National Library of Energy BETA

Sample records for radiological verification survey

  1. Results of the independent radiological verification survey at 112 Avenue E, Lodi, New Jersey (LJ082V)

    SciTech Connect (OSTI)

    Rodriguez, R.E.; Johnson, C.A.

    1996-09-01

    Thorium ores were processed by the Maywood Chemical Works until the property was sold to Stepan Chemical Company in 1959. Wastes were stored at what is now called the Maywood Interim Storage Site (MISS), owned by the U.S. Department of Energy (DOE). Because of the migration of residuals off site into the surrounding areas, the Stepan property and several vicinity properties were designated for remedial action under the 1984 Energy and Water Development Appropriations Act. The DOE conducted radiological surveys of these sites to evaluate current radiological conditions as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). In 1988, radiological surveys of some private residential properties on Avenue E in Lodi, New Jersey were conducted by members of an ORNL radiological survey team. Results of this survey indicated radiological contamination in excess of the DOE criteria for surface contamination at this vicinity property (112 Avenue E), and it was recommended for remediation. In the fall of 1995, a verification survey of this vicinity property was conducted by ORNL, the independent verification contractor for this effort, in conjunction with decontamination operations conducted under the supervision of Bechtel National Incorporated. The verification survey included complete surface gamma scans of the grounds and the collection of soil samples for radionuclide analysis. This report describes the radiological verification survey of this residential property. Based on the remedial action and verification survey data reported in this document, all radiological measurements fall below the limits prescribed by DOE radiological guidelines established for this site, and the property at 112 Avenue E, Lodi, New Jersey successfully meets the DOE radiological guidelines for unrestricted use.

  2. Results of the independent radiological verification survey at 113 Avenue E, Lodi, New Jersey (LJ081V)

    SciTech Connect (OSTI)

    Rodriguez, R.E.; Johnson, C.A.

    1996-09-01

    Thorium ores were processed by the Maywood Chemical Works until the property was sold to Stepan Chemical Company in 1959. Wastes were stored at what is now called the Maywood Interim Storage Site (MISS), owned by the U. S. Department of Energy (DOE). Because of the migration of residuals off site into the surrounding areas, the Stepan property and several vicinity properties were designated for remedial action under the 1984 Energy and Water Development Appropriations Act. The DOE conducted radiological surveys of these sites to evaluate current radiological conditions as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). In 1988, radiological surveys of some private residential properties on Avenue E in Lodi, New Jersey were conducted by members of an ORNL radiological survey team. Results of this survey indicated radiological contamination in excess of the DOE criteria for surface contamination at this vicinity property (113 Avenue E), and it was recommended for remediation. In the fall of 1995, a verification survey of this vicinity property was conducted by ORNL, the independent verification contractor for this effort, in conjunction with decontamination operations conducted under the supervision of Bechtel National Incorporated. The verification survey included complete surface gamma scans of the grounds and the collection of soil samples for radionuclide analysis. This report describes the radiological verification survey of this residential property.

  3. Results of the independent radiological verification survey at 108 Avenue E, Lodi, New Jersey (LJ084V)

    SciTech Connect (OSTI)

    Rodriguez, R.E.; Johnson, C.A.

    1996-09-01

    Thorium ores were processed by the Maywood Chemical Works until the property was sold to Stepan Chemical Company in 1959. Wastes were stored at what is now called the Maywood Interim Storage Site (MISS), owned by the US Department of Energy (DOE). Because of the migration of residuals off site into the surrounding areas, the Stepan property and several vicinity properties were designated for remedial action under the 1984 Energy and Water Development Appropriations Act. The DOE conducted radiological surveys of these sites to evaluate current radiological conditions as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). In 1988, radiological surveys of some private residential properties on Avenue E in Lodi, New Jersey were conducted by members of an ORNL radiological survey team. Results of this survey indicated radiological contamination in excess of the DOE criteria for surface contamination at this vicinity property (108 Avenue E), and it was recommended for remediation. In the fall of 1995, a verification survey of this vicinity property was conducted by ORNL, the independent verification contractor for this effort, in conjunction with decontamination operations conducted under the supervision of Bechtel National Incorporated. The verification survey included complete surface gamma scans of the grounds and the collection of soil samples for radionuclide analysis. This report describes the radiological verification survey of this residential property.

  4. radiological. survey

    National Nuclear Security Administration (NNSA)

    7%2A en NNSA to Conduct Aerial Radiological Surveys Over San Francisco, Pacifica, Berkeley, And Oakland, CA Areas http:nnsa.energy.govmediaroompressreleasesamsca

  5. Results of the independent radiological verification survey of the lower Sheffield Brook floodplain, Wayne, New Jersey

    SciTech Connect (OSTI)

    Yalcintas, M.G.; Carrier, R.F.

    1989-05-01

    Prior to 1971, the W.R. Grace Company processed and stored radioactive materials at Wayne, New Jersey, under license to the Atomic Energy Commission. Decontamination of structures and storage of waste materials on the property at the Wayne Interim Storage Site (WISS) took place in 1974. Surveys by the State of New Jersey Department of Environmental Protection and by Oak Ridge Associated Universities for the NRC in 1982 indicated that properties adjacent to the WISS contained surface contamination by radioactive residuals in amounts exceeding those acceptable under US Department of Energy (DOE) remedial action guidelines. At the request of DOE, remedial actions have been conducted by Bechtel National, Inc., to remove radioactive residuals from properties adjacent to the site. It is the policy of DOE to assign an independent verification contractor to ensure the effectiveness of remedial actions performed within the Formerly Utilized Sites Remedial Action Program. This report describes the methods and results of those studies that were conducted by the Measurement Applications and Development Group of the Oak Ridge National Laboratory for the lower Sheffield Brook floodplain west of the WISS. Based upon post-remedial action and verification survey data, it was concluded that residual soil concentrations and gamma levels following excavation and backfilling of the area are within the limits prescribed by DOE radiological guidelines. 12 refs., 6 figs., 8 tabs.

  6. Results of the radiological verification survey of the partial remediation at 90 Avenue C, Lodi, New Jersey (LJ079V)

    SciTech Connect (OSTI)

    Foley, R.D.; Johnson, C.A.

    1994-02-01

    The property at 90 Avenue C, Lodi, New Jersey is one of the vicinity properties of the former Maywood Chemical Works, Maywood, New Jersey designated for remedial action by the US Department of Energy (DOE). In July 1991, Bechtel National, Inc. performed a partial remedial action on this property. At the request of DOE, a team from Oak Ridge National Laboratory conducted an independent radiological verification survey in July, 1991 at this site. The purpose of the verification survey was to ensure the effectiveness of remedial actions performed within FUSRAP and to confirm the site`s compliance with DOE guidelines. The radiological survey included surface gamma scans indoors and outdoors, ground-level beta-gamma measurements, and systematic and biased soil and material sampling. Results of the verification survey demonstrated that all radiological measurements on the portions of the property that had been remediated were within DOE guidelines. However, there still remains a portion of the property to be remediated that is not covered by this verification survey.

  7. Results of the independent radiological verification survey at the former Bridgeport Brass Company Facility, Seymour, Connecticut (SSC001)

    SciTech Connect (OSTI)

    Foley, R.D.; Rice, D.E.; Allred, J.F.; Brown, K.S.

    1995-03-01

    At the request of the USDOE, a team from ORNL conducted an independent radiological verification survey at the former Bridgeport Brass Company Facility, Seymour, Connecticut, from September 1992 to March 1993. Purpose of the survey was to determine whether residual levels of radioactivity inside the Ruffert Building and selected adjacent areas were rmediated to levels below DOE guidelines for FUSRAP sites. The property was contaminated with radioactive residues of {sup 238}U from uranium processing experiments conducted by Reactive Metals, Inc., from 1962 to 1964 for the Atomic Energy Commission. A previous radiological survey did not characterize the entire floor space because equipment which could not be moved at the time made it inaccessible for radiological surveys. During the remediation process, additional areas of elevated radioactivity were discovered under stationary equipment, which required additional remediation and further verification. Results of the independent radiological verification survey confirm that, with the exception of the drain system inside the building, residual uranium contamination has been remediated to levels below DOE guidelines for unrestricted release of property at FUSRAP sites inside and outside the Ruffert Building. However, certain sections of the drain system retain uranium contamination above DOE surface guideline levels. These sections of pipe are addressed in separate, referenced documentation.

  8. Results of the Independent Radiological Verification Survey of the B Ditch at DuPont Chambers Works, Deepwater, New Jersey (DNJ001V)

    SciTech Connect (OSTI)

    Johnson, C.A.; Murray, M.E.

    1998-12-01

    This report documents the results of a radiological verification survey conducted at the Chambers Works of the E. I. DuPont Company in Deepwater, New Jersey by a team from the Oak Ridge National Laboratory (ORNL) in response to the Department of Energy's (DOE) Environmental Restoration Program requirements. The survey was to confirm that radioactive residuals previously identified in a portion of a central drainage ditch (the B Ditch) had been remediated to bring that portion of the property into compliance with current U.S. Department of Energy guidelines. The survey was conducted in the spring of 1997 in conjunction with DuPont's remediation and stabilization of the B Ditch to remove elevated levels of 2,4-dinitrotoluene and organic lead compounds. Portions of this ditch were located in an area where former Manhattan Engineering District of the Atomic Energy Commission work was conducted, and an independent verification survey was taken to ensure that this area had been remediated to radionuclide concentrations and activity levels below the applicable guideline limits. The survey included directly measured radiation levels and soil analysis to determine concentrations of uranium, and to compare these data to applicable guidelines. The results of the independent verification survey on this property demonstrate that the remediated and surveyed section of the B Ditch at the DuPont Chambers Works, Deepwater, New Jersey, successfully meets remedial action objectives, and radiological measurements in that portion of the property fall below the limits prescribed by radiological guidelines established for this site.

  9. Results of the Independent Radiological Verification Survey of Remediation at Building 31, Former Linde Uranium Refinery, Tonawanda, New York (LI001V)

    SciTech Connect (OSTI)

    McKenzie, S.P.; Uziel, M.S.

    1998-11-01

    As part of the Formerly Utilized Sites Remedial Action Progmq a team from Oak Ridge National Laboratory (ORNL) conducted a radiological veriihtion survey of Building 31 at the former Linde Uranium Refinery, Tonawau& New York. The purpose of the survey was to ver@ that remedial action completed by the project management contractor had reduced contamination levels to within authorized limits. Prior to remediatioq tied radioactive material was prevalent throughout the building and in some of the ductwork Decontaminadon consisted of removing surfhce contamination from floors, baseboards, and overhead areas; removing some air ducts; and vacuuming dust. Building 31 at the former Linde site in TonawandA New Yorlq was thoroughly investigated inside and outside for radionuclide residues. The verification team discovered previously undetected contaminadon beneath the concrete pad on the first floor and underneath floor tiles on the second floor. All suspect floor tiles were removed and any contamination beneath them cleaned to below guideline levels. The verification team also discovered elevated radiation levels associated with overhead air lines that led to the eventual removal of the entire air lige and a complete investigation of the history of all process piping in the building. Final verification surveys showed that residual surface beta-gamma activity levels were slightly elevated in some places but below U.S. Department of Energy applicable guidelines for protection against radiation (Table 1). Similarly, removable radioactive contamination was also below applicable guidelines. Exposure rates within the building were at typical background levels, and no consistently elevated indoor radon concentrations were measured. However, radionuclide analysis of subsurface soil from beneath the concrete floor on the ground level showed concentrations of `*U and'% that exceeded applicable guidelines. At the time of this survey, there was no measured exposure pathway for this

  10. radiological. survey | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    survey NNSA to Conduct Aerial Radiological Surveys Over San Francisco, Pacifica, Berkeley, And Oakland, CA Areas A U.S. Department of Energy National Nuclear Security...

  11. Independent Verification Survey Report for the Operable Unit-1 Miamisburg Closure Project, Miamisburg, OH

    SciTech Connect (OSTI)

    Weaver, P.

    2008-03-17

    The objectives of the independent verification survey were to confirm that remedial actions have been effective in meeting established release criteria and that documentation accurately and adequately describes the current radiological and chemical conditions of the MCP site.

  12. radiological survey | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    radiological survey San Francisco Bay Area Aerial Radiation Assessment Survey (SAN JOSE and SAN FRANCISCO, California) - A helicopter may be seen flying at low altitudes over portions of the San Francisco Bay Area from January 29 through February 6, 2016. The purpose of the flyovers is to measure naturally occurring background radiation. Officials from the National Nuclear... NNSA to Conduct Aerial Radiological Surveys Over Washington, D.C. and Baltimore, MD Areas WASHINGTON, D.C. AND BALTIMORE,

  13. Radiological Scoping Survey of the Scotia Depot, Scotia, NY

    SciTech Connect (OSTI)

    Bailey, E. N.

    2008-02-25

    The objectives of the radiological scoping survey were to collect adequate field data for use in evaluating the radiological condition of Scotia Depot land areas, warehouses, and support buildings.

  14. SQA_CodeVerification_Survey_FINAL

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Survey o f S oftware Q uality Assurance a nd Code Verification Practices i n CASL Michael P ernice Idaho N ational L aboratory Matt S ieger Oak R idge N ational Laboratory March 26, 2 013 INL/EXT-13-28675 CASL-U-2013-0079-000 CASL-U-2013-0079-000 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal

  15. Verification Survey of the Building 315 Zero Power Reactor-6 Facility, Argonne National Laboratory-East, Argonne, Illinois

    SciTech Connect (OSTI)

    W. C. Adams

    2007-05-25

    Oak Ridge Institute for Science and Education (ORISE) conducted independent verification radiological survey activities at Argonne National Laboratory’s Building 315, Zero Power Reactor-6 facility in Argonne, Illinois. Independent verification survey activities included document and data reviews, alpha plus beta and gamma surface scans, alpha and beta surface activity measurements, and instrumentation comparisons. An interim letter report and a draft report, documenting the verification survey findings, were submitted to the DOE on November 8, 2006 and February 22, 2007, respectively (ORISE 2006b and 2007).

  16. Autonomous mobile robot for radiologic surveys

    DOE Patents [OSTI]

    Dudar, Aed M.; Wagner, David G.; Teese, Gregory D.

    1994-01-01

    An apparatus for conducting radiologic surveys. The apparatus comprises in the main a robot capable of following a preprogrammed path through an area, a radiation monitor adapted to receive input from a radiation detector assembly, ultrasonic transducers for navigation and collision avoidance, and an on-board computer system including an integrator for interfacing the radiation monitor and the robot. Front and rear bumpers are attached to the robot by bumper mounts. The robot may be equipped with memory boards for the collection and storage of radiation survey information. The on-board computer system is connected to a remote host computer via a UHF radio link. The apparatus is powered by a rechargeable 24-volt DC battery, and is stored at a docking station when not in use and/or for recharging. A remote host computer contains a stored database defining paths between points in the area where the robot is to operate, including but not limited to the locations of walls, doors, stationary furniture and equipment, and sonic markers if used. When a program consisting of a series of paths is downloaded to the on-board computer system, the robot conducts a floor survey autonomously at any preselected rate. When the radiation monitor detects contamination, the robot resurveys the area at reduced speed and resumes its preprogrammed path if the contamination is not confirmed. If the contamination is confirmed, the robot stops and sounds an alarm.

  17. Autonomous mobile robot for radiologic surveys

    DOE Patents [OSTI]

    Dudar, A.M.; Wagner, D.G.; Teese, G.D.

    1994-06-28

    An apparatus is described for conducting radiologic surveys. The apparatus comprises in the main a robot capable of following a preprogrammed path through an area, a radiation monitor adapted to receive input from a radiation detector assembly, ultrasonic transducers for navigation and collision avoidance, and an on-board computer system including an integrator for interfacing the radiation monitor and the robot. Front and rear bumpers are attached to the robot by bumper mounts. The robot may be equipped with memory boards for the collection and storage of radiation survey information. The on-board computer system is connected to a remote host computer via a UHF radio link. The apparatus is powered by a rechargeable 24-volt DC battery, and is stored at a docking station when not in use and/or for recharging. A remote host computer contains a stored database defining paths between points in the area where the robot is to operate, including but not limited to the locations of walls, doors, stationary furniture and equipment, and sonic markers if used. When a program consisting of a series of paths is downloaded to the on-board computer system, the robot conducts a floor survey autonomously at any preselected rate. When the radiation monitor detects contamination, the robot resurveys the area at reduced speed and resumes its preprogrammed path if the contamination is not confirmed. If the contamination is confirmed, the robot stops and sounds an alarm. 5 figures.

  18. Radiological survey of San Diego Bay

    SciTech Connect (OSTI)

    Semler, M.O.; Blanchard, R.L.

    1989-06-01

    A radiological survey of three sites in San Diego Bay provided the basis for the following conclusions: 1. Small quantities of Co-60 (0.02-0.05 pCi/g) are present in the bottom sediments in some areas of the harbor at the Submarine Base. Most, if not all, of the Co-60 contamination present probably originated prior to the earlier 1967 survey that reported Co-60 levels as much as 300 times larger than those observed in this study. The highest Co-60 concentration measured is now less than one percent of the normal background radioactivity in harbor sediment samples. 2. No tritium or gamma-ray emitters, other than trace amounts of those occurring naturally, were detected in surface water from the dock areas or in nearby drinking water supplies. 3. Only radionuclides of natural origin and trace amounts of Cs-137 from fallout of previous nuclear weapons tests were detected in samples of kelp, algae, and fish taken from the harbor at the Submarine Base. 4. Gamma-ray surveys of the harbors near the docking areas and along shorelines and beaches near the shipyards failed to detect any exposure rates above background. 3 refs., 4 figs., 3 tabs.

  19. Final Report - Independent Verification Survey Report for the Waste Loading Area, Former Hazardous Waste Management Facility, Brookhaven National Laboratory, Upton, New York

    SciTech Connect (OSTI)

    P.C. Weaver

    2008-08-19

    The objective of the verification survey was to obtain evidence by means of measurements and sampling to confirm that the final radiological conditions were less than the established release criteria. This objective was achieved via multiple verification components including document reviews to determine the accuracy and adequacy of FSS documentation.

  20. Final Report Independent Verification Survey of the High Flux Beam Reactor, Building 802 Fan House Brookhaven National Laboratory Upton, New York

    SciTech Connect (OSTI)

    Harpeneau, Evan M.

    2011-06-24

    On May 9, 2011, ORISE conducted verification survey activities including scans, sampling, and the collection of smears of the remaining soils and off-gas pipe associated with the 802 Fan House within the HFBR (High Flux Beam Reactor) Complex at BNL. ORISE is of the opinion, based on independent scan and sample results obtained during verification activities at the HFBR 802 Fan House, that the FSS (final status survey) unit meets the applicable site cleanup objectives established for as left radiological conditions.

  1. Survey of Existing Tools for Formal Verification.

    SciTech Connect (OSTI)

    Punnoose, Ratish J.; Armstrong, Robert C.; Wong, Matthew H.; Jackson, Mayo

    2014-12-01

    Formal methods have come into wide use because of their effectiveness in verifying "safety and security" requirements of digital systems; a set of requirements for which testing is mostly ineffective. Formal methods are routinely used in the design and verification of high-consequence digital systems in industry. This report outlines our work in assessing the capabilities of commercial and open source formal tools and the ways in which they can be leveraged in digital design workflows.

  2. A survey of films for use as dosimeters in interventional radiology

    SciTech Connect (OSTI)

    Fajardo, L.C.; Geise, R.A.; Ritenour, E.R.

    1995-04-01

    Analysis of radiation doses in interventional radiological procedures that can lead to deterministic radiation effects such as erythema and epilation would assist physicians in planning patient care after exposure and in reducing doses. Photographic films used to measure skin exposure in the past are too sensitive for the high doses involved in interventional procedures. Seventeen different types of films, many of which are generally available in hospitals, were surveyed to see if any would meet the demands of interventional radiology. Sensitometric curves obtained demonstrate that most films are inappropriate for high dose procedures. Using Kodak Fine Grain Positive and Deupont duplicating films and automatic processing, doses as high as 2.8 Gy could be measured with reasonable accuracy. Similar results can be obtained by manually processing Kodak XV-2 verification film at room temperature.

  3. Interim Letter Report - Verification Survey of Partial Grid E9, David Witherspoon, Inc. 1630 Site Knoxville, Tennessee

    SciTech Connect (OSTI)

    P.C. Weaver

    2008-06-12

    Conduct verification surveys of available grids at the DWI 1630 in Knoxville, Tennessee. A representative with the Independent Environmental Assessment and Verification (IEAV) team from ORISE conducted a verification survey of a partial area within Grid E9.

  4. Verification survey report of the south waste tank farm training/test tower and hazardous waste storage lockers at the West Valley demonstration project, West Valley, New York

    SciTech Connect (OSTI)

    Weaver, Phyllis C.

    2012-08-29

    A team from ORAU's Independent Environmental Assessment and Verification Program performed verification survey activities on the South Test Tower and four Hazardous Waste Storage Lockers. Scan data collected by ORAU determined that both the alpha and alpha-plus-beta activity was representative of radiological background conditions. The count rate distribution showed no outliers that would be indicative of alpha or alpha-plus-beta count rates in excess of background. It is the opinion of ORAU that independent verification data collected support the site?s conclusions that the South Tower and Lockers sufficiently meet the site criteria for release to recycle and reuse.

  5. VERIFICATION SURVEY OF THE BAKER AND WILLIAMS WAREHOUSES

    Office of Legacy Management (LM)

    ,~ *-,-' .r_~, VERIFICATION SURVEY OF THE BAKER AND WILLIAMS WAREHOUSES BUILDING 513-519 NEW YORK, NEW YORK Prepared by W. C. Adams Environmental Survey and Site Assessment Program Energy/Environment Systems Division Oak Ridge Institute for Science and Education Oak Ridge, Tennessee 37831-0117 Prepared for the Office of Environmental Restoration U.S. Department of Energy FINAL REPORT JUNE 1994 This report is based on work performed under contract number DE-AC05-760R00033 with the U.S. Department

  6. NNSA to Conduct Aerial Radiological Surveys Over San Francisco, Pacifica,

    National Nuclear Security Administration (NNSA)

    Berkeley, And Oakland, CA Areas | National Nuclear Security Administration | (NNSA) Conduct Aerial Radiological Surveys Over San Francisco, Pacifica, Berkeley, And Oakland, CA Areas August 27, 2015 A U.S. Department of Energy National Nuclear Security Administration (NNSA) helicopter may be seen flying at low altitudes around the California Bay Area from September 1 - 6, 2015. The purpose of the flyovers is to measure naturally occurring background radiation. A twin-engine Bell 412

  7. INDEPENDENT VERIFICATION SURVEY REPORT OPERABLE UNIT-1 LANDFILL TRENCHES, MIAMISBURG CLOSURE PROJECT

    SciTech Connect (OSTI)

    W.C. Adams

    2010-07-21

    INDEPENDENT VERIFICATION SURVEY REPORT FOR THE OPERABLE UNIT-1 LANDFILL TRENCHES, MIAMISBURG CLOSURE PROJECT, MIAMISBURG, OHIO DCN: 0468-SR-03-0

  8. INDEPENDENT VERIFICATION SURVEY REPORT FOR THE OPERABLE UNIT-1 LANDFILL TRENCHES, MIAMISBURG CLOSURE PROJECT

    SciTech Connect (OSTI)

    W.C. Adams

    2010-05-24

    INDEPENDENT VERIFICATION SURVEY REPORT FOR THE OPERABLE UNIT-1 LANDFILL TRENCHES, MIAMISBURG CLOSURE PROJECT, MIAMISBURG, OHIO DCN: 0468-SR-02-0

  9. Northern Marshall Islands radiological survey: sampling and analysis summary

    SciTech Connect (OSTI)

    Robison, W.L.; Conrado, C.L.; Eagle, R.J.; Stuart, M.L.

