste (DHLW) glass and two types of spent nuclear fuel (SNF): CSNF and DOE-owned (DSNF). These wastes are placed in two groups of waste packages: the CSNF waste package and the codisposal waste package (CDSP), which are designated to contain DHLW glass and DSNF, or DHLW glass only. The radionuclide inventory for naval SNF is provided separately in the classified ''Naval Nuclear Propulsion Program Technical Support Document'' for the License Application. As noted previously, the radionuclide inventory data presented here is intended only for TSPA-LA postclosure calculations. It is not applicable to preclosure safety calculations. Safe storage, transportation, and ultimate disposal of these wastes require safety analyses to support the design and licensing of repository equipment and facilities. These analyses will require radionuclide inventories to represent the radioactive source term that must be accommodated during handling, storage and disposition of these wastes. This analysis uses the best available information to identify the radionuclide inventory that is expected at the last year of last emplacement

  19. Social impact of air pollution abatement. Societal cost benefit analysis of possible National Emission Ceilings

    International Nuclear Information System (INIS)

    Doenszelmann, C.E.P.; De Bruyn, S.M.; Korteland, M.H.; De Jong, F.; Sevenster, M.N.; Briene, M.; Wienhoven, M.; Bovens, J.

    2008-07-01

    In 2008, the European Commission will launch new proposals for revision of the NEC guideline (2001/81/EG) in which new emission ceilings are proposed for the year 2020. In order to determine which stand the Netherlands should take during the negotiations, the Dutch Ministry of Economic Affairs (also on behalf of the Ministry of Agriculture, Nature and Food Quality) asked CE Delft and Ecorys to conduct a societal cost benefit analysis in collaboration with the Environmental Assessment Agency. This report describes the results of the analysis of two alternative NEC targets for 2020. [mk] [nl

  20. Position in the World-System and National Emissions of Greenhouse Gases

    Directory of Open Access Journals (Sweden)

    Thomas J. Burns

    2015-08-01

    Full Text Available Despite the apparent importance of these dynamics, there is relatively little social science theorization and cross-national research on such global environmental issues. There is especially a paucity of cross-national, quantitative research in sociology that focuses on the social antecedents to environmental outcomes (for exceptions, see Burns et al. 1994, 1995; Kick et al. 1996; Grimes and Roberts 1995. We find this condition surprising given the substantial initial work of environmental sociologists (Dunlap and Catton 1978, 1979; Buttel 1987 and the key role social scientists might in principle play in addressing such worldwide problems (Laska 1993. As a consequence, we propose and assess a perspective on the global and national social causes of one environmental dynamic, the greenhouse effect.

  1. Savannah River Plant airborne emissions and controls

    International Nuclear Information System (INIS)

    Dukes, E.K.; Benjamin, R.W.

    1982-12-01

    The Savannah River Plant (SRP) was established to produce special nuclear materials, principally plutonium and tritium, for national defense needs. Major operating facilities include three nuclear reactors, two chemical separations plants, a fuel and target fabrication plant, and a heavy-water rework plant. An extensive environmental surveillance program has been maintained continuously since 1951 (before SRP startup) to determine the concentrations of radionuclides in a 1200-square-mile area centered on the plant, and the radiation exposure of the population resulting from SRP operations. This report provides data on SRP emissions, controls systems, and airborne radioactive releases. The report includes descriptions of current measurement technology. 10 references, 14 figures, 9 tables

  2. Radionuclide releases to the atmosphere from Hanford Operations, 1944--1972. Hanford Environmental Dose Reconstruction Project

    Energy Technology Data Exchange (ETDEWEB)

    Heeb, C.M.

    1994-05-01

    The purpose of the Hanford Environmental Dose Reconstruction Project is to estimate the radiation dose that individuals could have received as a result of radionuclide emissions since 1944 from the Hanford Site. The first step in determining dose is to estimate the amount and timing of radionuclide releases to air and water. This report provides the air release information.

  3. Distribution and inventories of fallout radionuclides (239+24Pu, 137Cs) and 21Pb to study the filling velocity of salt marshes in Donana National Park (Spain)

    International Nuclear Information System (INIS)

    Gasco, C.; Anton, M.P.; Pozuelo, M.; Clemente, L.; Rodriguez, A.; Yanez, C.; Gonzalez, A.; Meral, J.

    2006-01-01

    Within an extensive multinational and multidisciplinary project carried out in Donana National Park (Spain) to investigate its preservation and regeneration, the filling velocity of the salt marshes has been evaluated through the calculation of their average sediment accumulation rates. 239+24 Pu and 137 Cs from weapons testing fallout and total 21 Pb distribution profiles and inventories have been determined in some of the most characteristic zones of the park, namely, the ponds (or 'lucios') and the waterjets (or 'canos'). Plutonium inventories range from 16 to 101 Bq m -2 , 137 Cs values fluctuate between 514 and 3758 Bq m -2 and unsupported 21 Pb values comprise between 124 and 9398 Bq m -2 . Average sedimentation rates range from 3 to 5 mm y -1 (1952-2002). These data are higher than those obtained by carbon dating for the period 6500 AD-present, estimated as 1.5-2 mm y -1 , suggesting an increase in the accumulation of sediments and the alteration of the park's hydrodynamics caused by the re-channeling of the major rivers feeding the salt marshes

  4. Discharge of radionuclides in liquid effluent

    International Nuclear Information System (INIS)

    Duggleby, J.C.

    1985-01-01

    One of the aims of the Radiation Health Committee of the National Health and Medical Research Council, through Council recommendations, is to achieve some degree of uniformity in State legislation applied to the public health aspects of radiation. In developing the recommendation on the discharge of radionuclides to sewerage systems the Committee made use of the comparatively new concept of the Annual Limit on Intake (ALI)

  5. 76 FR 29031 - National Emissions Standards for Hazardous Air Pollutants: Secondary Lead Smelting

    Science.gov (United States)

    2011-05-19

    ... Agency for Toxic Substances and Disease Registry BACT best available control technology BLDS bag leak... ODW Office of Drinking Water OECA Office of Enforcement and Compliance Assurance OHEA Office of Health... Affect Energy Supply, Distribution, or Use I. National Technology Transfer and Advancement Act J...

  6. 78 FR 6673 - National Emission Standards for Hazardous Air Pollutants for Reciprocating Internal Combustion...

    Science.gov (United States)

    2013-01-30

    ..., Energy and Economic Impacts A. What are the air quality impacts? B. What are the cost impacts? C. What... will assist in stabilizing the grid during periods of instability, preventing electrical blackouts and... important programs that protect the reliability and stability of the national electric service grid. The use...

  7. Radionuclide production and radiopharmaceutical chemistry with BNL cyclotrons

    International Nuclear Information System (INIS)

    Lambrecht, R.M.; Wolf, A.P.

    1985-01-01

    The Brookhaven National Laboratory (BNL) radiopharmaceutical chemistry program focuses on production and utilization of radionuclides having a half-life of > 2 hr. However, a major portion of the BNL program is devoted to short-lived radionuclides, such as 11 C and 18 F. Activities encompassed in the program are classified into seven areas: cyclotron parameters, radiochemistry, design and rapid synthesis of radiopharmaceuticals and labeled compounds, radiotracer evaluation in animals, studies in humans, technology transfer, and several other areas

  8. Fukushima Daiichi Radionuclide Inventories

    Energy Technology Data Exchange (ETDEWEB)

    Cardoni, Jeffrey N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jankovsky, Zachary Kyle [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2016-09-01

    Radionuclide inventories are generated to permit detailed analyses of the Fukushima Daiichi meltdowns. This is necessary information for severe accident calculations, dose calculations, and source term and consequence analyses. Inventories are calculated using SCALE6 and compared to values predicted by international researchers supporting the OECD/NEA's Benchmark Study on the Accident at Fukushima Daiichi Nuclear Power Station (BSAF). Both sets of inventory information are acceptable for best-estimate analyses of the Fukushima reactors. Consistent nuclear information for severe accident codes, including radionuclide class masses and core decay powers, are also derived from the SCALE6 analyses. Key nuclide activity ratios are calculated as functions of burnup and nuclear data in order to explore the utility for nuclear forensics and support future decommissioning efforts.