    1981-07-23

    A radiological survey was conducted in the Northern Marshall Islands to document reamining external gamma exposures from nuclear tests conducted at Enewetak and Bikini Atolls. An additional program was later included to obtain terrestrial and marine samples for radiological dose assessment for current or potential atoll inhabitants. This report is the first of a series summarizing the results from the terrestrial and marine surveys. The sample collection and processing procedures and the general survey methodology are discussed; a summary of the collected samples and radionuclide analyses is presented. Over 5400 samples were collected from the 12 atolls and 2 islands and prepared for analysis including 3093 soil, 961 vegetation, 153 animal, 965 fish composite samples (average of 30 fish per sample), 101 clam, 50 lagoon water, 15 cistern water, 17 groundwater, and 85 lagoon sediment samples. A complete breakdown by sample type, atoll, and island is given here. The total number of analyses by radionuclide are 8840 for /sup 241/Am, 6569 for /sup 137/Cs, 4535 for /sup 239 +240/Pu, 4431 for /sup 90/Sr, 1146 for /sup 238/Pu, 269 for /sup 241/Pu, and 114 each for /sup 239/Pu and /sup 240/Pu. A complete breakdown by sample category, atoll or island, and radionuclide is also included.

  10. Letter Report - Verification Results for the Non-Real Property Radiological Release Program at the West Valley Demonstration Project, Ashford, New York

    SciTech Connect (OSTI)

    M.A. Buchholz

    2009-04-29

    The objective of the verification activities is to provide an independent review of the design, implementation, and performance of the radiological unrestricted release program for personal property, materials, and equipment (non-real property).

  11. Cosmic shear measurements with Dark Energy Survey Science Verification data

    DOE PAGES-Beta [OSTI]

    Becker, M. R.

    2016-07-06

    Here, we present measurements of weak gravitational lensing cosmic shear two-point statistics using Dark Energy Survey Science Verification data. We demonstrate that our results are robust to the choice of shear measurement pipeline, either ngmix or im3shape, and robust to the choice of two-point statistic, including both real and Fourier-space statistics. Our results pass a suite of null tests including tests for B-mode contamination and direct tests for any dependence of the two-point functions on a set of 16 observing conditions and galaxy properties, such as seeing, airmass, galaxy color, galaxy magnitude, etc. We use a large suite of simulationsmore » to compute the covariance matrix of the cosmic shear measurements and assign statistical significance to our null tests. We find that our covariance matrix is consistent with the halo model prediction, indicating that it has the appropriate level of halo sample variance. We also compare the same jackknife procedure applied to the data and the simulations in order to search for additional sources of noise not captured by the simulations. We find no statistically significant extra sources of noise in the data. The overall detection significance with tomography for our highest source density catalog is 9.7σ. Cosmological constraints from the measurements in this work are presented in a companion paper.« less

  12. Aerial radiological surveys of Steed Pond, Savannah River Site: Dates of surveys, 1984--1989

    SciTech Connect (OSTI)

    Fritzsche, A.E.; Jobst, J.E.

    1993-09-01

    From June 1984 to August 1985, three aerial radiological surveys were conducted over Steed Pond at the Savannah River Site in South Carolina. In addition, Steed Pond was included in larger-area surveys of the Savannah River Site in subsequent years. The surveys were conducted by the Remote Sensing Laboratory of EG&G Energy Measurements, Inc., Las Vegas, Nevada, for the US Department of Energy. Airborne measurements were obtained for both natural and man-made gamma radiation over Steed Pond and surrounding areas. The first survey was conducted when the pond was filled to normal capacity for the time of the year. On September 1, 1984, the Steed Pond dam spillway failed causing the pond to drain. The four subsequent surveys were conducted with the pond drained. The second survey and the third were conducted to study silt deposits exposed by the drop in water level after the spillway`s opening. Steed Pond data from the February 1987 and April 1989 Savannah River Site surveys have been included to bring this study up to date.

  13. Radiological re-survey results at 130 West Central Avenue, Maywood, New Jersey (MJ029)

    SciTech Connect (OSTI)

    Murray, M.E.; Johnson, C.A.

    1994-01-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from 1916 to 1959. During the early years of operation, MCW stored wastes and residues in low-lying areas west of the processing facilities and consequently some of the residuals containing radioactive materials migrated offsite to the surrounding area. Subsequently, the U.S. Department of Energy (DOE), designated for remedial action the old MCW property and several vicinity properties. Additionally, in 1984, the property at 130 West Central Ave., Maywood, New Jersey and properties in its vicinity were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. In 1987 and 1988, at the request of DOE, ORNL conducted a radiological survey on this property. A second radiological survey by ORNL was conducted on this property in May, 1993 at the request of DOE after an ad hoc radiological survey, requested by a new property owner and conducted by Bechtel National, Inc. (BNI), identified some contamination not previously found by ORNL. The purpose of the survey was to determine if residuals from the old MCW were present on the property, and if so, if any radiological elements present were above guidelines. A certified civil survey was requisitioned by ORNL to determine actual property boundaries before beginning the radiological survey. The radiological re-survey included a surface gamma scan and the collection of a large number of soil samples for radionuclide analyses.

  14. Radiological survey report for the Weldon Spring Raffinate Pits site, Weldon Spring, Missouri

    SciTech Connect (OSTI)

    Not Available

    1984-08-01

    The Weldon Spring Site (WSS) is a US Department of Energy (DOE) surplus facility comprising the Raffinate Pits facility, the Quarry, and potentially contaminated vicinity properties. Radiological characterization of the WSS will be conducted in three phases: the Raffinate Pits facility, Quarry, and the vicinity properties. Bechtel National, Inc. (BNI) and its radiological support subcontractor, Eberline Instrument Corporation (EIC), conducted a radiological characterization survey of the Raffinate Pits during 1982 and 1983 in support of on-site construction work and a technical evaluation of site geology. The survey consisted of direct beta-gamma surface readings, near-surface gamma readings, exposure level measurements, and gamma-logs of boreholes. Soil samples were also collected from the surface, shallow boreholes, and trenches on the site. This report describes the radiological characterization of the Raffinate Pits facility, the procedures used to conduct the survey, the survey results, and their significance. 5 references, 9 figures, 8 tables.

  15. COT"IPREITENS IVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY P NIAGARA...

    Office of Legacy Management (LM)

    COT"IPREITENS IVE RADIOLOGICAL SURVEY OFF-SITE PROPERTY P NIAGARA FALIS STORAGE SITE LEWISTON, NEW YORK Prepared for U.S. DePartment of EnergY as part of the Formerly Utilized ...

  16. Radiological survey of Johnston Atoll. Dates of survey: April-August 1980. Revision 1

    SciTech Connect (OSTI)

    Jaffe, R.J.; Tipton, W.J.

    1982-04-01

    A radiological survey was conducted over all land areas of Johnston Atoll between April and August 1980. The survey was performed to locate and quantify residual surface transuranic (i.e., plutonium and americium) contamination resulting from three THOR missile aborts which occurred during that portion of the 1962 atmospheric nuclear testing series conducted by the United States from Johnston Island. A high purity germanium planar detector was utilized to enhance the detection sensitivity for the 59.5 keV gamma ray from /sup 241/Am. Results are reported as equivalent surface concentration in units of nCi/m/sup 2/. Conversion factors are also included for several other assumed source distributions. Soil samples were obtained to determine plutonium-to-americium ratios. 7 references, 14 figures, 1 table.

  17. Radiological Survey Results for Areas A1 North, A5A, A6, and B2 at the Molycorp Washington Remediation Project, Washington, Pennsylvania

    SciTech Connect (OSTI)

    W.C. Adams

    2007-03-13

    Perform radiological surveys of the Molycorp Washington Remediation Project (MWRP) facility in Washington, Pennsylvania

  18. INDEPENDENT VERIFICATION SURVEY REPORT FOR ZONE 1 OF THE EAST TENNESSEE TECHNOLOGY PARK IN OAK RIDGE, TENNESSEE

    SciTech Connect (OSTI)

    King, David A.

    2012-08-16

    Oak Ridge Associated Universities (ORAU) conducted in-process inspections and independent verification (IV) surveys in support of DOE's remedial efforts in Zone 1 of East Tennessee Technology Park (ETTP) in Oak Ridge, Tennessee. Inspections concluded that the remediation contractor's soil removal and survey objectives were satisfied and the dynamic verification strategy (DVS) was implemented as designed. Independent verification (IV) activities included gamma walkover surveys and soil sample collection/analysis over multiple exposure units (EUs).

  19. INDEPENDENT VERIFICATION SURVEY OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT OUTSIDE AREAS BROOKHAVEN NATIONAL LABORATORY UPTON, NEW YORK

    SciTech Connect (OSTI)

    P.C. Weaver

    2010-12-15

    5098-SR-03-0 FINAL REPORT- INDEPENDENT VERIFICATION SURVEY OF THE HIGH FLUX BEAM REACTOR DECOMMISSIONING PROJECT OUTSIDE AREAS, BROOKHAVEN NATIONAL LABORATORY

  20. Radiological survey results at 1 Shady Lane, Lodi, New Jersey (LJ095)

    SciTech Connect (OSTI)

    Foley, R.D.; Johnson, C.A.

    1995-07-01

    The US Department of Energy (DOE) conducted remedial action at the Stepan property in Maywood, New Jersey and several vicinity properties in Lodi, New Jersey as part of the Formerly Utilized Sites Remedial Action Program (FUSRAP). These properties are in the vicinity of the DOE-owned Maywood Interim Storage Site (MISS), adjacent to the former Maywood Chemical Works facility. The property at One Shady Lane, Lodi, New Jersey was not one of these vicinity properties but was surveyed by DOE at the request of the owner. At the request of DOE, a team from Oak Ridge National Laboratory conducted a radiological survey at this property. The purpose of the survey, conducted in November 1994, was to confirm whether remedial actions were to be performed on the property in order to be in compliance with the identified Guidelines. The radiological survey included surface gamma scans and gamma readings at 1 meter, and the collection of soil samples for radionuclide analysis. Results of the survey demonstrated that all radiological measurements on the property at One Shady Lane, Lodi, New Jersey, were comparable to background levels in the area, and well within the limits prescribed by DOE radiological guidelines. Based on the results of the radiological survey data, this property does not meet guidelines for inclusion under FUSRAP.

  1. Limitations Influencing Interventional Radiology in Canada: Results of a National Survey by the Canadian Interventional Radiology Association (CIRA)

    SciTech Connect (OSTI)

    O'Brien, Jeremy; Baerlocher, Mark Otto Asch, Murray R.; Hayeems, Eran; Kachura, John R.; Collingwood, Peter

    2007-09-15

    Purpose. To describe the current state and limitations to interventional radiology (IR) in Canada through a large, national survey of Canadian interventional radiologists. Methods. An anonymous online survey was offered to members of the Canadian Interventional Radiology Association (CIRA). Only staff radiologists were invited to participate. Results. Seventy-five (75) responses were received from a total of 247, giving a response rate of 30%. Respondents were split approximately equally between academic centers (47%) and community practice (53%), and the majority of interventional radiologists worked in hospitals with either 200-500 (49%) or 500-1,000 (39%) beds. Procedures listed by respondents as most commonly performed in their practice included PICC line insertion (83%), angiography and stenting (65%), and percutaneous biopsy (37%). Procedures listed as not currently performed but which interventional radiologists believed would benefit their patient population included radiofrequency ablation (36%), carotid stenting (34%), and aortic stenting (21%); the majority of respondents noted that a lack of support from referring services was the main reason for not performing these procedures (56%). Impediments to increasing scope and volume of practice in Canadian IR were most commonly related to room or equipment shortage (35%), radiologist shortage (33%), and a lack of funding or administrative support (28%). Conclusion. Interventional radiology in Canada is limited by a number of factors including funding, manpower, and referral support. A concerted effort should be undertaken by individual interventional radiologists and IR organizations to increase training capacity, funding, remuneration, and public exposure to IR in order to help advance the subspecialty.

  2. ORNL/luSA-85/6 Health and Safety Research Division PRELIMINARY RADIOLOGICAL SURVEY OF TEE FORMER HAVENS PLANT

    Office of Legacy Management (LM)

    luSA-85/6 Health and Safety Research Division PRELIMINARY RADIOLOGICAL SURVEY OF TEE FORMER HAVENS PLANT OF TEE BRIDGEPORT BRASS COMPANY, BRIDGEPORT, CONNECTICUT May 1985 Work performed as part of the RADIOLOGICAL SURVEY ACCIVITIES PROGRAM OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37831 operated by MARTIN MARIETTA ENERGY SYSTEMS, INC. for the U. S. DEPARTMENT OF ENERGY under Contract No. DE-AC05-840R21400 \ .-l__--.-- -- PRELIMINARY RADIOLOGICAL SURVEY OF THE FORMER HAVENS PLAEJT OF THE

  3. RADIOLOGICAL SURVEY OF A PORTION OF PROPERTY OWNED BY MODERN...

    Office of Legacy Management (LM)

    for the DEPARTMENT OF ENERGY as part of the Formerly ... Figure Page 1 Plan view of Former AEC Storage Site Showing ... Survey Techniques A survey grid system (100-ft spacing) was ...

  4. Radiological survey results at 14 Cliff Street, Beverly, Massachusetts (VB011)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.

    1992-08-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at 14 Cliff Street, Beverly, Massachusetts. The survey was performed in May 1991. The purpose of the survey was to determine if uranium dust from work performed under government contract at the former Ventron facility had migrated off-site to neighboring areas. The survey included a surface gamma scan and the collection of soil samples for radionuclide analyses. Results of the survey demonstrated no radionuclide concentrations or radiation measurements in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines.

  5. Radiological re-survey results at 146 West Central Avenue, Maywood, New Jersey (MJ034)

    SciTech Connect (OSTI)

    Murray, M.E.; Johnson, C.A.

    1994-05-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from 1916 to 1959. During the early years of operation, MCW stored wastes and residues in low-lying areas west of the processing facilities and consequently some of the residuals containing radioactive materials migrated offsite to the surrounding area. Subsequently, the U.S. Department of Energy (DOE) designated for remedial action the old MCW property and several vicinity properties. Additionally, in 1984, the property at 146 West Central Ave., Maywood, New Jersey and properties in its vicinity were included as a decontamination research and development project under the DOE Formerly Utilized Sites Remedial Action Program. In 1987 and 1988, at the request of DOE, Oak Ridge National Laboratory (ORNL) conducted a radiological survey on this property. A report describing this survey was published in 1989. A second radiological survey by ORNL was conducted on this property in May 1993 at the request of DOE after an ad hoc radiological survey, requested by the property owner and conducted by Bechtel National, Inc. (BNI), identified some contamination not previously found by ORNL. The purpose of the second ORNL survey was to determine whether radioactive materials from the old MCW were present on the property, and if so, if radioactive materials present were above guidelines. A certified civil survey was requisitioned by ORNL to determine actual property boundaries before beginning the radiological re-survey. The re-survey included a surface gamma scan and the collection of a large number of soil samples for radionuclide analyses. Results of this survey demonstrated that although elevated residual thorium-232 contamination was present in a few isolated spots on the southern end of the backyard, it did not exceed DOE guidelines.

  6. Radiological Final Status Survey of the Hammond Depot, Hammond, Indiana

    SciTech Connect (OSTI)

    T.J. Vitkus

    2008-04-07

    ORISE conducted extensive scoping, characterization, and final status surveys of land areas and structures at the DNSC’s Hammond Depot located in Hammond, Indiana in multiple phases during 2005, 2006 and 2007.

  7. 2016 Annual Inspection and Radiological Survey Results for the Piqua, Ohio, Decommissioned Reactor Site

    Office of Legacy Management (LM)

    Radiological Survey Results for the Piqua, Ohio, Decommissioned Reactor Site July 2016 LMS/PIQ/S14427 This page intentionally left blank U.S. Department of Energy 2016 Annual Inspection - Piqua, OH, Decommissioned Reactor Site July 2016 Doc. No. S14427 Page i Contents Abbreviations .................................................................................................................................. ii Summary

  8. Independent Verification Survey of the Clean Coral Storage Pile at the Johnston Atoll Plutonium Contaminated Soil Remediation Project

    SciTech Connect (OSTI)

    Wilson-Nichols, M.J.; Egidi, P.V.; Roemer, E.K.; Schlosser, R.M.

    2000-09-01

    f I The Oak Ridge National Laboratory (ORNL) Environmental Technology Section conducted an independent verification (IV) survey of the clean storage pile at the Johnston Atoll Plutonium Contaminated Soil Remediation Project (JAPCSRP) from January 18-25, 1999. The goal of the JAPCSRP is to restore a 24-acre area that was contaminated with plutonium oxide particles during nuclear testing in the 1960s. The selected remedy was a soil sorting operation that combined radiological measurements and mining processes to identify and sequester plutonium-contaminated soil. The soil sorter operated from about 1990 to 1998. The remaining clean soil is stored on-site for planned beneficial use on Johnston Island. The clean storage pile currently consists of approximately 120,000 m3 of coral. ORNL conducted the survey according to a Sampling and Analysis Plan, which proposed to provide an IV of the clean pile by collecting a minimum number (99) of samples. The goal was to ascertain wi th 95% confidence whether 97% of the processed soil is less than or equal to the accepted guideline (500-Bq/kg or 13.5-pCi/g) total transuranic (TRU) activity.

  9. VERIFICATION SURVEY OF PHASE I REMEDIAL ACTIONS ALBANY RESEARCH CENTER

    Office of Legacy Management (LM)

    SURVEY OF PHASE I REMEDIAL ACTIONS ALBANY RESEARCH CENTER ALBANY, OREGON Prepared by T. J. Vitkus Environmental Survey and Site Assessment Program Energy/Environment Systems Division Oak Ridge Associated Universities Oak Ridge, TN 37831-0117 Project Staff E. A. Powell R. B. Slaten Prepared for U.S. Department of Energy INTERIM REPORT I MARCH 1991 This report is based on work performed under contract number DE-AC05-760R00033 with the U.S. Department of Energy. This draft report has not been given

  10. VERIFICATION SURVEY ACTIVITIES IN FS SURVEY UNITS 7, 8, 9, 10, 11, 13 & 14 AT THE SEPARATIONS PROCESS RESEARCH UNIT

    SciTech Connect (OSTI)

    M.G. JADICK

    2010-05-26

    FINAL INTERIM REPORT VERIFICATION SURVEY ACTIVITIES IN FINAL STATUS SURVEY UNITS 7, 8, 9, 10, 11, 13 AND 14 AT THE SEPARATIONS PROCESS RESEARCH UNIT, Niskayuna, New York 0496-SR-03-0. The Separations Process Research Unit (SPRU) facilities were constructed in the late 1940s to research the chemical separation of plutonium and uranium. SPRU operated between February 1950 and October 1953. The research activities ceased following the successful development of the reduction/oxidation and plutonium/uranium extraction processes that were subsequently used by the Hanford and the Savannah River sites.

  11. Results of the radiological survey at Two Mile Creek, Tonawanda, New York (TNY002)

    SciTech Connect (OSTI)

    Murray, M.E.; Rodriguez, R.E.; Uziel, M.S.

    1997-08-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at Two Mile Creek, Tonawanda, New York. The survey was performed in November 1991 and May 1996. The purpose of the survey was to determine if radioactive materials from work performed under government contract at the Linde Air Products Division of Union Carbide Corporation, Tonawanda, New York, had been transported into the creek. The survey included a surface gamma scan in accessible areas near the creek and the collection of soil, sediment, and core samples for radionuclide analyses. Survey results indicate that no significant material originating at the Linde plant is presently in the creek. Three of the 1991 soil sample locations on the creek bank and one near the lake contained slightly elevated concentrations of {sup 238}U with radionuclide distributions similar to that found in materials resulting from former processing activities at the Linde site.

  12. Results of the radiological survey at State Route 17 Becker Avenue, Maywood, New Jersey (MJ033)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.

    1990-03-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. 5 refs., 2 figs., 3 tabs.

  13. An Aerial Radiological Survey of the Portsmouth Gaseous Diffusion Plant and Surrounding Area, Portsmouth, Ohio

    SciTech Connect (OSTI)

    Namdoo Moon

    2007-12-01

    An aerial radiological survey was conducted over the 16 square-mile (~41 square-kilometer) area surrounding the Portsmouth Gaseous Diffusion Plant. The survey was performed in August 2007 utilizing a large array of helicopter mounted sodium iodide detectors. The purpose of the survey was to update the previous radiological survey levels of the environment and surrounding areas of the plant. A search for a missing radium-226 source was also performed. Implied exposure rates, man-made activity, and excess bismuth-214 activity, as calculated from the aerial data are presented in the form of isopleth maps superimposed on imagery of the surveyed area. Ground level and implied aerial exposure rates for nine specific locations are compared. Detected radioisotopes and their associated gamma ray exposure rates were consistent with those expected from normal background emitters. At specific plant locations described in the report, man-made activity was consistent with the operational histories of the location. There was no spectral activity that would indicate the presence of the lost source.

  14. Results of the radiological survey of the Excelsior Steel Ball Company, Tonawanda, New York (TNY005)

    SciTech Connect (OSTI)

    McKenzie, S.P.; Brown, K.S.

    1998-07-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted two radiological surveys of property belonging to the Excelsior Steel Ball Company, which is surrounded on three sides by the former site of the Linde Uranium Refinery, Tonawanda, New York. The surveys were performed in September 1997 and February 1998. The purpose of the first survey was to determine if radioactive residuals were present from previous activities at the former Linde site. The Linde Air Products Division of Union Carbide Corporation, Tonawanda, New York, had used radioactive materials at that location for work performed under government contract from 1942 through 1948. The purpose of the second survey was to collect additional biased samples from an area of the site where biased sample results showed slightly elevated levels of thorium-232.

  15. Results of the Radiological Survey of the Iowa Army Ammunition Plant, Middletown, Iowa

    SciTech Connect (OSTI)

    Murray, M.E.

    2001-07-17

    At the request of the U.S. Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted an indoor radiological survey of property at the Iowa Army Ammunition Plant (IAAAP), Middletown, Iowa in June 2000. The purpose of the survey was to determine if radioactive residuals resulting from previous Atomic Energy Commission (AEC) activities were present inside selected Line 1 buildings at the IAAAP and conduct sampling in those areas of previous AEC operations that utilized radioactive components at some point during the manufacturing process, in order to evaluate any possible immediate health hazards and to collect sufficient information to determine the next type of survey. The AEC occupied portions of IAAAP from 1947 to 1975 to assemble nuclear weapons. The surveyed areas were identified through interviews with current and former IAAAP employees who had worked at the plant during AEC's tenure, and from AEC records.

  16. Results of the radiological survey at 205 Main Street, Lodi, New Jersey (LJ075)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.; Floyd, L.M.; Crutcher, J.W.

    1989-08-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 205 Main Street, Lodi, New Jersey (LJ075), was conducted during 1987 and 1988. Results of the survey indicated radioactivity in the range of normal background for the northern New Jersey area. Radiological assessments of soil samples from the site demonstrate no radionuclide concentrations in excess of DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 21 figs., 3 tabs.

  17. radiological survey

    National Nuclear Security Administration (NNSA)

    application of nuclear science. NNSA maintains and enhances the safety, security, reliability and performance of the U.S. nuclear weapons stockpile without nuclear testing;...

  18. Nevada Test Site Area 25, Radiological Survey and Cleanup Project, 1974-1983 (a revised final report). Revision 1

    SciTech Connect (OSTI)

    Miller, M.G.

    1984-12-01

    This report describes the radiological survey, decontamination and decommissioning (D and D) of the Nevada Test Site (NTS) Area 25 facilities and land areas incorporated in the Nuclear Rocket Development Station (NRDS). Buildings, facilities and support systems used after 1959 for nuclear reactor and engine testing were surveyed for the presence of radioactive contamination. The radiological survey portion of the project encompassed portable instrument surveys and removable contamination surveys (swipe) for beta plus gamma and alpha radioactive contamination of facilities, equipment and land areas. Soil sampling was also accomplished. The majority of Area 25 facilities and land areas have been returned to unrestricted use. Remaining radiologically contaminated areas are posted with warning signs and barricades. 9 references, 23 figures.

  19. Interim Letter Report - Verification Survey of 19 Grids in the Lester Flat Area, David Witherspoon Inc. 1630 Site Knoxville, Tennessee

    SciTech Connect (OSTI)

    P.C. Weaver

    2008-10-17

    Perform verification surveys of 19 available grids located in the Lester Flat Area at the Davod Witherspoon Site. The survey grids included E11, E12, E13, F11, F12, F13, F14, F15, G15, G16, G17, H16, H17, H18, X16, X17, X18, K16, and J16.

  20. Radiological Survey Results for the Niagara Mohawk Right-of-Way, Tonawanda, New York (TNY004)

    SciTech Connect (OSTI)

    McKenzie, S.P.; Uziel, M.S.

    1998-11-01

    At the request of the U.S. Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey of a small portion of the Niagara Mohawk Power Corporation right-of-way in Tonawanda, New York. The purpose of the survey was to determine if radioactive residuals had migrated from or been redistributed onto the Niagara Mohawk right-of-way from the former Linde property to the west. The Linde Air Products Division of Union Carbide Corporation, Tonawanda New York, had used radioactive materials at that location for work performed under government contract from 1942 through 1948. The survey was performed in May 1996 in response to Formerly Utilized Sites Remedial Action Program (FUSRAP) requirements. These requirements dictate that the radiological status of certain vicinity properties shall be assessed and documented according to prescribed procedures prior to certification of the property for release for unrestricted use. Such release can only be granted if the property is found to be within current applicable authorized limits. The survey included a gamma scan of accessible areas and the collection and radionuclide analysis of soil samples from the portion of right-of-way located east of the former Linde plant site and north of the railway spur entrance gate. Results of the survey indicate that radioactive material probably originating from the Linde plant is located on the Niagara Mohawk right-of-way in the area surveyed. Surface gamma exposure rates were elevated above typical background levels. Four scattered surface soil samples exceeded DOE guideline values for {sup 238}U, and 8 of 13 surface soil samples exceeded DOE guideline values for {sup 226}Ra. The radionuclide distribution in these samples was similar to that found in materials resulting from former processing activities at the Linde site. It is recommended that the property be designated for remedial action by DOE.

  1. Independent Verification Survey of the Clean Coral Storage Pile at the Johnston Atoll Plutonium-Contaminated Soil Remediation Project

    SciTech Connect (OSTI)

    Wilson-Nichols, M.J.

    2000-12-07

    The Oak Ridge National Laboratory (ORNL) Environmental Technology Section conducted an independent verification (IV) survey of the clean storage pile at the Johnston Atoll Plutonium Contaminated Soil Remediation Project (JAPCSRP) from January 18-25, 1999. The goal of the JAPCSRP is to restore a 24-acre area that was contaminated with plutonium oxide particles during nuclear testing in the 1960s. The selected remedy was a soil sorting operation that combined radiological measurements and mining processes to identify and sequester plutonium-contaminated soil. The soil sorter operated from about 1990 to 1998. The remaining clean soil is stored on-site for planned beneficial use on Johnston Island. The clean storage pile currently consists of approximately 120,000 m{sup 3} of coral. ORNL conducted the survey according to a Sampling and Analysis Plan, which proposed to provide an IV of the clean pile by collecting a minimum number (99) of samples. The goal was to ascertain with 95% confidence whether 97% of the processed soil is less than or equal to the accepted guideline (500-Bq/kg or 13.5-pCi/g) total transuranic (TRU) activity. In previous IV tasks, ORNL has (1) evaluated and tested the soil sorter system software and hardware and (2) evaluated the quality control (QC) program used at the soil sorter plant. The IV has found that the soil sorter decontamination was effective and significantly reduced plutonium contamination in the soil processed at the JA site. The Field Command Defense Threat Reduction Agency currently plans to re-use soil from the clean pile as a cover to remaining contamination in portions of the radiological control area. Therefore, ORNL was requested to provide an IV. The survey team collected samples from 103 random locations within the top 4 ft of the clean storage pile. The samples were analyzed in the on-site radioanalytical counting laboratory with an American Nuclear Systems (ANS) field instrument used for the detection of low

  2. Radiological Survey Results for the R.P. Adams Company Property, Tonawanda, New York (TNY003)

    SciTech Connect (OSTI)

    Carrier, R.F.; McKenzie, S.P.; Uziel, M.S.

    1998-11-01

    At the request of the U.S. Department of Energy (DOE), a team horn Oak Ridge National Laboratory conducted a radiological survey of property belonging to the R P. Adarns Company, Inc., Tonawanda, New York. The survqy was performed in November 1995 and May and July 1996. The P-e of tie SUIWY was to determine if radioactive residuals had migrated, or been re&stribu@ from the former Linde property to the south onto the R P. Adams property. The Linde Air Products Division of Union Carbide Corporation, Toni~w~da, New York, had used radioactive materials at that location for work performed under government contract born 1942 through 1948. The survey was performed in response to Formerly Utilized Sites Remedial Action Program (FUSRAP) requirements. These requirements dictate that the radiological status of certain vicinity properties shall be assessed and docw.nented according to prescribed procedures prior to certification of the property for release for unrestricted use. Such release can only be granted if the property is found to be within current applicable authorized limits. The survey included a gamma scan of accessible areas in both the developed and the undeveloped portions of the property and the collection and radionuclide analysis of soil samples. A comparison of these data to the current DOE guidelines shows that all radionuclide concentrations and radioactivity levels found on the property are below the current guidelines. Therefore, this property should not be included in the FUSRAP program for remediation. xi

  3. Results of the radiological survey at the Granite City Steel facility, Granite City, Illinois

    SciTech Connect (OSTI)

    Swaja, R.E.; Cottrell, W.D.

    1990-07-01

    In the late 1950s and early 1960s, uranium ingots were x-rayed for the Atomic Energy Commission at the South Plant facility of the Granite City Steel Company, Granite City, Illinois. The x-ray equipment is still housed in a building on the southern end of the property. At the time of the survey, neither the equipment nor the building had been used for some time. It is the policy of the US Department of Energy (DOE) to verify that such sites are in compliance with current federal guidelines. Because documentation establishing the current radiological condition of the property is unavailable, a radiological survey was conducted by members of the Measurement Applications and Development Group of the Oak Ridge National Laboratory in March 1989. The survey included: measurement of gamma exposure rates both indoors and outdoors; collection and radionuclide analysis of soil and debris samples; and measurements to determine alpha and beta-gamma surface contamination. 3 refs., 12 figs., 3 tabs.

  4. An aerial radiological survey of the EG G Mound Applied Technologies and surrounding area, Miamisburg, Ohio

    SciTech Connect (OSTI)

    Not Available

    1992-11-01

    An aerial radiological survey was conducted over EG G Mound Applied Technologies, Miamisburg, Ohio, during the period of June 9--24, 1989. The purpose of the 41-square-kilometer (16-square-mile) survey was to document the terrestrial gamma environment of the plant and surrounding area. In addition, ground-based exposure rate measurements and soil samples were obtained to support the aerial data. An exposure rate contour map at 1 meter above ground level was.constructed from the gamma data and overlaid on an aerial photograph and map of the area. Exposure rates measured in the area typically ranged from 9 to 11 microroentgens per hour ([mu]R/h).

  5. Radiological surveys of properties in the Middlesex, New Jersey area. Final report

    SciTech Connect (OSTI)

    Leggett, R W; Haywood, F.F. Cottrell, W.D.

    1981-03-01

    Results of the radiological surveys conducted at three properties in the Middlesex, New Jersey area as well as one additional location downstream from the Middlesex Sampling Plant (Willow Lake), are presented. The survey revealed that the yard around the church rectory on Harris Avenue is contaminated with a /sup 226/Ra-bearing material, probably pitchblende ore from the former Middlesex Sampling Plant. The elevated /sup 226/Ra concentrations around and, to a lesser extent, underneath the rectory are leading to elevated /sup 222/Rn concentrations in air in the rectory and elevated alpha contamination levels (from radon daughters) on surfaces inside the rectory. External gamma radiation levels in the rectory yard are well above background levels, and beta-gamma dose rates at many points in the yard are above federal guidelines for the release of property for unrestricted use. The radiological survey of a parking lot at the Union Carbide plant in Bound Brook, New Jersey revealed that a nearly circular region of 50-ft diam in the lot showed above-background external gamma radiation levels. Two isolated spots within this region showed concentrations of uranium in soil above the licensable level stated in 10 CFR 40. Soil samples taken in the area of elevated gamma radiation levels generally showed nearly equal activities of /sup 226/Ra and /sup 238/U. The survey at the residences on William Street in Piscataway, revealed that the front yeard is generally contaminated from near the surface to a depth of 1.5 to 2.5 ft with /sup 226/Ra-bearing material, possibly pitchblende ore. The remainder of the yard shows scattered contaminaion. External gamma radiation levels inside the house are above the background level near some outside walls.

  6. Radiological survey results at the former Bridgeport Brass Company facility, Seymour, Connecticut

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.

    1993-06-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey of the former Bridgeport Brass Company facility, Seymour, Connecticut. The survey was performed in May 1992. The purpose of the survey was to determine if the facility had become contaminated with residuals containing radioactive materials during the work performed in the Ruffert building under government contract in the 1960s. The survey included a gamma scanning over a circumscribed area around the building, and gamma and beta-gamma scanning over all indoor surfaces as well as the collection of soil and other samples for radionuclide analyses. Results of the survey demonstrated radionuclide concentrations in indoor and outdoor samples, and radiation measurements over floor and wall surfaces, in excess of the DOE Formerly Utilized Sites Remedial Action Program guidelines. Elevated uranium concentrations outdoors were limited to several small, isolated spots. Radiation measurements exceeded guidelines indoors over numerous spots and areas inside the building, mainly in Rooms 1--6 that had been used in the early government work.

  7. An aerial radiological survey of the Fernald Environmental Management Project and surrounding area, Fernald, Ohio

    SciTech Connect (OSTI)

    Phoenix, K.A.

    1997-04-01

    An aerial radiological survey was conducted from May 17--22, 1994, over a 36 square mile (93 square kilometer) area centered on the Fernald Environmental Management Project located in Fernald, Ohio. The purpose of the survey was to detect anomalous gamma radiation in the environment surrounding the plant. The survey was conducted at a nominal altitude of 150 feet (46 meters) with a line spacing of 250 feet (76 meters). A contour map of the terrestrial gamma exposure rate extrapolated to 1 meter (3.3 feet) above ground was prepared and overlaid on an aerial photograph of the area. Analysis of the data for man made sources showed five sites within the boundaries of the Fernald Environmental Management Project having elevated readings. The exposure rates outside the plant boundary were typical of naturally occurring background radiation. Soil samples and pressurized ion chamber measurements were obtained at four locations within the survey boundaries to supplement the aerial data. It was concluded that although the radionuclides identified in the high-exposure-rate areas are naturally occurring, the levels encountered are greatly enhanced due to industrial activities at the plant.

  8. Results of the radiological survey at 5 Hancock Street, Lodi, New Jersey (LJ029)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 5 Hancock Street, Lodi, New Jersey (LJ029), was conducted during 1985 and 1986. Results of the survey demonstrated concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of the material originating from the MCW site. 5 refs., 6 figs., 3 tabs.

  9. Results of the radiological survey at 80 Industrial Road, Lodi, New Jersey (LJ061)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.; Floyd, L.M.; Crutcher, J.W.

    1989-07-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 80 Industrial Road, Lodi, New Jersey (LJ061), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of DOE remedial action criteria, primarily from the /sup 232/Th decay chain, with some contamination from /sup 226/Ra. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 11 figs., 3 tabs.

  10. Results of the radiological survey at 48 Schlosser Drive, Rochelle Park, New Jersey (RJ005)

    SciTech Connect (OSTI)

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956.MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from thisthorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy(DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally [sup 232]Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 48 Schlosser Drive, Rochelle Park, New Jersey (RJO05), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  11. Results of the radiological survey at 37 Schlosser Drive, Rochelle Park, New Jersey (RJ002)

    SciTech Connect (OSTI)

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 37 Schlosser Drive, Rochelle Park, New Jersey (RJ002), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  12. Results of the radiological survey at 28 Long Valley Road, Lodi, New Jersey (LJ047)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 28 Long Valley Road, Lodi, New Jersey (LJ047), was conducted during 1985, 1986, 1987. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the Survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 8 figs., 3 tabs.

  13. Results of the radiological survey at 27 Schlosser Drive, Rochelle Park, New Jersey (RJ004)

    SciTech Connect (OSTI)

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally [sup 232]Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 27 Schlosser Drive, Rochelle Park, New Jersey (RJ004), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  14. Results of the radiological survey at 30 Long Valley Road, Lodi, New Jersey (LJ045)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 30 Long Valley Road, Lodi, New Jersey (LJ045), was conducted during 1985, 1986, and 1987. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 10 figs., 3 tabs.

  15. Results of the radiological survey at 31 Schlosser Drive, Rochelle Park, New Jersey (RJ003)

    SciTech Connect (OSTI)

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally [sup 232]Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 31 Schlosser Drive, Rochelle Park, New Jersey (RJ003), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  16. Results of the radiological survey at 27 Schlosser Drive, Rochelle Park, New Jersey (RJ004)

    SciTech Connect (OSTI)

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 27 Schlosser Drive, Rochelle Park, New Jersey (RJ004), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  17. Results of the radiological survey at 90 C Avenue, Lodi, New Jersey (LJ079)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducted an investigative radiological survey during 1988 at 90 C Avenue, Lodi, New Jersey (LJ079), one of the properties in the vicinity of the MCW site. The survey included a gamma radiation scan of the surface and at one meter above the surface, as well as radionuclide sampling of surface and subsurface soil. The survey objective was to determine whether this site was contaminated with radioactive residues derived from MCW, principally /sup 232/Th. Results of the survey demonstrated radionuclide concentrations in excess of DOE remedial action criteria, primarily from the /sup 232/Th decay chain, with some contamination from /sup 226/Ra. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 3 figs., 3 tabs.

  18. Results of the radiological survey at 112 Avenue E, Lodi, New Jersey (LJ082)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residue, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 112 Avenue E, Lodi, New Jersey (LJ082), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 2 figs., 3 tabs.

  19. Review of radiological surveys of the General Services Administration's Raritan Depot in Edison, New Jersey

    SciTech Connect (OSTI)

    Herzenberg, C.L.; Winter, R.C.

    1986-10-01

    This report reviews two recent radiological surveys of the General Services Administration (GSA) Raritan Depot in Edison, New Jersey, that were conducted after somewhat elevated levels of radiation were detected within a depot building. The first survey indicated gamma radiation levels were higher than natural background levels in some buildings and identified the probable source of the radiation as gypsum-like building tiles that contained natural uranium-chain radionuclides at a level 20 times higher than other materials. Elevated levels of radon and radon decay products also were detected in some buildings. A follow-on survey was conducted to confirm the January measurements and to measure radiation levels at other locations: additional buildings at the depot, buildings on the Middlesex County College campus, and a possible outdoor disposal site. EPA measurements established that ceiling material is the primary source of the radiation. Radioisotope analysis of the ceiling tile material from buildings with elevated radiation levels showed the presence of radium-226 at levels of approximately 25 picocuries per gram (pCi/g); this material would thus have to be treated as hazardous waste, should it be removed. This report critiques the methodology and results of the two surveys and recommends further action.

  20. Results of the radiological survey at 77 Sinninger Street, Maywood, New Jersey (MJ052)

    SciTech Connect (OSTI)

    Foley, R.D.; Brown, K.S.

    1993-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 77 Sinninger Street, Maywood, New Jersey (MJ052), was conducted on December 17, 1992. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  1. Results of the radiological survey at 48 Schlosser Drive, Rochelle Park, New Jersey (RJ005)

    SciTech Connect (OSTI)

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956.MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from thisthorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy(DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 48 Schlosser Drive, Rochelle Park, New Jersey (RJO05), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  2. Results of the radiological survey at 37 Schlosser Drive, Rochelle Park, New Jersey (RJ002)

    SciTech Connect (OSTI)

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally [sup 232]Th derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 37 Schlosser Drive, Rochelle Park, New Jersey (RJ002), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  3. Results of the radiological survey at 31 Schlosser Drive, Rochelle Park, New Jersey (RJ003)

    SciTech Connect (OSTI)

    Foley, R.D.; Brown, K.S.

    1992-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Tb, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 31 Schlosser Drive, Rochelle Park, New Jersey (RJ003), was conducted on July 14, 1991. Results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions were not significantly different from normal background levels in the northern New Jersey area.

  4. Results of the radiological survey at 113 Avenue E, Lodi, New Jersey (LJ081)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 113 Avenue E, Lodi, New Jersey (LJ081), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs, 2 figs., 3 tabs.

  5. Results of the radiological survey at 62 Trudy Drive, Lodi, New Jersey (LJ080)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 62 Trudy Drive, Lodi, New Jersey (LJ080), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 5 figs., 3 tabs.

  6. Results of the radiological survey at 133 Maywood Avenue, Maywood, New Jersey (MJ025)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.; Floyd, L.M.; Crutcher, J.W. )

    1989-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 133 Maywood Avenue, Maywood, New Jersey (MJ025), was conducted during 1987. The survey results demonstrate that all radionuclide concentrations and measurements conform to DOE remedial action criteria. All values are at or below typical background values found in northern New Jersey. 5 refs., 2 figs., 3 tabs.

  7. Results of the radiological survey at 108 Avenue E, Lodi, New Jersey (LJ084)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 108 Avenue E, Lodi, New Jersey (LJ084), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 2 figs., 2 tabs.

  8. Results of the radiological survey at 9 Hancock Street, Lodi, New Jersey (LJ028)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 9 Hancock Street, Lodi, New Jersey (LJ028), was conducted during 1985 and 1986. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 6 figs., 3 tabs.

  9. Results of the radiological survey at 7 Redstone Lane, Lodi, New Jersey (LJ044)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclides analyses. The survey of this site, 7 Redstone Lane, Lodi, New Jersey (LJ044), was conducted during 1985 and 1986. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 4 figs., 3 tabs.

  10. Results of the radiological survey at 79 Avenue B, Lodi, New Jersey (LJ091)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 79 Avenue B, Lodi, New Jersey (LJ091), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 2 figs., 2 tabs.

  11. Results of the radiological survey at 32 Long Valley Road, Lodi, New Jersey (LJ046)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-10-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 32 Long Valley Road, Lodi, New Jersey (LJ046), was conducted during 1985, 1986, and 1987. Some radionuclide measurements were greater than typical background levels in the northern New Jersey area. However, results of the survey demonstrated no radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. 5 refs., 6 figs., 3 tabs.

  12. Results of the radiological survey at 14 Long Valley Road, Lodi, New Jersey (LJ070)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.

    1989-12-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 14 Long Valley Road, Lodi New Jersey (LJ070), was conducted during 1987. Survey measurements indicate that the property contained radioactive contamination primarily from the {sup 232}Th decay chain. The radionuclide distributions are typical of the type of material originating from processing operations at the MCW. 5 refs., 5 figs., 3 tabs.

  13. Results of the radiological survey at 7 Hancock Street, Lodi, New Jersey (LJ027)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Floyd, L.M.; Francis, M.W.; Mynatt, J.O.

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. AT the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 7 Hancock Street, Lodi, New Jersey (LJ027), was conducted during 1985 and 1986. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 5 figs., 3 tabs.

  14. ORISE: Independent verification

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Independent verification ORISE techinician performs environmental scanning The Oak Ridge Institute for Science and Education (ORISE) performs independent environmental assessments and verification to determine the effectiveness of radiological cleanup at decontamination and decommissioning (D&D) projects across the United States. Since 1980, ORISE has performed independent verification at more than 500 sites in 42 states and the District of Columbia. As the primary independent verification

  15. Final report of the radiological release survey of Building 11 at the Grand Junction Office Facility

    SciTech Connect (OSTI)

    Johnson, R.K.; Corle, S.G.

    1997-09-01

    The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailings during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 11 and the underlying soil were found not to be radiologically contaminated; therefore, the building can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual final release report for each GJO building.

  16. Final report of the radiological release survey of Building 19 at the Grand Junction Office Facility

    SciTech Connect (OSTI)

    Johnson, R.K.; Corle, S.G.

    1997-09-01

    The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailings during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 19 and the underlying soil were found not to be radiologically contaminated; therefore, the building can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual final release report for each GJO building.

  17. Final report of the radiological release survey of Building 54 at the Grand Junction Office Facility

    SciTech Connect (OSTI)

    Johnson, R.K.; Corle, S.G.

    1997-09-01

    The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailings during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 54 and the underlying soil were found not to be radiologically contaminated, and can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual release report for each GJO building.

  18. Final report of the radiological release survey of Building 29 at the Grand Junction Office Facility

    SciTech Connect (OSTI)

    Johnson, R.K.; Corle, S.G.

    1997-09-01

    The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailing during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 29 and the underlying soil were found not to be radiologically contaminated; therefore, the building can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual final release report for each GJO building.

  19. Radiological survey of the inactive uranium-mill tailings at Rifle, Colorado

    SciTech Connect (OSTI)

    Haywood, F.F.; Jacobs, D.J.; Ellis, B.S.; Hubbard, H.M. Jr.; Shinpaugh, W.H.

    1980-06-01

    Results of radiological surveys of two inactive uranium-mill sites near Rifle, Colorado, in May 1976 are presented. These sites are referred to as Old Rifle and New Rifle. The calculated /sup 226/Ra inventory of the latter site is much higher than at the older mill location. Data on above-ground measurements of gamma exposure rates, surface and near-surface concentration of /sup 226/Ra in soil and sediment samples, concentration of /sup 226/Ra in water, calculated subsurface distribution of /sup 226/Ra, and particulate radionuclide concentrations in air samples are given. The data serve to define the extent of contamination in the vicinity of the mill sites and their immediate surrounding areas with tailings particles. Results of these measurements were utilized as technical input for an engineering assessment of these two sites.