  9. Radionuclide table. Pt. 1

    International Nuclear Information System (INIS)

    Legrand, Jean; Perolat, J.-P.; Lagoutine, Frederic; Le Gallic, Yves.

    The evaluation of the following 29 radionuclides is presented: 22 Na, 24 Na, sup(24m)Na, 51 Cr, 54 Mn, 57 Co, 58 Co, sup(58m)Co, 60 Co, sup(60m)Co, 75 Se, 103 Ru, sup(103m)Rh, sup(110m)Ag- 110 Ag, 109 Cd, 125 Sb, sup(125mTe), 125 I, 133 Xe, sup(133m)Xe, 131 Cs, 134 Cs, sup(134m)Cs, 139 Ce, 144 Ce- 144 Pr, 144 Pr, 169 Er, 186 Re, 203 Hg. The introduction contains a brief description of radioactive processes and the evaluation rules followed. The best values and associated uncertainties are given for each radionuclide for the major parameters of the decay scheme and the radiation intensities emitted, together with a decay table. Gamma, X-rays and sometimes conversion electron spectra are also provided [fr

  10. Understanding Radionuclide Interactions with Layered Materials

    Science.gov (United States)

    Wang, Y.

    2015-12-01

    Layered materials play an important role in nuclear waste management and environmental cleanup. Better understanding of radionuclide interactions with those materials is critical for engineering high-performance materials for various applications. This presentation will provide an overview on radionuclide interactions with two general categories of layered materials - cationic clays and anionic clays - from a perspective of nanopore confinement. Nanopores are widely present in layered materials, either as the interlayers or as inter-particle space. Nanopore confinement can significantly modify chemical reactions in those materials. This effect may cause the preferential enrichment of radionuclides in nanopores and therefore directly impact the mobility of the radionuclides. This effect also implies that conventional sorption measurements using disaggregated samples may not represent chemical conditions in actual systems. The control of material structures on ion exchange, surface complexation, and diffusion in layered materials will be systematically examined, and the related modeling approaches will be discussed. This work was performed at Sandia National Laboratories, which is a multiprogram laboratory operated by Sandia Corporation, a Lockheed-Martin Company, for the DOE under contract DE-AC04-94AL8500.

  11. Maximum permissible body burdens and maximum permissible concentrations of radionuclides in air and in water for occupational exposure. Recommendations of the National Committee on Radiation Protection. Handbook 69

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1959-06-05

    The present Handbook and its predecessors stem from the Second International Congress of Radiology, held in Stockholm in 1928. At that time, under the auspices of the Congress, the International Commission on Radiological Protection (ICRP) was organized to deal initially with problems of X-ray protection and later with radioactivity protection. At that time 'permissible' doses of X-rays were estimated primarily in terms of exposures which produced erythema, the amount of exposure which would produce a defined reddening of the skin. Obviously a critical problem in establishing criteria for radiation protection was one of developing useful standards and techniques of physical measurement. For this reason two of the organizations in this country with a major concern for X-ray protection, the American Roentgen Ray Society and the Radiology Society of North America, suggested that the National Bureau of Standards assume responsibility for organizing representative experts to deal with the problem. Accordingly, early in 1929, an Advisory Committee on X-ray and Radium Protection was organized to develop recommendations on the protection problem within the United States and to formulate United States points of view for presentation to the International Commission on Radiological Protection. The organization of the U.S. Advisory Committee included experts from both the medical and physical science fields. The recommendations of this Handbook take into consideration the NCRP statement entitled 'Maximum Permissible Radiation Exposures to Man', published as an addendum to Handbook 59 on April 15, 1958. As noted above this study was carried out jointly by the ICRP and the NCRP, and the complete report is more extensive than the material contained in this Handbook.