  20. Radiological survey of the inactive uranium-mill tailings at Durango, Colorado

    SciTech Connect (OSTI)

    Haywood, F.F.; Perdue, P.T.; Shinpaugh, W.H.; Ellis, B.S.; Chou, K.D.

    1980-03-01

    Results of a radiological survey of the inactive uranium-mill site at Durango, Colorado, conducted in April 1976, in cooperation with a team from Ford, Bacon and Davis Utah Inc., are presented together with descriptions of the instruments and techniques used to obtain the data. Direct above-ground gamma measurements and analysis of surface soil and sediment samples indicate movement of tailings from the piles toward Lightner Creek on the north and the Animas River on the east side of the piles. The concentration of /sup 226/Ra in the former raffinate pond area is only slightly above the background level. Two structures in Durango were found to contain high concentrations of airborne radon daughters, where tailings are known to have been utilized in construction. Near-background concentrations of radon daughters were found in a well-ventilated building close to the tailings.

  1. Radiological survey of the inactive uranium-mill tailings at Maybell, Colorado

    SciTech Connect (OSTI)

    Haywood, F.F.; Perdue, P.T.; Ellis, B.S.

    1980-03-01

    Results of a radiological survey of the inactive uranium-mill tailings near Maybell, Colorado are presented. Measurements of external gamma exposure rate at 1 m above the tailings ranged 16 to 340 ..mu..R/hr with an average value of 65 ..mu..R/hr. Radionuclide analysis of offsite soil and sediment samples, as well as above-ground gamma exposure rate measurements defined the spread of contamination around the tailings pile. This spread is greatest toward the east, in the direction of surface water runoff. Calculated concentrations of /sup 226/Ra in all of the holes drilled in the tailngs, based on gamma monitoring data, showed maximum concentrations in the range 100 to 800 pCi/g.

  2. Results of the radiological survey at 83 Belle Avenue, Maywood, New Jersey (MJ047)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 83 Belle Avenue, Maywood, New Jersey (MJ047), was conducted during 1988. 5 refs., 2 figs., 3 tabs.

  3. Results of the radiological survey at 15 John Street, Lodi, New Jersey (LJ087)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-12-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 15 John Street, Lodi, New Jersey (LJ087), was conducted during 1988. 5 refs., 3 figs., 3 tabs.

  4. Results of the radiological survey at 48 Long Valley Road, Lodi, New Jersey (LJ085)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 48 Long Valley Road, Lodi, New Jersey (LJ085), was conducted during 1988. 5 refs., 6 figs., 3 tabs.

  5. Results of the radiological survey at 104 Avenue E, Lodi, New Jersey (LJ086)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-12-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 104 Avenue E, Lodi, New Jersey (LJ086), was conducted during 1988. 5 refs., 2 figs., 3 tabs.

  6. Results of the radiological survey at 137 Maywood Avenue, Maywood, New Jersey (MJ026)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.

    1989-12-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 137 Maywood Avenue, Maywood, New Jersey (MJ026), was conducted during 1987. 6 refs., 2 figs., 3 tabs.

  7. Results of the radiological survey at 17 John Street, Lodi, New Jersey

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-12-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 17 John Street, Lodi, New Jersey (LJ088), was conducted during 1988. 5 refs., 2 figs., 3 tabs.

  8. Results of the radiological survey at 21 West Central Avenue, Maywood, New Jersey (MJ046)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 21 West Central Avenue, Maywood, New Jersey (MJ046), was conducted during 1988. 5 refs., 2 figs., 3 tabs.

  9. Mass and galaxy distributions of four massive galaxy clusters from Dark Energy Survey Science Verification data

    SciTech Connect (OSTI)

    Melchior, P.; Suchyta, E.; Huff, E.; Hirsch, M.; Kacprzak, T.; Rykoff, E.; Gruen, D.; Armstrong, R.; Bacon, D.; Bechtol, K.; Bernstein, G. M.; Bridle, S.; Clampitt, J.; Honscheid, K.; Jain, B.; Jouvel, S.; Krause, E.; Lin, H.; MacCrann, N.; Patton, K.; Plazas, A.; Rowe, B.; Vikram, V.; Wilcox, H.; Young, J.; Zuntz, J.; Abbott, T.; Abdalla, F. B.; Allam, S. S.; Banerji, M.; Bernstein, J. P.; Bernstein, R. A.; Bertin, E.; Buckley-Geer, E.; Burke, D. L.; Castander, F. J.; da Costa, L. N.; Cunha, C. E.; Depoy, D. L.; Desai, S.; Diehl, H. T.; Doel, P.; Estrada, J.; Evrard, A. E.; Neto, A. F.; Fernandez, E.; Finley, D. A.; Flaugher, B.; Frieman, J. A.; Gaztanaga, E.; Gerdes, D.; Gruendl, R. A.; Gutierrez, G. R.; Jarvis, M.; Karliner, I.; Kent, S.; Kuehn, K.; Kuropatkin, N.; Lahav, O.; Maia, M. A. G.; Makler, M.; Marriner, J.; Marshall, J. L.; Merritt, K. W.; Miller, C. J.; Miquel, R.; Mohr, J.; Neilsen, E.; Nichol, R. C.; Nord, B. D.; Reil, K.; Roe, N. A.; Roodman, A.; Sako, M.; Sanchez, E.; Santiago, B. X.; Schindler, R.; Schubnell, M.; Sevilla-Noarbe, I.; Sheldon, E.; Smith, C.; Soares-Santos, M.; Swanson, M. E. C.; Sypniewski, A. J.; Tarle, G.; Thaler, J.; Thomas, D.; Tucker, D. L.; Walker, A.; Wechsler, R.; Weller, J.; Wester, W.

    2015-03-31

    We measure the weak-lensing masses and galaxy distributions of four massive galaxy clusters observed during the Science Verification phase of the Dark Energy Survey. This pathfinder study is meant to 1) validate the DECam imager for the task of measuring weak-lensing shapes, and 2) utilize DECam's large field of view to map out the clusters and their environments over 90 arcmin. We conduct a series of rigorous tests on astrometry, photometry, image quality, PSF modelling, and shear measurement accuracy to single out flaws in the data and also to identify the optimal data processing steps and parameters. We find Science Verification data from DECam to be suitable for the lensing analysis described in this paper. The PSF is generally well-behaved, but the modelling is rendered difficult by a flux-dependent PSF width and ellipticity. We employ photometric redshifts to distinguish between foreground and background galaxies, and a red-sequence cluster finder to provide cluster richness estimates and cluster-galaxy distributions. By fitting NFW profiles to the clusters in this study, we determine weak-lensing masses that are in agreement with previous work. For Abell 3261, we provide the first estimates of redshift, weak-lensing mass, and richness. Additionally, the cluster-galaxy distributions indicate the presence of filamentary structures attached to 1E 0657-56 and RXC J2248.7-4431, stretching out as far as 1degree (approximately 20 Mpc), showcasing the potential of DECam and DES for detailed studies of degree-scale features on the sky.

  10. Mass and galaxy distributions of four massive galaxy clusters from Dark Energy Survey Science Verification data

    SciTech Connect (OSTI)

    Melchior, P.; et al.

    2015-05-21

    We measure the weak-lensing masses and galaxy distributions of four massive galaxy clusters observed during the Science Verification phase of the Dark Energy Survey. This pathfinder study is meant to 1) validate the DECam imager for the task of measuring weak-lensing shapes, and 2) utilize DECam's large field of view to map out the clusters and their environments over 90 arcmin. We conduct a series of rigorous tests on astrometry, photometry, image quality, PSF modeling, and shear measurement accuracy to single out flaws in the data and also to identify the optimal data processing steps and parameters. We find Science Verification data from DECam to be suitable for the lensing analysis described in this paper. The PSF is generally well-behaved, but the modeling is rendered difficult by a flux-dependent PSF width and ellipticity. We employ photometric redshifts to distinguish between foreground and background galaxies, and a red-sequence cluster finder to provide cluster richness estimates and cluster-galaxy distributions. By fitting NFW profiles to the clusters in this study, we determine weak-lensing masses that are in agreement with previous work. For Abell 3261, we provide the first estimates of redshift, weak-lensing mass, and richness. In addition, the cluster-galaxy distributions indicate the presence of filamentary structures attached to 1E 0657-56 and RXC J2248.7-4431, stretching out as far as 1 degree (approximately 20 Mpc), showcasing the potential of DECam and DES for detailed studies of degree-scale features on the sky.

  11. Mass and galaxy distributions of four massive galaxy clusters from Dark Energy Survey Science Verification data

    DOE PAGES-Beta [OSTI]

    Melchior, P.; Suchyta, E.; Huff, E.; Hirsch, M.; Kacprzak, T.; Rykoff, E.; Gruen, D.; Armstrong, R.; Bacon, D.; Bechtol, K.; et al

    2015-03-31

    We measure the weak-lensing masses and galaxy distributions of four massive galaxy clusters observed during the Science Verification phase of the Dark Energy Survey. This pathfinder study is meant to 1) validate the DECam imager for the task of measuring weak-lensing shapes, and 2) utilize DECam's large field of view to map out the clusters and their environments over 90 arcmin. We conduct a series of rigorous tests on astrometry, photometry, image quality, PSF modelling, and shear measurement accuracy to single out flaws in the data and also to identify the optimal data processing steps and parameters. We find Sciencemore » Verification data from DECam to be suitable for the lensing analysis described in this paper. The PSF is generally well-behaved, but the modelling is rendered difficult by a flux-dependent PSF width and ellipticity. We employ photometric redshifts to distinguish between foreground and background galaxies, and a red-sequence cluster finder to provide cluster richness estimates and cluster-galaxy distributions. By fitting NFW profiles to the clusters in this study, we determine weak-lensing masses that are in agreement with previous work. For Abell 3261, we provide the first estimates of redshift, weak-lensing mass, and richness. Additionally, the cluster-galaxy distributions indicate the presence of filamentary structures attached to 1E 0657-56 and RXC J2248.7-4431, stretching out as far as 1degree (approximately 20 Mpc), showcasing the potential of DECam and DES for detailed studies of degree-scale features on the sky.« less

  12. INDEPENDENT VERIFICATION OF THE BUILDING 3550 SLAB AT OAK RIDGE NATIONAL LABORATORY OAK RIDGE, TENNESSEE

    SciTech Connect (OSTI)

    Weaver, Phyllis C.

    2012-05-08

    The Oak Ridge Institute for Science and Education (ORISE) has completed the independent verification survey of the Building 3550 Slab. The results of this effort are provided. The objective of this verification survey is to provide independent review and field assessment of remediation actions conducted by Safety and Ecology Corporation (SEC) to document that the final radiological condition of the slab meets the release guidelines. Verification survey activities on the Building 3550 Slab that included scans, measurements, and the collection of smears. Scans for alpha, alpha plus beta, and gamma activity identified several areas that were investigated.

  13. Results of the radiological survey at 110 E Hunter Avenue, Maywood, New Jersey (MJ022)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.; Floyd, L.M.; Crutcher, J.W. )

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, 110 E. Hunter Avenue, Maywood, New Jersey (MJ022), was conducted during 1987. Following the removal of a small chunk of material showing elevated gamma exposure rates, all radionuclide concentrations and measurements conformed to DOE remedial action criteria. The slightly elevated radionuclide concentrations found in other soil samples were the result of naturally enhances radioactivity characteristic of some environmental materials such as coal ash and were unrelated to operations at the MCW site. The survey data demonstrate that the property requires no further action on the part of DOE. 4 refs., 2 figs., 3 tabs.

  14. RADIOLOGICAL SURVEY STATION DEVELOPMENT FOR THE PIT DISASSEMBLY AND CONVERSION PROJECT

    SciTech Connect (OSTI)

    Dalmaso, M.; Gibbs, K.; Gregory, D.

    2011-05-22

    The Savannah River National Laboratory (SRNL) has developed prototype equipment to demonstrate remote surveying of Inner and Outer DOE Standard 3013 containers for fixed and transferable contamination in accordance with DOE Standard 3013 and 10 CFR 835 Appendix B. When fully developed the equipment will be part of a larger suite of equipment used to package material in accordance with DOE Standard 3013 at the Pit Disassembly and Conversion Project slated for installation at the Savannah River Site. The prototype system consists of a small six-axis industrial robot with an end effector consisting of a force sensor, vacuum gripper and a three fingered pneumatic gripper. The work cell also contains two alpha survey instruments, swipes, swipe dispenser, and other ancillary equipment. An external controller interfaces with the robot controller, survey instruments and other ancillary equipment to control the overall process. SRNL is developing automated equipment for the Pit Disassembly and Conversion (PDC) Project that is slated for the Savannah River Site (SRS). The equipment being developed is automated packaging equipment for packaging plutonium bearing materials in accordance with DOE-STD-3013-2004. The subject of this paper is the development of a prototype Radiological Survey Station (RSS). Other automated equipment being developed for the PDC includes the Bagless transfer System, Outer Can Welder, Gantry Robot System (GRS) and Leak Test Station. The purpose of the RSS is to perform a frisk and swipe of the DOE Standard 3013 Container (either inner can or outer can) to check for fixed and transferable contamination. This is required to verify that the contamination levels are within the limits specified in DOE-STD-3013-2004 and 10 CFR 835, Appendix D. The surface contamination limit for the 3013 Outer Can (OC) is 500 dpm/100 cm2 (total) and 20 dpm/100 cm2 (transferable). This paper will concentrate on the RSS developments for the 3013 OC but the system for the

  15. An aerial radiological survey of the West Valley Demonstration Project and surrounding area, West Valley, New York

    SciTech Connect (OSTI)

    Berry, H.A.

    1991-09-01

    An aerial radiological survey of the West Valley Demonstration Project and the surrounding area was conducted from mid-August through early September 1984 by EG G Energy Measurements, Inc. for the United States Department of Energy. The radiological survey was part of the United States Department of Energy Comprehensive Integrated Remote Sensing (CIRS) program, which provides state-of-the-art remote sensing to support the needs of the various DOE facilities. The survey consisted of airborne measurements of both natural and man-made gamma radiation emanating from the terrestrial surface. These measurements allowed an estimate of the distribution of isotopic concentrations in the area surrounding the project site. Results are reported as isopleths superimposed on aerial photographs of the area. Gamma ray energy spectra are also presented for the net man-made radionuclides. 8 refs., 16 figs., 9 tabs.

  16. Results of the radiological survey at 146 W. Central Avenue, Maywood, New Jersey (MJ034)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and reining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from OaK Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. These surveys typically include direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, a private property at 146 West Central Avenue, Maywood, New Jersey (MJ034), was conducted during 1987 and 1988. While some measurements at this property were greater than background levels typically encountered in the New jersey area, no radiation levels nor radionuclide concentrations exceeded the guidelines established by the DOE for the Maywood, New Jersey, area remedial action plan. However, because of the proximity of the railroad property, which will be remediated, and the DOE's ALARA (As Low As Reasonably Achievable) policy, concurrent removal of the slightly elevated soil layers at 146 W. Central Avenue may be justified. 6 refs., 6 figs., 3 tabs.

  17. Observation and Confirmation of Six Strong Lensing Systems in The Dark Energy Survey Science Verification Data

    SciTech Connect (OSTI)

    Nord, B.; et al.

    2015-12-09

    We report the observation and confirmation of the first group- and cluster-scale strong gravitational lensing systems found in Dark Energy Survey (DES) data. Through visual inspection of data from the Science Verification (SV) season, we identified 53 candidate systems. We then obtained spectroscopic follow-up of 21 candidates using the Gemini Multi-Object Spectrograph (GMOS) at the Gemini South telescope and the Inamori-Magellan Areal Camera and Spectrograph (IMACS) at the Magellan/Baade telescope. With this follow-up, we confirmed six candidates as gravitational lenses: Three of the systems are newly discovered, and the remaining three were previously known. Of the 21 observed candidates, the remaining 15 were either not detected in spectroscopic observations, were observed and did not exhibit continuum emission (or spectral features), or were ruled out as lensing systems. The confirmed sample consists of one group-scale and five galaxy cluster-scale lenses. The lensed sources range in redshift z ~ 0.80-3.2, and in i-band surface brightness i_{SB} ~ 23-25 mag/sq.-arcsec. (2" aperture). For each of the six systems, we estimate the Einstein radius and the enclosed mass, which have ranges ~ 5.0 - 8.6" and ~ 7.5 x 10^{12} - 6.4 x 10^{13} solar masses, respectively.

  18. Wide-Field Lensing Mass Maps from Dark Energy Survey Science Verification Data

    DOE PAGES-Beta [OSTI]

    Chang, C.

    2015-07-29

    We present a mass map reconstructed from weak gravitational lensing shear measurements over 139 deg2 from the Dark Energy Survey science verification data. The mass map probes both luminous and dark matter, thus providing a tool for studying cosmology. We also find good agreement between the mass map and the distribution of massive galaxy clusters identified using a red-sequence cluster finder. Potential candidates for superclusters and voids are identified using these maps. We measure the cross-correlation between the mass map and a magnitude-limited foreground galaxy sample and find a detection at the 6.8σ level with 20 arc min smoothing. Thesemore » measurements are consistent with simulated galaxy catalogs based on N-body simulations from a cold dark matter model with a cosmological constant. This suggests low systematics uncertainties in the map. Finally, we summarize our key findings in this Letter; the detailed methodology and tests for systematics are presented in a companion paper.« less

  19. Wide-Field Lensing Mass Maps from Dark Energy Survey Science Verification Data

    SciTech Connect (OSTI)

    Chang, C.

    2015-07-29

    We present a mass map reconstructed from weak gravitational lensing shear measurements over 139 deg2 from the Dark Energy Survey science verification data. The mass map probes both luminous and dark matter, thus providing a tool for studying cosmology. We also find good agreement between the mass map and the distribution of massive galaxy clusters identified using a red-sequence cluster finder. Potential candidates for superclusters and voids are identified using these maps. We measure the cross-correlation between the mass map and a magnitude-limited foreground galaxy sample and find a detection at the 6.8σ level with 20 arc min smoothing. These measurements are consistent with simulated galaxy catalogs based on N-body simulations from a cold dark matter model with a cosmological constant. This suggests low systematics uncertainties in the map. Finally, we summarize our key findings in this Letter; the detailed methodology and tests for systematics are presented in a companion paper.

  20. Cosmic Voids and Void Lensing in the Dark Energy Survey Science Verification Data

    DOE PAGES-Beta [OSTI]

    Sánchez, C.; Clampitt, J.; Kovacs, A.; Jain, B.; García-Bellido, J.; Nadathur, S.; Gruen, D.; Hamaus, N.; Huterer, D.; Vielzeuf, P.; et al

    2016-10-26

    Galaxies and their dark matter halos populate a complicated filamentary network around large, nearly empty regions known as cosmic voids. Cosmic voids are usually identified in spectroscopic galaxy surveys, where 3D information about the large-scale structure of the Universe is available. Although an increasing amount of photometric data is being produced, its potential for void studies is limited since photometric redshifts induce line-of-sight position errors of ~50 Mpc/h or more that can render many voids undetectable. In this paper we present a new void finder designed for photometric surveys, validate it using simulations, and apply it to the high-quality photo-zmore » redMaGiC galaxy sample of the Dark Energy Survey Science Verification (DES-SV) data. The algorithm works by projecting galaxies into 2D slices and finding voids in the smoothed 2D galaxy density field of the slice. Fixing the line-of-sight size of the slices to be at least twice the photo- z scatter, the number of voids found in these projected slices of simulated spectroscopic and photometric galaxy catalogs is within 20% for all transverse void sizes, and indistinguishable for the largest voids of radius ~70 Mpc/h and larger. The positions, radii, and projected galaxy profiles of photometric voids also accurately match the spectroscopic void sample. Applying the algorithm to the DES-SV data in the redshift range 0.2 < z < 0.8 , we identify 87 voids with comoving radii spanning the range 18-120 Mpc/h, and carry out a stacked weak lensing measurement. With a significance of 4.4σ, the lensing measurement confirms the voids are truly underdense in the matter field and hence not a product of Poisson noise, tracer density effects or systematics in the data. In conclusion, it also demonstrates, for the first time in real data, the viability of void lensing studies in photometric surveys.« less

  1. Radiological survey report for the former Middlesex Sampling Plant, Middlesex, New Jersey

    SciTech Connect (OSTI)

    Not Available

    1985-03-01

    The former Middlesex Sampling Plant (MSP), Middlesex, New Jersey is currently owned by the United States Department of Energy (DOE). It was used from 1943 to 1967 as a sampling and storage facility for uranium and thorium concentrates. During the course of operations, the buildings and grounds at the site became contaminated. In 1980, DOE initiated a multiphase remedial action project to clean up the site and several vicinity properties onto which contamination from the plant had migrated. Material from these properties was consolidated in a storage pile at the MSP during Phases I and II of the project. A decision by DOE regarding the final disposition of the site will be made once the results of an engineering evaluation of disposition alternatives and of other studies required by the National Environmental Policy Act are available. This report describes the current radiological status of the MSP site as determined by a characterization survey performed to obtain information necessary for the development of the Phase III engineering design. The grounds and the four buildings on-site were surveyed; uranium-238 and radium-226 concentrations exceeded DOE remedial action guidelines. Approximately 69,000 m/sup 3/ (91,000 yd/sup 3/) of material must be removed for the site to comply with guidelines. This total comprises the following approximate volumes: 13,000 m/sup 3/ (17,000 yd/sup 3/) of asphalt/gravel and soil from the grounds, 3650 m/sup 3/ (4775 yd/sup 3/) from demolition of the Boiler House and Process Building, and 52,000 m/sup 3/ (69,000 yd/sup 3/) of contaminated material that is or will be stored on-site. In addition, parts of the Garage and Administration Building must be decontaminated. 14 refs., 11 figs., 6 tabs.

  2. INDEPENDENT VERIFICATION OF THE CENTRAL CAMPUS AND SOUTHEAST LABORATORY COMPLEX BUILDING SLABS AT OAK RIDGE NATIONAL LABORATORY, OAK RIDGE, TENNESSEE

    SciTech Connect (OSTI)

    Weaver, Phyllis C.

    2012-07-24

    Oak Ridge Associated Universities/Oak Ridge Institute for Science and Education (ORAU/ORISE) has completed the independent verification survey of the Central Campus and Southeast Lab Complex Building Slabs. The results of this effort are provided. The objective of this verification survey was to provide independent review and field assessment of remediation actions conducted by SEC, and to independently assess whether the final radiological condition of the slabs met the release guidelines.

  3. Results of the radiological survey at the ALCOA Research Laboratory, 600 Freeport Road, New Kensington, Pennsylvania (ANK001)

    SciTech Connect (OSTI)

    Foley, R.D.; Brown, K.S.

    1992-10-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the ALCOA Research Laboratory, 600 Freeport Road, New Kensington, Pennsylvania. The survey was performed on November 12, 1991. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally [sup 238]U, as a result of work done for the Manhattan Engineer District in 1944. The survey included measurement of direct alpha and beta-gamma levels in the northeast comer of the basement of Building 29, and the collection of a debris sample from a floor drain for radionuclide analysis. The survey area was used for experimental canning of uranium slugs prior to production activities at the former New Kensington Works nearby.

  4. A comparison of four aerial radiological surveys of Par Pond and the surrounding area, Savannah River Site, Aiken, South Carolina. Dates of surveys: 1989--1992

    SciTech Connect (OSTI)

    Feimster, E.L.

    1993-09-01

    A series of gamma radiation surveys was conducted over Par Pond at the Savannah River Site (SRS) in August 1993, October 1991, and August 1992 as part of an effort to monitor the radiological changes around Par Pond as its water level was lowered. The results of an April 1989 survey, which was about one-half the area of those surveys listed above, were used as baseline data for the comparison. Gamma energy spectrum analysis revealed that the only man-made gamma ray emitter detected during the four surveys in the Par Pond area was cesium-137. The comparisons revealed that: (1) significant change in the radiological environment occurred along the Par Pond shoreline as the water levels were lowered, (2) the activity in Lower Three Runs Creek varied slightly as the level/flow rate changed during the pumping process, (3) minor changes occurred in areas adjacent to the Par Pond, and (4) little or no change occurred between surveys in the spatial distribution or kind of sources detected. All changes were directly related to the moisture variations (Par Pond water lowering, rainfall, waterway flow rates) between the survey periods. The distribution, kind, and activity of sources detected beyond the pond bed were consistent between surveys. 60 figs., 14 tabs.

  5. Radiological Survey Tool Set for ArcGIS 8.3 and ArcPad 6.0

    SciTech Connect (OSTI)

    ROGER, COTTRELL

    2004-11-30

    The Radiological Control Operations (RCO) group at the Savannah River Site (SRS) is tasked with conducting routine surveys for the detection of radiological contaminants in the environment. The Radiological Survey Tool Set (RSTS) was developed by the Environmental & Geographic Information Systems (EGIS) group of SRS to assist RCO personnel in this survey process. The tool set consists of two major components. The first component is a custom extension for ArcGIS 8.3 that allows the user to interactively create a sampling plan prior to entering the field. Additionally, the extension allows the user to upload field-collected data to the GIS with post-processing functionality. The second component is a custom ArcPad 6.0 applet. This applet provides the user with navigational capabilities to a selected origin point with the help of Global Positioning Systems (GPS) technology, and the recording of the sample data results into a hand-held field computer via ArcPad 6.0 software.

  6. Guidelines for the verification and validation of expert system software and conventional software: Survey and documentation of expert system verification and validation methodologies. Volume 3

    SciTech Connect (OSTI)

    Groundwater, E.H.; Miller, L.A.; Mirsky, S.M.

    1995-03-01

    This report is the third volume in the final report for the Expert System Verification and Validation (V&V) project which was jointly sponsored by the Nuclear Regulatory Commission and the Electric Power Research Institute. The ultimate objective is the formulation of guidelines for the V&V of expert systems for use in nuclear power applications. The purpose of this activity was to survey and document techniques presently in use for expert system V&V. The survey effort included an extensive telephone interviewing program, site visits, and a thorough bibliographic search and compilation. The major finding was that V&V of expert systems is not nearly as established or prevalent as V&V of conventional software systems. When V&V was used for expert systems, it was almost always at the system validation stage after full implementation and integration usually employing the non-systematic dynamic method of {open_quotes}ad hoc testing.{close_quotes} There were few examples of employing V&V in the early phases of development and only weak sporadic mention of the possibilities in the literature. There is, however, a very active research area concerning the development of methods and tools to detect problems with, particularly, rule-based expert systems. Four such static-testing methods were identified which were not discovered in a comprehensive review of conventional V&V methods in an earlier task.

  7. INDEPENDENT VERIFICATION SURVEY OF THE SPRU LOWER LEVEL HILLSIDE AREA AT THE KNOLLS ATOMIC POWER LABORATORY NISKAYUNA, NEW YORK

    SciTech Connect (OSTI)

    Harpenau, Evan M.; Weaver, Phyllis C.

    2012-06-06

    During August 10, 2011 through August 19, 2011, and October 23, 2011 through November 4, 2011, ORAU/ORISE conducted verification survey activities at the Separations Process Research Unit (SPRU) site that included in-process inspections, surface scans, and soil sampling of the Lower Level Hillside Area. According to the Type-B Investigation Report, Sr-90 was the primary contributor to the majority of the activity (60 times greater than the Cs-137 activity). The evaluation of the scan data and sample results obtained during verification activities determined that the primary radionuclide of concern, Sr-90, was well below the agreed upon soil cleanup objective (SCO) of 30 pCi/g for the site. However, the concentration of Cs-137 in the four judgmental samples collected in final status survey (FSS) Units A and B was greater than the SCO. Both ORAU and aRc surveys identified higher Cs-137 concentrations in FSS Units A and B; the greatest concentrations were indentified in FSS Unit A.

  8. Nearest Neighbor Averaging and its Effect on the Critical Level and Minimum Detectable Concentration for Scanning Radiological Survey Instruments that Perform Facility Release Surveys.

    SciTech Connect (OSTI)

    Fournier, Sean Donovan; Beall, Patrick S; Miller, Mark L.

    2014-08-01

    Through the SNL New Mexico Small Business Assistance (NMSBA) program, several Sandia engineers worked with the Environmental Restoration Group (ERG) Inc. to verify and validate a novel algorithm used to determine the scanning Critical Level (L c ) and Minimum Detectable Concentration (MDC) (or Minimum Detectable Areal Activity) for the 102F scanning system. Through the use of Monte Carlo statistical simulations the algorithm mathematically demonstrates accuracy in determining the L c and MDC when a nearest-neighbor averaging (NNA) technique was used. To empirically validate this approach, SNL prepared several spiked sources and ran a test with the ERG 102F instrument on a bare concrete floor known to have no radiological contamination other than background naturally occurring radioactive material (NORM). The tests conclude that the NNA technique increases the sensitivity (decreases the L c and MDC) for high-density data maps that are obtained by scanning radiological survey instruments.

  9. Results of the radiological survey at the former Chapman Valve Manufacturing Company, Indian Orchard, Massachusetts (CIO001)

    SciTech Connect (OSTI)

    Foley, R.D.; Uziel, M.S.

    1992-07-01

    Radiological survey was conducted at Building 23 (Department No. 40) at the former Chapman Valve Manufacturing Company, Indian Orchard, Massachusetts. The survey was performed in August 1991. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally {sup 238}U, as a result of work done for the Atomic Energy Commission (AEC) during the 1940s. The survey included a gamma scan, a beta-gamma scan, and measurement of alpha activity; measurement of direct and removable alpha and beta-gamma levels; and the collection of soil, dust, debris, and smear samples for radionuclide analyses. Survey emphasis was on interior floors, walls, and overhead beams. Radionuclide analysis of soil, dust, and debris, and analysis of smear samples indicate that residual {sup 238}U attributable to former AEC-supported operations is present at this site. Elevated levels of radioactivity were particularly evident on the floors and walls in the western part of the central area of the building (grid blocks Al through A6). Concentrations of {sup 238}U in dust samples collected from overhead beams exceeded DOE guidelines in grid blocks Al through A14 and remained elevated in grid blocks A15 through A19. Dust on a movable overhead crane in grid block A23 was well above the guideline, probably because the crane had at some time been located further west. Some contamination was evident in grid blocks B1 through B5, but clutter and debris in this area prevented a thorough survey.

  10. Informed Consent for Interventional Radiology Procedures: A Survey Detailing Current European Practice

    SciTech Connect (OSTI)

    O'Dwyer, H.M.; Lyon, S.M.; Fotheringham, T.; Lee, M.J.

    2003-09-15

    Purpose: Official recommendations for obtaining informed consent for interventional radiology procedures are that the patient gives their consent to the operator more than 24 hr prior to the procedure. This has significant implications for interventional radiology practice. The purpose of this study was to identify the proportion of European interventional radiologists who conform to these guidelines. Methods: A questionnaire was designed consisting of 12 questions on current working practice and opinions regarding informed consent. These questions related to where, when and by whom consent was obtained from the patient. Questions also related to the use of formal consent forms and written patient information leaflets. Respondents were asked whether they felt patients received adequate explanation regarding indications for intervention,the procedure, alternative treatment options and complications. The questionnaire was distributed to 786 European interventional radiologists who were members of interventional societies. The anonymous replies were then entered into a database and analyzed. Results: Two hundred and fifty-four (32.3%) questionnaires were returned. Institutions were classified as academic (56.7%),non-academic (40.5%) or private (2.8%). Depending on the procedure,in a significant proportion of patients consent was obtained in the outpatient department (22%), on the ward (65%) and in the radiology day case ward (25%), but in over half (56%) of patients consent or re-consent was obtained in the interventional suite. Fifty percent of respondents indicated that they obtain consent more than 24 hr before some procedures, in 42.9% consent is obtained on the morning of the procedure and 48.8% indicated that in some patients consent is obtained immediately before the procedure. We found that junior medical staff obtained consent in 58% of cases. Eighty-two percent of respondents do not use specific consent forms and 61% have patient information leaflets. The

  11. Results of the radiological survey at the National Community Bank, 113 Essex Street, Maywood, New Jersey (MJ021)

    SciTech Connect (OSTI)

    Foley, R.D.; Cottrell, W.D.; Floyd, L.M.

    1989-09-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, the National Community Bank, 113 Essex Street, Maywood, New Jersey (MJ021), was conducted during 1986. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 2 figs., 3 tabs.

  12. Results of the radiological survey at Interstate 80, North Right of Way at Lodi Brook, Lodi, New Jersey (LJ077)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-06-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally /sup 232/Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and oil sampling for radionuclide analyses. The survey of this site, on the North Right of Way of Interstate 80 at Lodi Brook, Lodi, New Jersey (LJ077), was conducted during 1988. Results of the survey demonstrated radionuclide concentrations in excess of the DOE Formerly Utilized Sites Remedial Action Program criteria. The radionuclide distributions are typical of the type of material originating from the MCW site. 5 refs., 3 figs., 3 tabs.

  13. Final report of the radiological release survey of Building 30B at the Grand Junction Office Facility

    SciTech Connect (OSTI)

    Krauland, P.A.; Corle, S.G.

    1997-09-01

    The U.S. Department of Energy (DOE) Grand Junction Office (GJO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore concentrates and mill tailings during vanadium refining activities of the Manhattan Engineer District, and during sampling, assaying, pilot milling, storage, and brokerage activities conducted for the U.S. Atomic Energy Commission`s domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJO Remedial Action Project (GJORAP) to clean up and restore the facility lands, improvements, and underlying aquifer. WASTREN-Grand Junction is the site contractor for the facility and the remedial action contractor for GJORAP. Building 30B and the underlying soil were found not to be radiologically contaminated; therefore, the building can be released for unrestricted use. Placards have been placed at the building entrances indicating the completion of the radiological release survey and prohibiting the introduction of any radioactive materials within the building without written approvals from the GJO Facilities Operations Manager. This document was prepared in response to a DOE-GJO request for an individual final release report for each GJO building.

  14. An Aerial Radiological survey of the Alvin W. Vogtle Nuclear Plant and surrounding area, Waynesboro, Georgia: Date of survey: August--September 1988

    SciTech Connect (OSTI)

    Not Available

    1990-09-01

    An Aerial Radiological Survey was conducted during the period of August 24 to September 14, 1988 over an area of approximately 310 square kilometers (120 square miles) surrounding the Alvin W. Vogtle Nuclear Plant. The Vogtle Nuclear Plant is located near Augusta, Georgia, along the Savannah River and adjacent to the Savannah River Site (SRS). Several anomalous areas were identified in the portion of the survey extending into the SRS perimeter. The dominant isotopes found in these areas were cesium-137 and cobalt-60. All of these man-made anomalies identified by the aerial measurements were attributed to SRS processing. For the remainder of the survey area, the inferred radiation exposure rates generally varied from 6 to 10 microroentgens per hour ({mu}R/h), which was found to be due to naturally occurring uranium, thorium, and radioactive potassium gamma emitters. The reported exposure rate values included an estimated cosmic ray contribution of 3.6 {mu}R/h. Soils samples and pressurized ion chamber measurements were obtained at three locations within the survey boundaries to support the aerial data. The exposure rate values obtained from these groundbased measurements were in agreement with the corresponding inferred aerial values. 6 refs., 13 figs., 4 tabs.

  15. Radiological survey of the Mare Island Naval Shipyard, Alameda Naval Air Station, and Hunters Point Shipyard

    SciTech Connect (OSTI)

    Semler, M.O.; Blanchard, R.L. . Eastern Environmental Radiation Facility)

    1989-06-01

    Since 1963, the Eastern Environmental Radiation Facility (EERF), US Environmental Protection Agency (USEPA), in cooperation with the US Naval Sea Systems Command (NAVSEA) has surveyed facilities serving nuclear-powered warships on the Atlantic and Pacific coasts and the Gulf of Mexico. These surveys assess whether the operation of nuclear-powered warships, during construction, maintenance, overhaul, or refueling, have created elevated levels of radioactivity. The surveys emphasize sampling those areas and pathways that could expose the public. In 1984, NAVSEA requested that EPA survey all active facilities serving nuclear-powered warships over the next three years. This report contains the results of surveys conducted at Naval facilities located at Mare Island, Alameda, and Hunters Point in the San Francisco region. The locations of these facilities are shown. 3 refs., 4 figs., 3 tabs.

  16. Results of the radiological survey at Sumitomo Machinery Corporation of America, 7 Malcolm Avenue, Teterboro, New Jersey (TJ001)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-02-01

    A radiological survey of the commercial property at 7 Malcolm Avenue, Teterboro, New Jersey, was conducted on November 12--20, 1986. Samples of the soil surface were taken for further analyses during this time. Conversations with property owners revealed that originally this site was part of a single property of approximately 107 acres owned entirely by the Bendix Aerospace Corporation. During this period of total property ownership, Bendix was licensed by the Nuclear Regulatory Commission to use thorium in on-site Navy/Bendix process. Around 1976, the property was subdivided into three parcels, and one parcel of about 7 acres was purchased by Sumitomo Corporation. 5 refs., 3 figs., 5 tabs.

  17. FINAL REPORT INDEPENDENT VERIFICATION SURVEY SUMMARY AND RESULTS FOR THE ARGONNE NATIONAL LABORATORY BUILDING 330 PROJECT FOOTPRINT, ARGONNE, ILLINOIS

    SciTech Connect (OSTI)

    ERIKA N. BAILEY

    2012-02-29

    ORISE conducted onsite verification activities of the Building 330 project footprint during the period of June 6 through June 7, 2011. The verification activities included technical reviews of project documents, visual inspections, radiation surface scans, and sampling and analysis. The draft verification report was issued in July 2011 with findings and recommendations. The contractor performed additional evaluations and remediation.

  18. Results of the radiological survey at Greg's Auto Emporium, 60 State Highway 46, Lodi, New Jersey (LJ089)

    SciTech Connect (OSTI)

    Foley, R.D.; Floyd, L.M.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The survey typically includes direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this site, Greg's Auto Emporium, 60 State Highway 46, Lodi, New Jersey (LJ089), was conducted during 1988. 5 refs., 3 figs., 3 tabs.

  19. Radiological survey of Latty Avenue in the vicinity of the former Cotter site, Hazelwood/Berkeley, Missouri (LM001)

    SciTech Connect (OSTI)

    Cottrell, W.D.; Carrier, R.F.

    1987-05-01

    A radiological survey was conducted over a proposed construction corridor in the vicinity of the former Cotter site at 9200 Latty Avenue. The survey included gamma exposure rates at the ground surface and at 1 m above the surface throughout the site, sampling of surface soil, sampling of subsurface soil from auger holes, gamma logging of auger holes, and sampling of subsurface water. The results of the survey demonstrated some degree of radioactive contamination in all areas of the construction corridor, extending north and south in some regions onto adjacent private properties. Redistribution of the contamination by flooding, surface runoff, and road and utility line activities was evident. The pattern of contamination ranged from widespread to isolated spots and was found to occur from near the surface to depths of approx.1.8 m. The most highly contaminated region was noted on both sides of Latty Avenue adjacent to the former Cotter site. Concentrations of /sup 230/Th in soil from that region were as high as 16,000 pCi/g.

  20. INDEPENDENT VERIFICATION SURVEY REPORT FOR EXPOSURE UNITS Z2-24, Z2-31, Z2-32, AND Z2-36 IN ZONE 2 OF THE EAST TENNESSEE TECHNOLOGY PARK OAK RIDGE, TENNESSEE

    SciTech Connect (OSTI)

    2013-10-10

    The U.S. Department of Energy (DOE) Oak Ridge Office of Environmental Management selected Oak Ridge Associated Universities (ORAU), through the Oak Ridge Institute for Science and Education (ORISE) contract, to perform independent verification (IV) at Zone 2 of the East Tennessee Technology Park (ETTP) in Oak Ridge, Tennessee. ORAU has concluded IV surveys, per the project-specific plan (PSP) (ORAU 2013a) covering exposure units (EUs) Z2-24, -31, -32, and -36. The objective of this effort was to verify the following. • Target EUs comply with requirements in the Zone 2 Record of Decision (ROD) (DOE 2005), as implemented by using the dynamic verification strategy presented in the dynamic work plan (DWP) (BJC 2007) • Commitments in the DWP were adequately implemented, as verified via IV surveys and soil sampling The Zone 2 ROD establishes maximum remediation level (RLmax) values and average RL (RLavg) values for the primary contaminants of concern (COCs) U-234, U-235, U-238, Cs-137, Np-237, Ra-226, Th-232, arsenic, mercury, and polychlorinated biphenyls (PCBs). Table 1.1 lists Zone 2 COCs with associated RLs. Additional radiological and chemical contaminants were also identified during past characterization and monitoring actions, though the ROD does not present RLs for these potential contaminants. IV activities focused on the identification and quantification of ROD-specific COCs in surface soils, but also generated data for other analytes to support future decisions. ORAU personnel also reviewed EU-specific phased construction completion reports (PCCRs) to focus IV activities and identify potential judgmental sample locations, if any.

  1. Wide-field lensing mass maps from Dark Energy Survey science verification data: Methodology and detailed analysis

    DOE PAGES-Beta [OSTI]

    Vikram, V.; Sheldon, E.; Chang, C.; Jain, B.; Bacon, D.; Amara, A.; Becker, M. R.; Bernstein, G.; Bonnett, C.; Bridle, S.; et al

    2015-07-29

    Weak gravitational lensing allows one to reconstruct the spatial distribution of the projected mass density across the sky. These mass maps provide a powerful tool for studying cosmology as they probe both luminous and dark matter. In this paper, we present a weak lensing mass map reconstructed from shear measurements in a 139 deg2 area from the Dark Energy Survey science verification data. We compare the distribution of mass with that of the foreground distribution of galaxies and clusters. The overdensities in the reconstructed map correlate well with the distribution of optically detected clusters. We demonstrate that candidate superclusters andmorevoids along the line of sight can be identified, exploiting the tight scatter of the cluster photometric redshifts. We cross-correlate the mass map with a foreground magnitude-limited galaxy sample from the same data. Our measurement gives results consistent with mock catalogs from N-body simulations that include the primary sources of statistical uncertainties in the galaxy, lensing, and photo-z catalogs. The statistical significance of the cross-correlation is at the 6.8? level with 20 arcminute smoothing. We find that the contribution of systematics to the lensing mass maps is generally within measurement uncertainties. We analyze less than 3% of the final area that will be mapped by the DES; the tools and analysis techniques developed in this paper can be applied to forthcoming larger data sets from the survey.less

  2. Wide-field lensing mass maps from Dark Energy Survey science verification data: Methodology and detailed analysis

    DOE PAGES-Beta [OSTI]

    Vikram, V.

    2015-07-29

    Weak gravitational lensing allows one to reconstruct the spatial distribution of the projected mass density across the sky. These “mass maps” provide a powerful tool for studying cosmology as they probe both luminous and dark matter. In this paper, we present a weak lensing mass map reconstructed from shear measurements in a 139 deg2 area from the Dark Energy Survey (DES) science verification data. We compare the distribution of mass with that of the foreground distribution of galaxies and clusters. The overdensities in the reconstructed map correlate well with the distribution of optically detected clusters. We demonstrate that candidate superclustersmore » and voids along the line of sight can be identified, exploiting the tight scatter of the cluster photometric redshifts. We cross-correlate the mass map with a foreground magnitude-limited galaxy sample from the same data. Our measurement gives results consistent with mock catalogs from N-body simulations that include the primary sources of statistical uncertainties in the galaxy, lensing, and photo-z catalogs. The statistical significance of the cross-correlation is at the 6.8σ level with 20 arcminute smoothing. We find that the contribution of systematics to the lensing mass maps is generally within measurement uncertainties. In this study, we analyze less than 3% of the final area that will be mapped by the DES; the tools and analysis techniques developed in this paper can be applied to forthcoming larger data sets from the survey.« less

  3. Wide-field lensing mass maps from Dark Energy Survey science verification data: Methodology and detailed analysis

    SciTech Connect (OSTI)

    Vikram, V.; Sheldon, E.; Chang, C.; Jain, B.; Bacon, D.; Amara, A.; Becker, M. R.; Bernstein, G.; Bonnett, C.; Bridle, S.; Brout, D.; Busha, M.; Frieman, J.; Gaztanaga, E.; Hartley, W.; Jarvis, M.; Kacprzak, T.; Kovacs, A.; Lahav, O.; Leistedt, B.; Lin, H.; Melchior, P.; Peiris, H.; Rozo, E.; Rykoff, E.; Sanchez, C.; Sheldon, E.; Troxel, M. A.; Wechsler, R.; Zuntz, J.; Abbott, T.; Abdalla, F. B.; Armstrong, R.; Banerji, M.; Bauer, A. H.; Benoit-Levy, A.; Bertin, E.; Brooks, D.; Buckley-Geer, E.; Burke, D. L.; Capozzi, D.; Carnero Rosell, A.; Kind, M. Carrasco; Castander, F. J.; Crocce, M.; Cunha, C. E.

    2015-07-29

    Weak gravitational lensing allows one to reconstruct the spatial distribution of the projected mass density across the sky. These mass maps provide a powerful tool for studying cosmology as they probe both luminous and dark matter. In this paper, we present a weak lensing mass map reconstructed from shear measurements in a 139 deg2 area from the Dark Energy Survey science verification data. We compare the distribution of mass with that of the foreground distribution of galaxies and clusters. The overdensities in the reconstructed map correlate well with the distribution of optically detected clusters. We demonstrate that candidate superclusters and voids along the line of sight can be identified, exploiting the tight scatter of the cluster photometric redshifts. We cross-correlate the mass map with a foreground magnitude-limited galaxy sample from the same data. Our measurement gives results consistent with mock catalogs from N-body simulations that include the primary sources of statistical uncertainties in the galaxy, lensing, and photo-z catalogs. The statistical significance of the cross-correlation is at the 6.8? level with 20 arcminute smoothing. We find that the contribution of systematics to the lensing mass maps is generally within measurement uncertainties. We analyze less than 3% of the final area that will be mapped by the DES; the tools and analysis techniques developed in this paper can be applied to forthcoming larger data sets from the survey.

  4. Wide-field lensing mass maps from Dark Energy Survey science verification data: Methodology and detailed analysis

    SciTech Connect (OSTI)

    Vikram, V.