  12. Maximum permissible body burdens and maximum permissible concentrations of radionuclides in air and in water for occupational exposure. Recommendations of the National Committee on Radiation Protection. Handbook 69

    International Nuclear Information System (INIS)

    1959-01-01

    The present Handbook and its predecessors stem from the Second International Congress of Radiology, held in Stockholm in 1928. At that time, under the auspices of the Congress, the International Commission on Radiological Protection (ICRP) was organized to deal initially with problems of X-ray protection and later with radioactivity protection. At that time 'permissible' doses of X-rays were estimated primarily in terms of exposures which produced erythema, the amount of exposure which would produce a defined reddening of the skin. Obviously a critical problem in establishing criteria for radiation protection was one of developing useful standards and techniques of physical measurement. For this reason two of the organizations in this country with a major concern for X-ray protection, the American Roentgen Ray Society and the Radiology Society of North America, suggested that the National Bureau of Standards assume responsibility for organizing representative experts to deal with the problem. Accordingly, early in 1929, an Advisory Committee on X-ray and Radium Protection was organized to develop recommendations on the protection problem within the United States and to formulate United States points of view for presentation to the International Commission on Radiological Protection. The organization of the U.S. Advisory Committee included experts from both the medical and physical science fields. The recommendations of this Handbook take into consideration the NCRP statement entitled 'Maximum Permissible Radiation Exposures to Man', published as an addendum to Handbook 59 on April 15, 1958. As noted above this study was carried out jointly by the ICRP and the NCRP, and the complete report is more extensive than the material contained in this Handbook

  13. Radionuclide co-precipitation

    International Nuclear Information System (INIS)

    Bruno, J.; Sandino, A.

    1987-12-01

    The thermodynamic and kinetic behaviour of the minor components of the spent fuel matrix has been theoretically and experimentally investigated. Two different situations have been studied: Part I, the near field scenario, where the release and migration of the minor components is dependent on the solubility behaviour of UO 2 (s); Part II, the far field, where the solubility and transport of the radionuclides is related to the major geochemical processes occurring. (orig.)

  14. Radionuclide fate and effects

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    The studies reported here deal with the full range of contaminant behavior and fate, from the initial physicochemical factors that govern radionuclide availability in terrestrial and aquatic environments to studies of contaminant transport by biological means. By design, we focus more on the biologically and chemically mediated transport processes and food-chain pathways than on the purely physical forms of contaminant transport, such as transport by wind and water

  15. Geochemistry and radionuclide migration

    International Nuclear Information System (INIS)

    Isherwood, D.

    1978-01-01

    Theoretically, the geochemical barrier can provide a major line of defense in protecting the biosphere from the hazards of nuclear waste. The most likely processes involved are easily identified. Preliminary investigations using computer modeling techniques suggest that retardation is an effective control on radionuclide concentrations. Ion exchange reactions slow radionuclide migration and allow more time for radioactive decay and dispersion. For some radionuclides, solubility alone may limit concentrations to less than the maximum permissible now considered acceptable by the Federal Government. The effectiveness of the geochemical barrier is ultimately related to the repository site characteristics. Theory alone tells us that geochemical controls will be most efficient in an environment that provides for maximum ion exchange and the precipitation of insoluble compounds. In site selection, consideration should be given to rock barriers with high ion exchange capacity that might also act as semi-permeable membranes. Also important in evaluating the site's potential for effective geochemical controls are the oxidation potentials, pH and salinity of the groundwater

  16. Radionuclides in terrestrial ecosystems

    International Nuclear Information System (INIS)

    Howard, B.J.; Kennedy, V.H.; Nelson, A.