    2015-07-29

    Weak gravitational lensing allows one to reconstruct the spatial distribution of the projected mass density across the sky. These mass maps provide a powerful tool for studying cosmology as they probe both luminous and dark matter. In this paper, we present a weak lensing mass map reconstructed from shear measurements in a 139 deg2 area from the Dark Energy Survey (DES) science verification data. We compare the distribution of mass with that of the foreground distribution of galaxies and clusters. The overdensities in the reconstructed map correlate well with the distribution of optically detected clusters. We demonstrate that candidate superclusters and voids along the line of sight can be identified, exploiting the tight scatter of the cluster photometric redshifts. We cross-correlate the mass map with a foreground magnitude-limited galaxy sample from the same data. Our measurement gives results consistent with mock catalogs from N-body simulations that include the primary sources of statistical uncertainties in the galaxy, lensing, and photo-z catalogs. The statistical significance of the cross-correlation is at the 6.8? level with 20 arcminute smoothing. We find that the contribution of systematics to the lensing mass maps is generally within measurement uncertainties. In this study, we analyze less than 3% of the final area that will be mapped by the DES; the tools and analysis techniques developed in this paper can be applied to forthcoming larger data sets from the survey.

  5. Formerly utilized MED/AEC sites remedial action program post-remedial-action radiological survey of Kent Chemical Laboratory, the University of Chicago, Chicago, IL

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1983-05-01

    A comprehensive radiological assessment of Kent Laboratory was conducted during September 1977, by the ANL Radiological Survey Group to determine if any radioactive contamination remained. The results of the assessment indicated the need for remedial action. Since 1977, the University has decontaminated this laboratory building, and in May 1983, the Department of Energy requested the ANL Radiological Survey Group to conduct a post-remedial-action survey. All the contaminated areas identified during the 1977 assessment were rechecked. Contamination remained in six of the rooms. Further decontamination of these areas was conducted by university personnel, and as a result, these areas are now free of contamination. However, a contaminated clay pipe in the attic remained. The clay pipe has since been removed and disposed of as solid radioactive waste. During the post-remedial-action survey, six soil samples were collected from excavation trenches dug in Rooms 1 and 2 as part of the University's remedial action efforts. Also, four sludge samples were taken from below the manhole covers in the basement of Kent Chemical Laboratory to assess the radiological condition of the sewer system. A radiological assessment of the sewer system had not been accomplished during the 1977 survey as per program direction. Radiochemical (fluorometric) and gamma-spectral analyses indicated that eight out of ten soil and sludge samples contained levels of radioactivity above expected background concentrations. The soil has since been further excavated. The building is now free of radioactive contamination in excess of background levels; however, the sewers do contain radioactive materials above background levels since contamination was found at appropriate access points. 6 references, 16 figures, 7 tables.

  6. Results of the radiological survey at Route 17(S) and Becker Avenue, Rochelle Park, New Jersey (RJ001)

    SciTech Connect (OSTI)

    Foley, R.D.; Carrier, R.F.

    1989-11-01

    Maywood Chemical Works (MCW) of Maywood, New Jersey, generated process wastes and residues associated with the production and refining of thorium and thorium compounds from monazite ores from 1916 to 1956. MCW supplied rare earth metals and thorium compounds to the Atomic Energy Commission and various other government agencies from the late 1940s to the mid-1950s. Area residents used the sandlike waste from this thorium extraction process mixed with tea and cocoa leaves as mulch in their yards. Some of these contaminated wastes were also eroded from the site into Lodi Brook. At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducts investigative radiological surveys of properties in the vicinity of MCW to determine whether a property is contaminated with radioactive residues, principally {sup 232}Th, derived from the MCW site. The surveys typically include direct measurement of gamma radiation levels and soil sampling for radionuclide analyses. The survey of this commercial property at Route 17(S) and Becker Avenue, Rochelle Park, New Jersey (RJ001), was conducted in 1986. Measurements taken at the commercial property located at Route 17(S) and Becker Avenue indicate slightly elevated gamma exposure rates in three areas of the parking lot. Although results of analysis of the asphalt disclosed radionuclide concentrations in excess of the applicable criterion, their presence is due to naturally radioactive substances in asphalt patching materials and is not associated with material from the MCW site. Therefore, it is recommended that this site be eliminated from consideration for inclusion in the DOE remedial action program. 5 refs., 2 figs., 3 tabs.

  7. Cosmology from large scale galaxy clustering and galaxy-galaxy lensing with Dark Energy Survey Science Verification data

    DOE PAGES-Beta [OSTI]

    Kwan, J.

    2016-10-05

    Here, we present cosmological constraints from the Dark Energy Survey (DES) using a combined analysis of angular clustering of red galaxies and their cross-correlation with weak gravitational lensing of background galaxies. We use a 139 square degree contiguous patch of DES data from the Science Verification (SV) period of observations. Using large scale measurements, we constrain the matter density of the Universe as Ωm = 0.31 ± 0.09 and the clustering amplitude of the matter power spectrum as σ8 = 0.74 ± 0.13 after marginalizing over seven nuisance parameters and three additional cosmological parameters. This translates into S8 Ξ σ8more » (Ωm/0.3)0.16 = 0.74 ± 0.12 for our fiducial lens redshift bin at 0.35 < z < 0.5, while S8 = 0.78 ± 0.09 using two bins over the range 0.2 < z < 0.5. We study the robustness of the results under changes in the data vectors, modelling and systematics treatment, including photometric redshift and shear calibration uncertainties, and find consistency in the derived cosmological parameters. We show that our results are consistent with previous cosmological analyses from DES and other data sets and conclude with a joint analysis of DES angular clustering and galaxy-galaxy lensing with Planck CMB data, Baryon Accoustic Oscillations and Supernova type Ia measurements.« less

  8. DRAFT - Design of Radiological Survey and Sampling to Support Title Transfer or Lease of Property on the Department of Energy Oak Ridge Reservation

    SciTech Connect (OSTI)

    Cusick L.T.

    2002-09-25

    The U.S. Department of Energy (DOE) owns, operates, and manages the buildings and land areas on the Oak Ridge Reservation (ORR) in Oak Ridge, Tennessee. As land and buildings are declared excess or underutilized, it is the intent of DOE to either transfer the title of or lease suitable property to the Community Reuse Organization of East Tennessee (CROET) or other entities for public use. It is DOE's responsibility, in coordination with the U.S. Environmental Protection Agency (EPA), Region 4, and the Tennessee Department of Environment and Conservation (TDEC), to ensure that the land, facilities, and personal property that are to have the title transferred or are to be leased are suitable for public use. Release of personal property must also meet site requirements and be approved by the DOE contractor responsible for site radiological control. The terms title transfer and lease in this document have unique meanings. Title transfer will result in release of ownership without any restriction or further control by DOE. Under lease conditions, the government retains ownership of the property along with the responsibility to oversee property utilization. This includes involvement in the lessee's health, safety, and radiological control plans and conduct of site inspections. It may also entail lease restrictions, such as limiting access to certain areas or prohibiting digging, drilling, or disturbing material under surface coatings. Survey and sampling requirements are generally more rigorous for title transfer than for lease. Because of the accelerated clean up process, there is an increasing emphasis on title transfers of facilities and land. The purpose of this document is to describe the radiological survey and sampling protocols that are being used for assessing the radiological conditions and characteristics of building and land areas on the Oak Ridge Reservation that contain space potentially available for title transfer or lease. After necessary surveys and

  9. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the Harshaw Chemical Company, Cleveland, Ohio

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1984-04-01

    During the MED/AEC era, the Harshaw Chemical Company processed large quantities of normal uranium to produce both oxide and fluoride compounds. This work was done under contract to MED and its successor, AEC. Records indicated that at the time the AEC contract was terminated, the facility was decontaminated by Harshaw and released from AEC control in 1960. However, a search of AEC records indicated that documentation was insufficient to determine whether the decontamination work was adequate by current guidelines. Hence, a radiological assessment of the site ws initiated in 1976. The entire grounds and all buildings were surveyed using surface survey instruments to detect surface contamination and radiation detectors to determine general radiation levels. Extensive surface contamination was found throughout the site. While the major contamination was found in Plant C, significant levels of contamination also were found in 16 other buildings and at 32 exterior locations. The contaminating material seemed to be normal uranium exclusively. Air samples were taken at numerous indoor locations throughout the site, but no elevated levels of radon were detected. This was as expected since normal uranium has been separated from radium and hence radon levels are very low. Several soil samples were taken from around the site. Analyses of these samples indicated extensive soil contamination, as well as suspected contamination of the river bed in the vicinity of the plant outfall. Scheduled subsurface investigation of the site, as well as of the river bed and sewer system, have not been conducted. Levels of contamination at this site are significantly above guidelines for release of the site for unrestricted use. 57 figures, 7 tables.

  10. Results of the radiological survey at the ALCOA Research Laboratory, 600 Freeport Road, New Kensington, Pennsylvania (ANK001). Environmental Restoration and Waste Management Non-Defense Programs

    SciTech Connect (OSTI)

    Foley, R.D.; Brown, K.S.

    1992-10-01

    At the request of the US Department of Energy (DOE), a team from Oak Ridge National Laboratory conducted a radiological survey at the ALCOA Research Laboratory, 600 Freeport Road, New Kensington, Pennsylvania. The survey was performed on November 12, 1991. The purpose of the survey was to determine whether the property was contaminated with radioactive residues, principally {sup 238}U, as a result of work done for the Manhattan Engineer District in 1944. The survey included measurement of direct alpha and beta-gamma levels in the northeast comer of the basement of Building 29, and the collection of a debris sample from a floor drain for radionuclide analysis. The survey area was used for experimental canning of uranium slugs prior to production activities at the former New Kensington Works nearby.

  11. Formerly utilized MED/AEC sites Remedial Action Program. Radiological survey of the Albany Metallurgical Research Center, United States Bureau of Mines, Albany, Oregon

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1983-06-01

    During the periods 1954 to 1956 and 1960 to 1971, the Albany Metallurgical Research Center (AMRC) was engaged in metallurgical operations that included melting, machining, welding, and alloying of thorium. In addition, research on alloys of uranium and thorium started in 1955 and continued until suspended in 1978. Records indicated that at the time the original AEC contract was terminated, buildings and surrounding areas were decontaminated to the general guidelines provided by the AEC. Those guidelines were not as specific as current guidelines, and detailed records of the final decontamination were not documented. Because of that, radiological assessemnt of this site was initiated in June 1978. During June and July 1978, a radiological survey of the grounds and the buildings was completed. Certain buildings were designated as areas where no survey was necessary; however, it was decided by the ANL survey team to at least perform floor surveys in those buildings. Significant levels of contamination, both loose and fixed, were found in 10 of the 33 buildings surveyed. In addition, about 60 contaminated areas, including 17 with loose contamination, were found outside the buildings. Surveys of the sanitary sewers, the Albany sewage treatment plant and the Ohling Farm showed no significant contamination. Significant levels of contamination were found in the septic system behind Buildings 12 and 17. Air samples taken throughout the site revealed no radon concentrations in excess of the limits proposed by the US Surgeon General (10 CFR 712).

  12. Radiological Assessment Survey of the Vance road Facility Source Vault Building Materials, Oak Ridge Institute for Science and Education, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    J. R. Morton

    2000-09-01

    From the 1950s, the Vance Road laboratory was the site of extensive nuclear medical research and involved the used of numerous radionuclides. These nuclides were stored in a source vault stored on the first floor of the facility. Nuclear medical research is no longer conducted in this facility, and the source vault was remediated in preparation for converting the area to office space and general use. The Environmental Survey and Site Assessment Program (ESSAP) of ORISE performed a radiological assessment survey of the source vault and its associated miscellaneous building materials and laboratory equipment in preparation for the conversion to general use space.

  13. An aerial radiological survey of the Tonopah Test Range including Clean Slate 1,2,3, Roller Coaster, decontamination area, Cactus Springs Ranch target areas. Central Nevada

    SciTech Connect (OSTI)

    Proctor, A.E.; Hendricks, T.J.

    1995-08-01

    An aerial radiological survey was conducted of major sections of the Tonopah Test Range (TTR) in central Nevada from August through October 1993. The survey consisted of aerial measurements of both natural and man-made gamma radiation emanating from the terrestrial surface. The initial purpose of the survey was to locate depleted uranium (detecting {sup 238}U) from projectiles which had impacted on the TTR. The examination of areas near Cactus Springs Ranch (located near the western boundary of the TTR) and an animal burial area near the Double Track site were secondary objectives. When more widespread than expected {sup 241}Am contamination was found around the Clean Slates sites, the survey was expanded to cover the area surrounding the Clean Slates and also the Double Track site. Results are reported as radiation isopleths superimposed on aerial photographs of the area.

  14. A Radiological Survey Approach to Use Prior to Decommissioning: Results from a Technology Scanning and Assessment Project Focused on the Chornobyl NPP

    SciTech Connect (OSTI)

    Milchikov, A.; Hund, G.; Davidko, M.

    1999-10-20

    The primary objectives of this project are to learn how to plan and execute the Technology Scanning and Assessment (TSA) approach by conducting a project and to be able to provide the approach as a capability to the Chernobyl Nuclear Power Plant (ChNPP) and potentially elsewhere. A secondary objective is to learn specifics about decommissioning and in particular about radiological surveying to be performed prior to decommissioning to help ChNPP decision makers. TSA is a multi-faceted capability that monitors and analyzes scientific, technical, regulatory, and business factors and trends for decision makers and company leaders. It is a management tool where information is systematically gathered, analyzed, and used in business planning and decision making. It helps managers by organizing the flow of critical information and provides managers with information they can act upon. The focus of this TSA project is on radiological surveying with the target being ChNPP's Unit 1. This reactor was stopped on November 30, 1996. At this time, Ukraine failed to have a regulatory basis to provide guidelines for nuclear site decommissioning. This situation has not changed as of today. A number of documents have been prepared to become a basis for a combined study of the ChNPP Unit 1 from the engineering and radiological perspectives. The results of such a study are expected to be used when a detailed decommissioning plan is created.

  15. ORNL-5680 Radiological Surveys

    Office of Legacy Management (LM)

    ... This conclusion is based on measurements of 226Ra in ... water sediment samples represents only that percentage of the activity (normally between 50 and 100%) available by hot ...

  16. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the Middlesex Municipal Landfill, Middlesex, New Jersey. Final report

    SciTech Connect (OSTI)

    Leggett, R W; Cottrell, W D; Goldsmith, W A; Christian, D J; Haywood, F F; Wagner, E B; Crawford, D J; Doane, R W; Shinpaugh, W H

    1980-04-01

    A radiological survey was conducted at the Middlesex Municipal Landfill in Middlesex, New Jersey. In 1948, dirt contaminated with pitchblende ores was brought to this site from a former ore sampling plant in Middlesex. This survey was conducted in order to characterize the present radiological condition of the site and to determine the extent to which contamination is being transported from the site by natural means such as by drainage. The survey included measurement of (1) radionuclide concentrations in surface and subsurface soil on the site; (2) radionuclide concentrations in surface and subsurface water on the site and in Bound Brook; (3) beta-gamma dose rates and external gamma radiation levels on and near the site; and (4) the rate of /sup 222/Rn emanation from the soil on the site. It was found that most of the contamination on the site is in the top 14 ft of soil; however, there is little contamination of surface soil on the site. Average radon emanation rates, average external gamma radiation levels, and average beta-gamma dose rates on the site do not appear to be significantly higher than background levels. Furthermore, radionuclide concentrations in water taken from Bound Brook near the site were far below guide values stated in federal guidelines.

  17. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the former Watertown arsenal property, Site 34 and Site 41, Watertown, Massachusetts

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1983-10-01

    During the MED/AEC era, work involving radioactive materials was conducted at various sites within the arsenal complex. Building 34 housed a uranium machine shop, and a portion of Building 41 contained a foundry that was used for uranium work. Information provided by site personnel indicated that only depleted uranium was used in these buildings. Results of radiological analyses of contaminated material found at these sites indicated depleted uranium with uranium-236. Both buildings have been razed. The remnants still in place consist of the concrete floor slabs, access drives, and underground utility service trenches. This area is currently under the control of the Watertown Redevelopment Authority of Watertown, Massachusetts. During the period from June 25 through July 1, 1981, the Argonne National Laboratory (ANL), Occupational Health and Safety Division (OHS) Radiological Survey Group (RSG), conducted a radiological survey of Building Sites 34 and 41 at the direction of the US Department of Energy. Significant levels of contamination were found at 33 locations on the pad of Site 34 and in 5 out of 15 soild corings from the perimeter of the pad. No contamination was found on the pad of Site 41; however, two-thirds of this pad was covered with soil up to 4 ft thick. One of the 14 soil corings taken adjacent to the pad of Site 41 had elevated levels of uranium. Levels of contamination in excess of criteria, as identified in ANSI 13.12 and NRC Guidelines, were found at this site. The analyses of the samples from the sewer access points also revealed uranium and radium-226 anomalies. Therefore, according to NRC guidelines dated July 1982, it must be concluded that they are contaminated.

  18. INTERIM REPORT--INDEPENDENT VERIFICATION SURVEY OF SECTION 3, SURVEY UNITS 1, 4 AND 5 EXCAVATED SURFACES, WHITTAKER CORPORATION, REYNOLDS INDUSTRIAL PARK, TRANSFER, PENNSYLVANIA DCN: 5002-SR-04-0"

    SciTech Connect (OSTI)

    ADAMS, WADE C

    2013-04-18

    At Pennsylvania Department of Environmental Protection's request, ORAU's IEAV program conducted verification surveys on the excavated surfaces of Section 3, SUs 1, 4, and 5 at the Whittaker site on March 13 and 14, 2013. The survey activities included visual inspections, gamma radiation surface scans, gamma activity measurements, and soil sampling activities. Verification activities also included the review and assessment of the licensee's project documentation and methodologies. Surface scans identified four areas of elevated direct gamma radiation distinguishable from background; one area within SUs 1 and 4 and two areas within SU5. One area within SU5 was remediated by removing a golf ball size piece of slag while ORAU staff was onsite. With the exception of the golf ball size piece of slag within SU5, a review of the ESL Section 3 EXS data packages for SUs 1, 4, and 5 indicated that these locations of elevated gamma radiation were also identified by the ESL gamma scans and that ESL personnel performed additional investigations and soil sampling within these areas. The investigative results indicated that the areas met the release criteria.

  19. Radiological Control

    Directives, Delegations, and Requirements [Office of Management (MA)]

    2009-06-16

    The Department of Energy (DOE) has developed this Standard to assist line managers in meeting their responsibilities for implementing occupational radiological control programs.

  20. Radiological Control

    Energy.gov (indexed) [DOE]

    ... of Radiological Conditions ......of this Standard to the extent appropriate to facility ... the underlying reasons or causes for the success or failure ...

  1. Formerly utilized MED/AEC sites remedial action program: radiological survey of the former Virginia-Carolina Chemical Corporation Uranium Recovery Pilot Plant, Nichols, Florida. Final report

    SciTech Connect (OSTI)

    Haywood, F F; Doane, R W; Goldsmith, W A; Shinpaugh, W H; Crawford, D J; Fox, W F; Leggett, R W; Stone, D R

    1980-01-01

    The results of a radiological survey conducted at the site of a former uranium recovery pilot plant operated by the Virginia-Carolina Chemical Corporation is presented. All that remains of this operation is a concrete pad situated within the boundary of a phosphate products plant now operated by Conserv, Inc., at the Nichols, Florida site. The survey included measurements designed to characterize the residual radioactivity in the vicinity of this pilot plant and to compare the quantities with federal guidelines for the release of decontaminated property for unrestricted use. The results of this survey indicate that only small quantities of radioactivity exist above normal background levels for that area. Some soil contamination was found in the vicinity of a concrete pad on which the pilot plant stood. Much of this contamination was due to /sup 226/Ra and /sup 238/U. Some beta-gamma dose rates in excess of applicable guidelines were observed in this same area. External gamma-ray exposure rates at 1 m above the ground range from 20 to 100 ..mu..R/hr. None of the direct measurements of alpha contamination were above guideline levels.

  2. INDEPENDENT VERIFICATION SURVEY SUMMARY AND RESULTS FOR SUB-SLAB SOILS ASSOCIATED WITH THE FORMER BUILDING K-33, OAK RIDGE, TENNESSEE

    SciTech Connect (OSTI)

    NICK A. ALTIC

    2012-09-20

    At DOE’s request, ORAU conducted confirmatory surveys of the K-33 sub-slab soil during the period of August 2011 through May 2012. The survey activities included visual inspections and measurement and sampling activities. LSRS was forthcoming with information relating to surface scan results. Scans performed by the contractor were of adequate coverage and overall data appear to represent actual site conditions. However, the LSRS technicians failed to identify several areas of elevated direct gamma radiation. Most of the samples taken by ORAU at locations of elevated instrument response were above the remediation concentration for one or more radionuclides of concern (ROC). The contractor was, however, quick to perform additional remediation of areas identified to have contamination above the guidelines. Further investigation by ORAU was not requested once additional remediation was completed. It is presumed the remediation contractor’s future PCCR will present detailed and conclusive evidence that K-33 sub-slab soils either comply or do not comply with record of decision (ROD) criteria. However, ORAU concludes, based on both independent verification (IV) data and data provided by LSRS, that the remediation contractor followed appropriate and applicable procedures and that the associated data adequately represent site conditions.

  3. Radiological Control

    National Nuclear Security Administration (NNSA)

    RADIOLOGICAL CONTROL U.S. Department of Energy SAFT Washington, D.C. 20585 DISTRIBUTION ... DOE-STD-1098-2008 ii This document is available on the Department of Energy Technical ...

  4. Formerly utilized MED/AEC sites Remedial Action Program. Radiological survey of the former Watertown Arsenal property GSA site Watertown, Massachusetts

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1983-10-01

    The complete radiological survey of all the buildings located on the GSA site revealed no contamination. However, significant contamination was found on the site grounds. A total of approximately 6 m/sup 2/ of surface area exhibited elevated radiation levels. The area of contamination is centered around Section I (the burn area) and spreads out from this point. The contamination includes the subsurface, descending to the water table at the 6-ft level in some places. The contamination is primarily reprocessed depleted uranium. The ambient radiation level in the vicinity of the contamination as measured with a pressurized ionization chamber is significantly above background levels (up to 18 ..mu..R/h). As expected, no significant levels of radon contamination were found in any of the air samples. These levels of contamination of exceed the criteria as defined in ANSI 13.12 and the NRC Guidelines. The ambient radiation levels (up to 18 ..mu..R/h) are not in excess of criteria as defined in Appendix 6.

  5. treaty verification | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    treaty verification Global Material Security The mission of the Office of Global Material Security (GMS) is to help partner countries secure and account for nuclear weapons, weapons-useable nuclear and radiological materials, as well as to build capacity to deter, detect and interdict the illicit trafficking of such materials. GMS achieves

  6. Formerly utilized MED/AEC sites remedial action program. Radiological survey of Chemicals Group, Olin Corporation (formerly Blockson Chemical Company) Joliet, Illinois March 27-November 28, 1978

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Mayes, C.B.; Justus, A.L.