    1983-06-01

    A bibliographical database has been developed to provide quick access to research and background literature in the field of radioecology. This is a development of an earlier database described by Nelson (Bocock 1981). ITE's particular fields of interest have led to a subject bias in the bibliography towards studies in Cumbria, especially those concerned with radionuclides originating from the reprocessing plant at Sellafield, and towards ecological research studies that are complementary to radionuclide studies. Other subjects covered, include the chemistry of radionuclides, budgets and transfers within ecosystems and techniques for the analysis of environmental samples. ITE's research objectives have led to the establishment of a specialized database which is intended to complement rather than compete with the large international databases made available by suppliers such as IRS-DIALTECH or DIALOG. Currently the database holds about 1900 references which are stored on a 2 1/2 megabyte hard disk on a Digital PDP11/34 computer operating under a time shared system. The references follow a standard format. (author)

  17. Radionuclides in marine organisms

    International Nuclear Information System (INIS)

    Honda, Teruyuki

    2001-01-01

    The concentration and accumulation of radionuclides in marine organisms were explained in this paper. Secular change of the radioactivity concentration of 137 Cs in seaweed in coastal area of Japan showed more than 5Bq/kg-fresh in the first half of 1960, but decreased less than 1 Bq/kg-fresh after then and attained to less than 0.1 Bq/kg-fresh in 1990s. However, the value increased a while in 1986, which indicated the effect of Chernobyl accident. The accident increased 137 Cs of shellfish near Japan. The concentration of 239+240 Pu was the lowest value in muscles of fish, but increased from 1.7 to 42.3 mBq/kg wet wt in seaweed in 1999. 99 Tc concentration of seaweed showed from 100 to 1000 times as much as that of seawater. Radionuclides in the Irish Sea are originated from Sellafield reprocessing plant. The concentration factors of macro-algae and surface water fish (IAEA,1985) were shown. Analytical results of U in 61 kinds of marine organs showed that the concentration was different in the part of organ. The higher concentration of U was observed in hard tissue of fish. The concentration factor was different between chemical substances with the same radionuclides. (S.Y.)

  18. Radionuclides in thyroid cancer

    International Nuclear Information System (INIS)

    Mahadev, V.

    1980-01-01

    The three main areas of application of radionuclides in thyroid disease will be reviewed. Firstly thyroid radionuclide imaging in thyroid swellings, in relationship to lumps in the neck and ectopic thyroid tissue such as retrosternal goitre, and lingual goitre will be described. Future developments in the field including tomographic scanning, using the coded aperture method, and fluorescent scans and ultrasound are reviewed. The second area of application is the assessment and evaluation of thyroid function and the therapy of Grave's Disease and Plummer's Disease using radioiodine. The importance of careful collection of the line of treatment, results of treatment locally and the follow-up of patients after radioiodine therapy will be described. The third area of application is in the diagnosis and therapy of thyroid cancer. Investigation of thyroid swelling, and the diagnosis of functioning metastases are reported. The therapeutic iodine scan as the sole evidence of functioning metastatic involvement is recorded. Histological thyroid cancer appears to be increasingly encountered in clinical practice and the plan of management in relation to choice of cases for therapeutic scanning is discussed with case reports. Lastly the role of whole body scanning in relationship to biochemical markers is compared. In the changing field of nuclear medicine radionuclide applications in thyroid disease have remained pre-eminent and this is an attempt to reassess its role in the light of newer developments and local experience in the Institute of Radiotherapy, Oncology and Nuclear Medicine. (author)

  19. Emission of Methane From Enteric Fermentation: National Contribution and Factors Affecting it in Livestock

    Directory of Open Access Journals (Sweden)

    Budi Haryanto

    2009-12-01

    Full Text Available Changing in atmosphere condition is affected by the quantity of gases produced from all activities on the earth. Gases that have effects on global warming are CO2, N2O, H2O, and CH4 (methane. Among other sources of methane are enteric fermentation of organic material from ruminants and feces decomposition. Methane production from ruminants is affected by several factors such as breed/type of animal, feed quality, environmental temperature and physiological status of the animal. Energy as methane in ruminants may reach 2 to 15% of the total energy consumption. To reduce the emission of methane from ruminants, it is necessary to apply a strategic feeding system for more efficient utilization of feed.

  20. Safety of systems for the retention of wastes containing radionuclides

    International Nuclear Information System (INIS)

    1980-11-01

    Information and minimal requirements demanded by CNEN for the emission of the Approval Certificate of the Safety Analysis Report related to system for the retention of wastes containing radionuclide, are established, aiming to assure low radioactivity levels to the environment. (E.G.) [pt