    1983-05-01

    A comprehensive radiological survey was conducted at Building 55 of the Chemicals Group, Olin Corporation, Joliet, Illinois. The survey included measurements of alpha and beta-gamma contamination, both fixed and removable; beta-gamma exposure readings at contact and at 1 m (3 ft) above the floor or ground level; estimates of radon-daughter concentrations in the air as airborne contaminants; and determinations of concentrations of /sup 137/Cs, the /sup 232/Th decay chain, the /sup 226/Ra decay chain, and uranium in the soil on the site. Thirty-three spots or localized areas and three larger general areas within Building 55 exceeded the allowable limits as given in the Draft ANSI Standard N13.12 for uranium, and the general roof area exceeded the acceptable limits for radium-226. Additionally, two spots or localized areas on the roof substantially exceeded those limits. In 15 instances, the contamination was found to be removable from surfaces and readily available for transfer to other locations. Concentrations of radon daughters in the air of the building, as measured by grab-sampling techniques, were below the limit of 0.01 WL above background as given in the Surgeon General's Guidelines. Analyses of ten soil samples from the site indicated significantly elevated concentrations of uranium and radium at two sampling locations near Building 55. Based on a hypothetical exposure scenario, the maximum potential dose equivalent to an individual for external penetrating radiation resulting from exposure to radioactivity at this site was calculated to be 340 mrem per year. The internal radiation 50-year dose commitments from potential inhalation/ingestion of radioactive material were calculated to be 8300 mrem to the lung, 120 mrem to the bone, 26 mrem to the kidney, and 250 mrem whole body. Few individuals are expected to acquire such doses or dose commitments annually.

  7. Formerly utilized MED/AEC sites remedial-action program. Radiological survey of Kent Chemical Laboratory, The University of Chicago, Chicago, Illinois, September 7-13, 1977

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Mayes, C.B.; Justus, A.L.

    1982-05-01

    A comprehensive radiological survey was conducted at the Kent Chemical Laboratory at the University of Chicago, Chicago, Illinois. General radiochemistry and/or physics research was performed at this facility during the MED/AEC era in the 1940s. The building is now used as laboratories, offices, and classrooms. The survey was undertaken to determine the location and quantities of any radioactive materials remaining from the MED/AEC operations. Nineteen spots of contamination possibly resulting from MED/AEC occupancy in 12 rooms exceeded the allowable limits for /sup 226/Ra and /sup 239/Pu as given in the ANSI Standard N13.12. Under current use conditions, the potential for radiation exposure to occupants of this building from these sources of contamination is remote. Concentrations of radon daughters in the air of the building were below the limit of 0.01 Working Level above background as given in the Surgeon General's Guidelines. Concentrations of radionuclides in soil samples from near the laboratory were essentially at background levels. The maximum potential dose for external penetrating radiation resulting from exposure to the radioactivity remaining from MED/AEC operations was calculated to be 500 mrem a year, which is equal to the 500 mrem standard for an individual in an uncontrolled area. In order to reduce the potential for radiation exposure, remedial measures such as stabilization of the contamination in place would be applicable as a short-term measure. In order to reduce the risk in the event that building modifications take place in the future, health physics procedures and coverage are recommended. The long-term solution would involve decontamination by removal of the radioactive residues from the 12 rooms or areas where contamination possibly resulting from MED/AEC activities was detected.

  8. Formerly utilized MED/AEC sites remedial action program. Radiological survey of Eckhart Hall, the University of Chicago, Chicago, Illinois, September 14, 1976-March 22, 1977

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Boggs Mayes, C.; Justus, A.L.

    1982-05-01

    A comprehensive radiological survey was conducted at the Eckhart Hall at the University of Chicago, Chicago, Illinois. General radiochemistry and/or physics research was performed at this facility during the MED/AEC era in the 1940s. The building is now used as laboratories, offices, and classrooms. Survey measurements included alpha and beta-gamma contamination determinations, both fixed and removable; beta-gamma exposure readings at contact and at 1 m (3 ft); estimates of radon-daughter concentrations in the air; and determination of concentrations of /sup 137/Cs, the /sup 232/Th decay chain, the /sup 226/Ra decay chain, and uranium in the soil on the site. Thirteen spots of contamination were found to be fixed to or under existing surfaces and not readily available for transfer to other locations. Under current use conditions, the potential for radiation exposure to occupants of this building from these sources of contamination is remote. Concentrations of radon daughters in the air of the building were less than the limit of 0.01 Working Level (WL) above background. No long-lived radionuclides were detected in any air sample. Concentrations of radionuclides in soil samples collected around the facility indicated background levels. The presumed maximum potential internal radiation 50-year dose commitments from inhalation/ingestion of contamination remaining from MED/AEC activities were calculated to be less than 25% of the appropriate annual standards for an individual in an uncontrolled area. Remedial measures such as stabilization of the contamination in place would be applicable as a short-term measure. In order to reduce the risk in the event that building modifications take place in the future, health physics procedures and coverage are recommended. The long-term solution would involve decontamination by removal of the radioactive residues.

  9. Formerly utilized MED/AEC sites remedial-action program. Radiological survey of Ryerson Physical Laboratory, The University of Chicago, Chicago, Illinois, September 11-25, 1976

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Mayes, C.B.; Justus, A.L.

    1982-05-01

    A comprehensive radiological survey was conducted at the Ryerson Physical Laboratory at the University of Chicago, Chicago, Illinois. General radiochemistry and/or physics research was performed at this facility during the MED/AEC era in the 1940s. The building is now used as laboratories, offices, and classrooms. The survey was undertaken to determine the location and quantities of any radioactive materials remaining from the MED/AEC activities. Forty spots of contamination in 26 rooms possibly resulting from MED/AEC occupancy exceeded the allowable limits as given in ANSI Standard N13.12 for Group 1 nuclides. The potential for radiation exposure to occupants of this building from these sources of contamination is remote under current use conditions. Concentrations of radon daughters in the air of the building were less than the limit of 0.01 WL above background as given in the Surgeon General's Guidelines. Concentrations of radionuclides in soil samples collected around the facility indicated background levels. The presumed maximum potential dose for external penetrating radiation resulting from exposure to the radioactivity remaining from MED/AEC operations was calculated to be 140 mrem a year, which is 30% of the 500-mrem standard for an individual in an uncontrolled area. In order to reduce the potential for radiation exposure, remedial measures such as stabilization of the contamination in place would be applicable as a short-term measure. In order to reduce the risk in the event that building modifications take place in the future, health physics procedures and coverage are recommended. The long-term solution would involve decontamination by removal of the radioactive residues from the 26 rooms or areas where contamination possibly resulting from MED/AEC activities was detected.

  10. In-Situ Radiological Surveys to Address Nuclear Criticality Safety Requirements During Remediation Activities at the Shallow Land Disposal Area, Armstrong County, Pennsylvania - 12268

    SciTech Connect (OSTI)

    Norris, Phillip; Mihalo, Mark; Eberlin, John; Lambert, Mike; Matthews, Brian

    2012-07-01

    Cabrera Services Inc. (CABRERA) is the remedial contractor for the Shallow Land Disposal Area (SLDA) Site in Armstrong County Pennsylvania, a United States (US) Army Corps of Engineers - Buffalo District (USACE) contract. The remediation is being completed under the USACE's Formerly Utilized Sites Remedial Action Program (FUSRAP) which was established to identify, investigate, and clean up or control sites previously used by the Atomic Energy Commission (AEC) and its predecessor, the Manhattan Engineer District (MED). As part of the management of the FUSRAP, the USACE is overseeing investigation and remediation of radiological contamination at the SLDA Site in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), 42 US Code (USC), Section 9601 et. seq, as amended and, the National Oil and Hazardous Substance Pollution Contingency Plan (NCP), Title 40 of the Code of Federal Regulations (CFR) Section 300.430(f) (2). The objective of this project is to clean up radioactive waste at SLDA. The radioactive waste contains special nuclear material (SNM), primarily U-235, in 10 burial trenches, Cabrera duties include processing, packaging and transporting the waste to an offsite disposal facility in accordance with the selected remedial alternative as defined in the Final Record of Decision (USACE, 2007). Of particular importance during the remediation is the need to address nuclear criticality safety (NCS) controls for the safe exhumation and management of waste containing fissile materials. The partnership between Cabrera Services, Inc. and Measutronics Corporation led to the development of a valuable survey tool and operating procedure that are essential components of the SLDA Criticality Safety and Material Control and Accountability programs. Using proven existing technologies in the design and manufacture of the Mobile Survey Cart, the continued deployment of the Cart will allow for an efficient and reliable methodology to

  11. Formerly utilized MED/AEC sites remedial action program: radiological survey of the Building Site 421, United States, Watertown Arsenel, Watertown, MA. Final report

    SciTech Connect (OSTI)

    1980-02-01

    This report contains the results of surveys of the current radiological condition of the Building Site 421, United States Arsenal Watertown, Watertown, Massachusetts. Findings of this survey indicate there are four spots involving an area of less than 6000 cm/sup 2/ of identifiable low-level residual radioactivity on the concrete pad which is all that remains of Building Site 421. The largest spot is approximately 5000 cm/sup 2/. The other three spots are 100 cm/sup 2/ or less. The beta-gamma readings at these spots are 8.4 x 10/sup 2/ dis/min-100 cm/sup 2/, 2.2 x 10/sup 5/ dis/min-100 cm/sup 2/, 2.2 x 10/sup 5/ dis/min-100 cm/sup 2/ and 8.5 x 10/sup 4/ dis/min-100 cm/sup 2/. No alpha contamination was found at these locations. Gamma spectral analysis of a chip of contaminated concrete from one of the spots indicates that the contaminant is natural uranium. This contamination is fixed in the concrete and does not present an internal or external exposure hazard under present conditions. A hypothetical hazard analysis under a conservative set of assumed conditions indicates minimal internal hazard. The highest End Window contact reading was 0.09 mR/h. None of the other three spots indicated an elevated direct reading with the End Window Detector. Radon daughter concentrations were determined at three locations on the Building 421 pad. These were 0.00013 WL, 0.00011 WL and 0.00009 WL. According to the Surgeon General's Guidelines found in 10 CFR 712, radon daughter concentrations below 0.03 WL do not require remedial action in structures other than private dwellings and schools. Soil samples taken about the site indicate no elevated levels above the natural background levels in the soil. A gamma spectral analysis of a water sample obtained from the storm sewer line near the Building 421 pad indicates no elevated radioactivity in the sample. It was therefore felt that no contamination is present in this sewer.

  12. I COMPREHENSIVE RADIOLOGICAL SURVEY I

    Office of Legacy Management (LM)

    ... Atomic Power Laboratory (KAPL) in Schenectady, New York. Receipt of additional wastes was ... surface soil, and micrometeorological conditions (e.g. surface wind speed and direction). ...

  13. For S Radiological

    Office of Legacy Management (LM)

    ? . -. .- * -* (\/If.r.-5- .* , d- For S Radiological ' mer Bridgepo pecial Metals Adrian, Survey of the Irt Brass Company Extrusion Plant, Michigan / /f?t' . ( F. F. Haywood H. W. Dickson W. D. Cottrell W. H. Shinpaugh _ : I., _-. .I ( ._ rc/ DOE/EV-0005128 ORNL-57 13 / J. E. Burden 0. R. Stone R. W. Doane W. A. Goldsmith 4 , Printed in the United States of America. Available from National Technical Information Service U.S. Department of Commerce 5285 Port Royal Road, Springfield, Virginia

  14. Supplemental Radiological Survey Plan for the Lease of the Rooms Associated with C107 of Building K-1006 at the East Tennessee Technology Park, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    Blevins M.F.

    2010-09-01

    In 1998, a portion of Bldg. K-1006 was leased to the Community Reuse Organization of East Tennessee (CROET) as part of the reindustrialization efforts at the East Tennessee Technology Park (ETTP). The facility was subleased and is being used as an analytical laboratory. The 1998 lease did not include rooms C107, C107-A, C107-B, C107-C, and C107-D. The lease of these rooms is now desired. These rooms comprise the area to be surveyed. The building was constructed as a laboratory facility to support the gaseous diffusion uranium enrichment process. It also contains offices and administrative spaces for laboratory personnel. After the gaseous diffusion process was shut down in the mid-1980s, the building was used to provide research and development support to ETTP environmental, safety, and health programs; the Toxic Substances Control Act Incinerator; the Central Neutralization Facility; and other multi-site waste treatment activities. It also served as the chemistry laboratory for the Environmental Technology Technical Services Organization. The activities currently conducted in Bldg. K-1006 utilize a variety of analytical techniques. Some of the major techniques being employed are X-ray analysis, electron microanalysis, and spectrochemical analysis. In 1998, a portion of Bldg. K-1006 was leased to CROET as part of the reindustrialization efforts at ETTP. The facility was subleased and is being used as an analytical laboratory. The 1998 lease did not include Rooms C107, C107-A, C107-B, C107-C, and C107-D. Some demolition of furniture and decontamination activities has taken place for Rooms C 107 and C 107-B since the last radiological survey of those rooms. In March 2009, a final remedial action (RA) was performed for the Bldg. K-1006 north basement sump. The Bldg. K-1006 north basement sump is a nominal 30-in.-diameter, 36-in.-deep concrete structure in the north corner of room C107B. The building receives groundwater in-leakage that is periodically pumped to the

  15. Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... of candidates for Radiological Control Technician (RCT) and for RCT Supervisor. ... OEBs as indicated in DOE's Radiological Control Standard (RCS) and the RCT Training ...

  16. Estimating radiological background using imaging spectroscopy

    SciTech Connect (OSTI)

    Bernacki, Bruce E.; Schweppe, John E.; Stave, Sean C.; Jordan, David V.; Kulisek, Jonathan A.; Stewart, Trevor N.; Seifert, Carolyn E.

    2014-06-13

    Optical imaging spectroscopy is investigated as a method to estimate radiological background by spectral identification of soils, sediments, rocks, minerals and building materials derived from natural materials and assigning tabulated radiological emission values to these materials. Radiological airborne surveys are undertaken by local, state and federal agencies to identify the presence of radiological materials out of regulatory compliance. Detection performance in such surveys is determined by (among other factors) the uncertainty in the radiation background; increased knowledge of the expected radiation background will improve the ability to detect low-activity radiological materials. Radiological background due to naturally occurring radiological materials (NORM) can be estimated by reference to previous survey results, use of global 40K, 238U, and 232Th (KUT) values, reference to existing USGS radiation background maps, or by a moving average of the data as it is acquired. Each of these methods has its drawbacks: previous survey results may not include recent changes, the global average provides only a zero-order estimate, the USGS background radiation map resolutions are coarse and are accurate only to 1 km – 25 km sampling intervals depending on locale, and a moving average may essentially low pass filter the data to obscure small changes in radiation counts. Imaging spectroscopy from airborne or spaceborne platforms can offer higher resolution identification of materials and background, as well as provide imaging context information. AVIRIS hyperspectral image data is analyzed using commercial exploitation software to determine the usefulness of imaging spectroscopy to identify qualitative radiological background emissions when compared to airborne radiological survey data.

  17. Gamma radiological surveys of the Oak Ridge Reservation, Paducah Gaseous Diffusion Plant, and Portsmouth Gaseous Diffusion Plant, 1990-1993, and overview of data processing and analysis by the Environmental Restoration Remote Sensing Program, Fiscal Year 1995

    SciTech Connect (OSTI)

    Smyre, J.L.; Moll, B.W.; King, A.L.

    1996-06-01

    Three gamma radiological surveys have been conducted under auspices of the ER Remote Sensing Program: (1) Oak Ridge Reservation (ORR) (1992), (2) Clinch River (1992), and (3) Portsmouth Gaseous Diffusion Plant (PORTS) (1993). In addition, the Remote Sensing Program has acquired the results of earlier surveys at Paducah Gaseous Diffusion Plant (PGDP) (1990) and PORTS (1990). These radiological surveys provide data for characterization and long-term monitoring of U.S. Department of Energy (DOE) contamination areas since many of the radioactive materials processed or handled on the ORR, PGDP, and PORTS are direct gamma radiation emitters or have gamma emitting daughter radionuclides. High resolution airborne gamma radiation surveys require a helicopter outfitted with one or two detector pods, a computer-based data acquisition system, and an accurate navigational positioning system for relating collected data to ground location. Sensors measure the ground-level gamma energy spectrum in the 38 to 3,026 KeV range. Analysis can provide gamma emission strength in counts per second for either gross or total man-made gamma emissions. Gross count gamma radiation includes natural background radiation from terrestrial sources (radionuclides present in small amounts in the earth`s soil and bedrock), from radon gas, and from cosmic rays from outer space as well as radiation from man-made radionuclides. Man-made count gamma data include only the portion of the gross count that can be directly attributed to gamma rays from man-made radionuclides. Interpretation of the gamma energy spectra can make possible the determination of which specific radioisotopes contribute to the observed man-made gamma radiation, either as direct or as indirect (i.e., daughter) gamma energy from specific radionuclides (e.g., cesium-137, cobalt-60, uranium-238).

  18. ORISE: Characterization surveys

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    objective characterization surveys to define the extent of radiological contamination at sites scheduled for decontamination and decommissioning (D&D). A fundamental...

  19. Radiological Control Manual

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

  20. Microsoft Word - Berger Radiological Conditions.doc

    Office of Legacy Management (LM)

    Dec. 2, 2009 1 Summary of Information Regarding Radiological Conditions of NFSS Vicinity Properties J. D. Berger, CHP DeNuke Contracting Services, Inc. Oak Ridge, TN The following is a summary of the information obtained from reviews of radiological survey reports, prepared by ORAU in support of the DOE Formerly Utilized Sites Remedial Action Program. These reports were obtained for review from the IVEA Program at ORAU/ORISE. A list of the reports, reviewed for this summary, is included at the

  1. Verification of Adaptive Systems

    SciTech Connect (OSTI)

    Pullum, Laura L; Cui, Xiaohui; Vassev, Emil; Hinchey, Mike; Rouff, Christopher; Buskens, Richard

    2012-01-01

    Adaptive systems are critical for future space and other unmanned and intelligent systems. Verification of these systems is also critical for their use in systems with potential harm to human life or with large financial investments. Due to their nondeterministic nature and extremely large state space, current methods for verification of software systems are not adequate to provide a high level of assurance for them. The combination of stabilization science, high performance computing simulations, compositional verification and traditional verification techniques, plus operational monitors, provides a complete approach to verification and deployment of adaptive systems that has not been used before. This paper gives an overview of this approach.

  2. Radiological/Nuclear Applications

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Radiological/Nuclear Applications Radiological/Nuclear Applications Radiological sensors in action, solutions for you. Radiological and Nuclear Capabilities-for Collaboration View our capability sheets: get details of what we do. Boron 10 Neutron Detector New Neutron Detector Materials How we deploy innovation radiiological-nuclear bubble In the mid-1990s, Los Alamos scientists were developing proton radiography techniques for a variety of applications and decided to try using muons instead of

  3. Radiological Technician Training

    Energy.gov (indexed) [DOE]

    Part 2 of 9 Radiological Control Technician Training Technician Qualification Standard ... . . . . . . . . 1 Phase I: RCT Academics Training . . . . . . . . . . . . . . . . . . . . ...

  4. Radiological Control Technician Training

    Energy Savers

    Part 8 of 9 Radiological Control Technician Training Oral Examination Boards Phase III ... Training of Oral Board Members ......

  5. Surveys

    Energy.gov [DOE]

    Surveys can be a useful way to gauge the opinions of your readers and learn more about your website's audiences, but you'll often need approval from the Office of Management and Budget (OMB) to run...

  6. Guidance on the Use of Hand-Held Survey Meters for radiological Triage: Time-Dependent Detector Count Rates Corresponding to 50, 250, and 500 mSv Effective Dose for Adult Males and Adult Females

    SciTech Connect (OSTI)

    Bolch, W.E.; Hurtado, J.L.; Lee, C.; Manger, Ryan P; Hertel, Nolan; Burgett, E.; Dickerson, W.

    2012-01-01

    In June 2006, the Radiation Studies Branch of the Centers for Disease Control and Prevention held a workshop to explore rapid methods of facilitating radiological triage of large numbers of potentially contaminated individuals following detonation of a radiological dispersal device. Two options were discussed. The first was the use of traditional gamma cameras in nuclear medicine departments operated as makeshift wholebody counters. Guidance on this approach is currently available from the CDC. This approach would be feasible if a manageable number of individuals were involved, transportation to the relevant hospitals was quickly provided, and the medical staff at each facility had been previously trained in this non-traditional use of their radiopharmaceutical imaging devices. If, however, substantially larger numbers of individuals (100 s to 1,000 s) needed radiological screening, other options must be given to first responders, first receivers, and health physicists providing medical management. In this study, the second option of the workshop was investigated by the use of commercially available portable survey meters (either NaI or GM based) for assessing potential ranges of effective dose (G50, 50Y250, 250Y500, and 9500 mSv). Two hybrid computational phantoms were used to model an adult male and an adult female subject internally contaminated with 241Am, 60Cs, 137Cs, 131I, or 192Ir following an acute inhalation or ingestion intake. As a function of time following the exposure, the net count rates corresponding to committed effective doses of 50, 250, and 500 mSv were estimated via Monte Carlo radiation transport simulation for each of four different detector types, positions, and screening distances. Measured net count rates can be compared to these values, and an assignment of one of four possible effective dose ranges could be made. The method implicitly assumes that all external contamination has been removed prior to screening and that the measurements be

  7. Verification Challenges at Low Numbers

    SciTech Connect (OSTI)

    Benz, Jacob M.; Booker, Paul M.; McDonald, Benjamin S.

    2013-06-01

    Many papers have dealt with the political difficulties and ramifications of deep nuclear arms reductions, and the issues of “Going to Zero”. Political issues include extended deterrence, conventional weapons, ballistic missile defense, and regional and geo-political security issues. At each step on the road to low numbers, the verification required to ensure compliance of all parties will increase significantly. Looking post New START, the next step will likely include warhead limits in the neighborhood of 1000 . Further reductions will include stepping stones at1000 warheads, 100’s of warheads, and then 10’s of warheads before final elimination could be considered of the last few remaining warheads and weapons. This paper will focus on these three threshold reduction levels, 1000, 100’s, 10’s. For each, the issues and challenges will be discussed, potential solutions will be identified, and the verification technologies and chain of custody measures that address these solutions will be surveyed. It is important to note that many of the issues that need to be addressed have no current solution. In these cases, the paper will explore new or novel technologies that could be applied. These technologies will draw from the research and development that is ongoing throughout the national laboratory complex, and will look at technologies utilized in other areas of industry for their application to arms control verification.

  8. Formerly utilized MED/AEC sites remedial action program. Radiological survey of Universal Cyclopes, Inc. , Titusville, Plant (formerly Vulcan Crucible Steel Company, Aliquippa, Pennsylvania, May 2-8, 1978

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Mundis, R.L.; Mayes, C.B.

    1982-05-01

    A radiological survey was conducted at the Universal Cyclops, Inc. Titusville Plant (formerly Vulcan Crucible Steel Company), in Aliquippa, Pennsylvania, to determine the location and quantities of any radioactive materials remaining on the site as a result of MED/AEC activities in the late 1940s. This facility was used for rolling uranium billets during the MED/AEC era. The survey included measurements of alpha and beta-gamma contamination, both fixed and removable; beta-gamma exposure readings at contact and at 1 m (3 ft) above the floor or ground level; and measurements of the concentrations of radon daughters in air and concentrations of /sup 137/Cs, the /sup 232/Th decay chain, the /sup 226/Ra decay chain, and uranium in the soil on the site. Fourteen spots of contamination exceeded the allowable limits for natural uranium. Under current use conditions, the potential for radiation exposure of occupants of the building from these sources of contamination is remote. Concentrations of radon daughters were below the 0.01 WL limit. Calculated radon concentrations based on the radon-daughter determinations ranged from 0.11 to 0.27 pCi/l. The concentration guide for /sup 222/Rn in uncontrolled areas is 3 pCi/l. Analysis of soil samples from the site indicated elevated concentrations of uranium (15.1 +- 0.7 to 109.0 +- 5.5 pCi/g) at one sampling location near the building. There currently are no regulatory limits for uranium concentration in soil, but, a proposed guide value is pCi/g. After evaluation of results of the survey, it was concluded that although some areas of the Universal Cyclops facility are contaminated, these areas do not pose a significant risk to the present occupants of the building. Nonetheless, in a few cases the contamination does exceed accepted guidelines. Remedial measures are indicated to bring the contaminated areas within the guidelines.

  9. Radiological Assistance Program

    Directives, Delegations, and Requirements [Office of Management (MA)]

    1992-04-10

    To establish Department of Energy (DOE) policy, procedures, authorities, and responsibilities for its Radiological Assistance Program. Canceled by DOE O 153.1.

  10. Office of Radiological Security

    National Nuclear Security Administration (NNSA)

    of physical security of radiological materials;

  11. Provision of mobile and man-portable radiation detection equipment;
  12. Regional cooperation on safeguards...

  13. Radiological Control Technician Training

    Energy.gov (indexed) [DOE]

    ... addresses the training requirements of 10 CFR 835.103 for Radiological Control Technicians, it must be supplemented with facility specific information to achieve full compliance. ...

  14. Radiological Control Technician Training

    Energy.gov (indexed) [DOE]

    7of 9 Radiological Control Technician Training Practical Training Phase II Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy ...

  15. Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    HANDBOOK RADIOLOGICAL CONTROL TECHNICIAN TRAINING U.S. Department of Energy AREA TRNG ... an implementation process for core training as recommended in chapter 14 to ...

  16. Radiological Control Technician Training

    Energy.gov (indexed) [DOE]

    Radiological Control Technician Training Facility Practical Training Attachment Phase IV Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of ...

  17. Verification Survey of the Building 4059 Site (Phase B); Post Historical Site Assessment Sites, Block 1; and Radioactive Materials Handling Facility HOldup Pond (Site 4614), Santa Susana Field Laboratory, The Boeing Company, Ventura County, California

    SciTech Connect (OSTI)

    T.J. Vitkus

    2008-06-06

    Confirm that the final radiological conditions were accurately and adequately described in the FSS documentation, relative to the established release criteria.

  18. Radiological Survey of Contaminated Installations of Research Reactor before Dismantling in High Dose Conditions with Complex for Remote Measurements of Radioactivity - 12069

    SciTech Connect (OSTI)

    Danilovich, Alexey; Ivanov, Oleg; Lemus, Alexey; Smirnov, Sergey; Stepanov, Vyacheslav; Volkovich, Anatoly

    2012-07-01

    Decontamination and decommissioning of the research reactors MR (Testing Reactor) and RFT (Reactor of Physics and Technology) has recently been initiated in the National Research Center (NRC) 'Kurchatov institute', Moscow. These research reactors have a long history and many installations - nine loop facilities for experiments with different kinds of fuel. When decommissioning nuclear facilities it is necessary to measure the distribution of radioactive contamination in the rooms and at the equipment at high levels of background radiation. At 'Kurchatov Institute' some special remote control measuring systems were developed and they are applied during dismantling of the reactors MR and RFT. For a survey of high-level objects a radiometric system mounted on the robotic Brokk vehicle is used. This system has two (4? and collimated) dose meters and a high resolution video camera. Maximum measured dose rate for this system is ?8.5 Sv/h. To determine the composition of contaminants, a portable spectrometric system is used. It is a remotely controlled, collimated detector for scanning the distribution of radioactive contamination. To obtain a detailed distribution of contamination a remote-controlled gamma camera is applied. For work at highly contaminated premises with non-uniform background radiation, another camera is equipped with rotating coded mask (coded aperture imaging). As a result, a new system of instruments for remote radioactivity measurements with wide range of sensitivity and angular resolution was developed. The experience and results of measurements in different areas of the reactor and at its loop installations, with emphasis on the radioactive survey of highly-contaminated samples, are presented. These activities are conducted under the Federal Program for Nuclear and Radiation Safety of Russia. Adaptation of complex remote measurements of radioactivity and survey of contaminated installations of research reactor before dismantling in high dose

  19. Real Time Quantitative Radiological Monitoring Equipment for Environmental Assessment

    SciTech Connect (OSTI)

    John R. Giles; Lyle G. Roybal; Michael V. Carpenter

    2006-03-01

    The Idaho National Laboratory (INL) has developed a suite of systems that rapidly scan, analyze, and characterize radiological contamination in soil. These systems have been successfully deployed at several Department of Energy (DOE) laboratories and Cold War Legacy closure sites. Traditionally, these systems have been used during the characterization and remediation of radiologically contaminated soils and surfaces; however, subsequent to the terrorist attacks of September 11, 2001, the applications of these systems have expanded to include homeland security operations for first response, continuing assessment and verification of cleanup activities in the event of the detonation of a radiological dispersal device. The core system components are a detector, a spectral analyzer, and a global positioning system (GPS). The system is computer controlled by menu-driven, user-friendly custom software designed for a technician-level operator. A wide variety of detectors have been used including several configurations of sodium iodide (NaI) and high-purity germanium (HPGe) detectors, and a large area proportional counter designed for the detection of x-rays from actinides such as Am-241 and Pu-238. Systems have been deployed from several platforms including a small all-terrain vehicle (ATV), hand-pushed carts, a backpack mounted unit, and an excavator mounted unit used where personnel safety considerations are paramount. The INL has advanced this concept, and expanded the system functionality to create an integrated, field-deployed analytical system through the use of tailored analysis and operations software. Customized, site specific software is assembled from a supporting toolbox of algorithms that streamline the data acquisition, analysis and reporting process. These algorithms include region specific spectral stripping, automated energy calibration, background subtraction, activity calculations based on measured detector efficiencies, and on-line data quality checks

  20. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the West Stands, New Chemistry Lab and Annex, and Ricketts Laboratory, the University of Chicago, Chicago, Illinois, August 31-September 2, 1977

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Mayes, C.B.; Justus, A.L.

    1982-05-01

    A radiological survey was conducted at the former locations of the West Stands, the New Chemistry Lab and Annex, and Ricketts Laboratory at the University of Chicago, Chicago, Illinois. General radiochemistry and/or physics research for the MED/AEC program was performed at these sites during the 1940s. The buildings have since been razed. The survey was undertaken to determine the presence of any radionuclides remaining from the MED/AEC operations that could have been spilled or released from the former structures. Environmental soil samples (corings) were collected from the areas where the West Stands, New Chemistry Lab and Annex, and Ricketts Laboratory once stood. The soil corings were taken at what appeared to be undisturbed locations near the sites of the three former facilities. Analyses of the soil corings included determination of the concentrations of /sup 137/Cs, the /sup 232/Th decay chain, the /sup 226/Ra decay chain, and uranium in the soil. The levels of uranium and the /sup 226/Ra decay chain found in the samples indicated that no concentrations above natural background levels were present. Slightly elevated levels of /sup 60/Co were found in soil taken from the top 5 cm of the ground at two sampling sites, but this activity was presumed to have been traceable to induced activity from contaminated stainless steel that had been stored in the area during operations not related to MED/AEC activities. No increased radiation dose attributable to exposure to residual radioactivity from MED/AEC activities is expected.

  21. Formerly utilized MED/AEC sites remedial action program. Radiological survey of The George Herbert Jones Chemical Laboratory, The University of Chicago, Chicago, Illinois, June 13-17, 1977

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Mayes, C.B.; Justus, A.L.

    1982-05-01

    A comprehensive radiological survey was conducted at George Herbert Jones Chemical Laboratory at the University of Chicago, Chicago, Illinois. Radiochemistry for the MED/AEC project was performed in this building in the 1940s. The building is now used as laboratories, offices, and classrooms. The survey was undertaken to determine the location and quantities of any radioactive materials remaining from the MED/AEC operations. Forty-three spots of contamination possibly resulting from MED/AEC occupancy in 17 rooms exceeded the allowable limits as given in the ANSI Standard N13.12. Under current use conditions, the potential for radiation exposure to occupants of this building from these sources of contamination is remote. Concentrations of radon daughters in the air of the building, as measured with grab-sampling techniques, were below the limit of 0.01 WL above background as given in the Surgeon General's Guidelines. No long-lived radionuclides were detected in any air sample. Concentrations of radionuclides in soil samples from near the laboratory generally indicated background levels. In order to reduce the potential for radiation exposure, remedial measures such as stabilization of the contamination in place would be applicable as a short-term measure. In order to reduce the risk in the event that building modifications take place in the future, health physics procedures and coverage are recommended. The long-term solution would involve decontamination by removal of the radioactive residues from the 17 rooms or areas where contamination possibly resulting from MED/AEC activities was detected.

  22. ORISE: Radiological program assessment services

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    ORISE focuses its radiological audit and assessment services in these key areas: Nondestructive assay (NDA) Radiological control programs Environmental monitoring programs ...

  1. Radiological Training for Tritium Facilities

    Energy Savers

    Change Notice No. 2 May 2007 DOE HANDBOOK RADIOLOGICAL TRAINING FOR TRITIUM FACILITIES ... Change Notice 2. Radiological Safety Training for Tritium Facilities ...

  2. Voltage verification unit

    DOE Patents [OSTI]

    Martin, Edward J.

    2008-01-15

    A voltage verification unit and method for determining the absence of potentially dangerous potentials within a power supply enclosure without Mode 2 work is disclosed. With this device and method, a qualified worker, following a relatively simple protocol that involves a function test (hot, cold, hot) of the voltage verification unit before Lock Out/Tag Out and, and once the Lock Out/Tag Out is completed, testing or "trying" by simply reading a display on the voltage verification unit can be accomplished without exposure of the operator to the interior of the voltage supply enclosure. According to a preferred embodiment, the voltage verification unit includes test leads to allow diagnostics with other meters, without the necessity of accessing potentially dangerous bus bars or the like.

  3. Employment Eligibility Verification

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Instructions for Employment Eligibility Verification Department of Homeland Security U.S. Citizenship and Immigration Services USCIS Form I-9 OMB No. 1615-0047 Expires 03/31/2016 Read all instructions carefully before completing this form. Anti-Discrimination Notice. It is illegal to discriminate against any work-authorized individual in hiring, discharge, recruitment or referral for a fee, or in the employment eligibility verification (Form I-9 and E-Verify) process based on that individual's

  4. Radiological Safety Analysis Code System.

    Energy Science and Technology Software Center (OSTI)

    2009-12-22

    Version 03 RSAC-6.2 can be used to model complex accidents and radiological consequences to individuals from the release of radionuclides to the atmosphere. A user can generate a fission product inventory; decay and ingrow the inventory during transport through processes, facilities, and the environment; model the downwind dispersion of the activity; and calculate doses to downwind individuals. Doses are calculated through the inhalation, immersion, ground surface and ingestion pathways. New to RSAC-6.2 are the abilitiesmore » to calculate inhalation from release to a room, inhalation from resuspension of activities, and a new model for dry deposition. Doses can now be calculated as close as 10 meters from the release point. RSAC-6.2 has been subjected to extensive independent verification and validation for use in performing safety-related dose calculations to support safety analysis reports. WinRP 2.0, a windows based overlay to RSAC-6.2, assists users in creating and running RSAC-6.2 input files. RSAC-6, Rev. 6.2 (03/11/02) corrects an earlier issue with RSAC-6, compiled with F77L-EM/32 Fortran 77 Version 5.10, which would not allow the executable to run with XP or VISTA Windows operating systems. Because this version is still in use at some facilities, it is being released through RSICC in addition to the new RSAC 7 (CCC-761).« less

  5. Confirmatory Survey Report for the Quehanna Decommissioning Project, Karthaus, PA

    SciTech Connect (OSTI)

    W. C. Adams

    2007-10-30

    The survey activities consisted of visual inspections and radiological surveys including beta and gamma surface scans and surface beta activity measurements.

  6. Formerly utilized MED/AEC sites remedial action program. Radiological survey of the National Guard Armory at Washington Park, 52nd Street and Cottage Grove Avenue, Chicago, Illinois, September 19, 1977-October 11, 1978

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Mayes, C.B.; Justus, A.L.

    1983-01-01

    A comprehensive radiological survey was conducted at the Illinois National Guard Armory at Washington Park in Chicago. This facility, used for uranium processing during the MED/AEC era, is now used as offices, classrooms, and storage and garage areas. Forty-two spots of contaminaton in nine rooms or areas exceeded the allowable limits for uranium as given in the ANSI Standard N13.12. In most instances, the contamination was found to be removable and available for transfer to other locations. However, under current use conditions, the potential for radiation exposure to occupants of this building from these sources of contamination is small. Concentrations of radon daughters in the air in the building, as measured by grab-sampling techniques, were less than the limit of 0.01 WL above background as given in the Surgeon General's Guidelines in 10 CFR 712. No long-lived radionuclides were detected in any air sample. Concentrations of radionuclides in soil samples collected around the facility indicated essentially background levels. The presumed maximum 50-year dose commitments from potential inhalation/ingestion of residual contamination were calculated to be 2.5 mrem to the lung, 0.51 mrem to the bone, 0.12 mrem to the kidney, and 0.031 mrem wholebody; each of these is less than 0.5% of the appropriate standards for an individual in an uncontrolled area. In order to rduce the potential for radiation exposure, remedial measures such as stabilization of the contamination in place would be applicable as a short-term measure. In order to reduce the risk in the event that building modifications take place in the future, health physics procedures and coverage are recommended. The long-term solution would involve dcontamination by removal of the radioactive residues from the 11 rooms or areas in the facility.

  7. Formerly utilized MED/AEC sites remedial action progam. Radiological survey of the Albany Metallurgical Research Center, United States Bureau of Mines, Biomass Facility and the Back Forty Area, Albany, Oregon

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.

    1983-06-01

    This report contains survey results identifying the current radiological condition of two areas located at the site of the United States Bureau of Mines' Albany Metallurgical Research Center in Albany, Oregon. These areas are designed as the BioMass Facility and the Back Forty. The BioMass Facility was a pilot plant for the production of oil from wood waste; it consists of five structures on a two-acre site. The Back Forty is a vacant area of about 14 acres south of the BioMass Facility. Both areas were reportedly used as dump sites for the Bureau of Mines operations. No contamination was found to be associated with the structures, equipment, or material in the BioMass Facility; however, four relatively small areas of contamination were found in the exterior grounds. The maximum radiation level measured was 0.7 mR/h at 1 cm. A relatively large area (approx. 0.8 acre) in the Back Forty area exhibited anomalous radiation levels. Radiation levels as high as 100 ..mu..R/h were measured at 3 ft above ground. This area was reportedly used as a dump site for Bureau of Mines activities. The structures, equipment, and material associated with the BioMass Facility can be released for unrestricted use. However, because of the subsurface contamination found in both the BioMass and the Back Forty areas, some restrictions should be incorporated into any planned useage for this site. Some discussion regarding these hazards are included in the text of this report.

  8. Measurement & Verification with Green Button Data | Department...

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Measurement & Verification with Green Button Data Measurement & Verification with Green ... Measurement and verification (M&V) focuses on ensuring that the savings from energy ...

  9. Automatic Estimation of the Radiological Inventory for the Dismantling of Nuclear Facilities

    SciTech Connect (OSTI)

    Garcia-Bermejo, R.; Felipe, A.; Gutierrez, S.; Salas, E.; Martin, N.

    2008-01-15

    The estimation of the radiological inventory of Nuclear Facilities to be dismantled is a process that included information related with the physical inventory of all the plant and radiological survey. Estimation of the radiological inventory for all the components and civil structure of the plant could be obtained with mathematical models with statistical approach. A computer application has been developed in order to obtain the radiological inventory in an automatic way. Results: A computer application that is able to estimate the radiological inventory from the radiological measurements or the characterization program has been developed. In this computer applications has been included the statistical functions needed for the estimation of the central tendency and variability, e.g. mean, median, variance, confidence intervals, variance coefficients, etc. This computer application is a necessary tool in order to be able to estimate the radiological inventory of a nuclear facility and it is a powerful tool for decision taken in future sampling surveys.

  10. Verification and validation benchmarks.

    SciTech Connect (OSTI)

    Oberkampf, William Louis; Trucano, Timothy Guy

    2007-02-01

    Verification and validation (V&V) are the primary means to assess the accuracy and reliability of computational simulations. V&V methods and procedures have fundamentally improved the credibility of simulations in several high-consequence fields, such as nuclear reactor safety, underground nuclear waste storage, and nuclear weapon safety. Although the terminology is not uniform across engineering disciplines, code verification deals with assessing the reliability of the software coding, and solution verification deals with assessing the numerical accuracy of the solution to a computational model. Validation addresses the physics modeling accuracy of a computational simulation by comparing the computational results with experimental data. Code verification benchmarks and validation benchmarks have been constructed for a number of years in every field of computational simulation. However, no comprehensive guidelines have been proposed for the construction and use of V&V benchmarks. For example, the field of nuclear reactor safety has not focused on code verification benchmarks, but it has placed great emphasis on developing validation benchmarks. Many of these validation benchmarks are closely related to the operations of actual reactors at near-safety-critical conditions, as opposed to being more fundamental-physics benchmarks. This paper presents recommendations for the effective design and use of code verification benchmarks based on manufactured solutions, classical analytical solutions, and highly accurate numerical solutions. In addition, this paper presents recommendations for the design and use of validation benchmarks, highlighting the careful design of building-block experiments, the estimation of experimental measurement uncertainty for both inputs and outputs to the code, validation metrics, and the role of model calibration in validation. It is argued that the understanding of predictive capability of a computational model is built on the level of

  11. Environmental Technology Verification of Mobile Sources Control...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Environmental Technology Verification of Mobile Sources Control Technologies Environmental Technology Verification of Mobile Sources Control Technologies 2005 Diesel Engine...

  12. WIPP Radiological Release Report Phase 1

    Office of Environmental Management (EM)

    Phase 1 Radiological Release Event at the Waste Isolation Pilot Plant on February 14, 2014 April 2014 Radiological Release Event at the Waste Isolation Pilot Plant Radiological ...

  13. WIPP Radiological Relase Report Phase 2

    Office of Environmental Management (EM)

    Phase 2 Radiological Release Event at the Waste Isolation Pilot Plant, February 14, 2014 April 2015 Radiological Release Event at the Waste Isolation Pilot Plant Radiological Release ...

  14. Radiological worker training

    SciTech Connect (OSTI)

    1998-10-01

    This Handbook describes an implementation process for core training as recommended in Implementation Guide G441.12, Radiation Safety Training, and as outlined in the DOE Radiological Control Standard (RCS). The Handbook is meant to assist those individuals within the Department of Energy, Managing and Operating contractors, and Managing and Integrating contractors identified as having responsibility for implementing core training recommended by the RCS. This training is intended for radiological workers to assist in meeting their job-specific training requirements of 10 CFR 835. While this Handbook addresses many requirements of 10 CFR 835 Subpart J, it must be supplemented with facility-specific information to achieve full compliance.

  15. 324 Building Baseline Radiological Characterization

    SciTech Connect (OSTI)

    R.J. Reeder, J.C. Cooper

    2010-06-24

    This report documents the analysis of radiological data collected as part of the characterization study performed in 1998. The study was performed to create a baseline of the radiological conditions in the 324 Building.

  16. Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    9 of 9 Radiological Control Technician Training Facility Practical Training Attachment Phase IV Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 This page intentionally left blank ii DOE-HDBK-1122-2009 Table of Contents Page Introduction................................................................................................................................1 Facility Job Performance Measures

  17. Radiological Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    DOE-HDBK-1122-2009 Part 2 of 9 Radiological Control Technician Training Technician Qualification Standard Coordinated and Conducted for the Office of Health, Safety and Security U.S. Department of Energy DOE-HDBK-1122-2009 This page intentionally left blank. ii DOE-HDBK-1122-2009 Table of Contents Page Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .1 Purpose of Qualification Standard . . . . . . . . . . . . . . . . .

  18. NNSA Conducts International Radiological Response Training in...

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    NNSA Conducts International Radiological Response Training in Vienna August 01, 2013 ... Radiological Assistance Program Training for Emergency Response Advanced ...

  19. TFE Verification Program

    SciTech Connect (OSTI)

    Not Available

    1990-03-01

    The objective of the semiannual progress report is to summarize the technical results obtained during the latest reporting period. The information presented herein will include evaluated test data, design evaluations, the results of analyses and the significance of results. The program objective is to demonstrate the technology readiness of a TFE suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW(e) range, and a full-power life of 7 years. The TF Verification Program builds directly on the technology and data base developed in the 1960s and 1970s in an AEC/NASA program, and in the SP-100 program conducted in 1983, 1984 and 1985. In the SP-100 program, the attractive but concern was expressed over the lack of fast reactor irradiation data. The TFE Verification Program addresses this concern. The general logic and strategy of the program to achieve its objectives is shown on Fig. 1-1. Five prior programs form the basis for the TFE Verification Program: (1) AEC/NASA program of the 1960s and early 1970; (2) SP-100 concept development program;(3) SP-100 thermionic technology program; (4) Thermionic irradiations program in TRIGA in FY-86; (5) and Thermionic Technology Program in 1986 and 1987. 18 refs., 64 figs., 43 tabs.

  20. General Employee Radiological Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    _______ Change Notice 1 June 2009 DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1131-2007 Original Change Part 2 page 5 The average annual radiation dose to a

  1. General Employee Radiological Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. Not Measurement Sensitive This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ DOE-HDBK-1131-2007 iii Foreword This Handbook describes an implementation process for core training as recommended in chapter 14,

  2. General Employee Radiological Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Not Measurement Sensitive DOE-HDBK-1131-2007 December 2007_______ Change Notice 1 Reaffirmed 2013 DOE HANDBOOK GENERAL EMPLOYEE RADIOLOGICAL TRAINING U.S. Department of Energy AREA TRNG Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. This document is available on the Department of Energy Technical Standards Program Web Site at http://www.hss.energy.gov/nuclearsafety/techstds/ Change 1 DOE-HDBK-1131-2007 Original Change Part 2 page 5 The

  3. Quantum money with classical verification

    SciTech Connect (OSTI)

    Gavinsky, Dmitry

    2014-12-04

    We propose and construct a quantum money scheme that allows verification through classical communication with a bank. This is the first demonstration that a secure quantum money scheme exists that does not require quantum communication for coin verification. Our scheme is secure against adaptive adversaries - this property is not directly related to the possibility of classical verification, nevertheless none of the earlier quantum money constructions is known to possess it.

  4. DOE Challenge Home Verification

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    DOE Challenge Home Verification Projected Rating: Based on Plans - Field Confirmation Required. Energy Performance House Ty pe DOE Challenge Home Builder Partner ID# Single-family det ac hed 12345 Y ear built Square footage of Conditioned Space including Basement 2013 3968.0 Numbe r of Bedrooms Square footage of Conditioned Space without Basement 4 2368.0 Site addre ss (if no t available , list the site Lo t #) Registered Builder 555 Main St r eet Cold City Certified Rater MN, 20853 HERS Index

  5. Methodology for Determining the Radiological Status of a Process: Application to Decommissioning of a Fuel Reprocessing Plant

    SciTech Connect (OSTI)

    Girones, Ph.; Ducros, C.; Legoaller, C.; Lamadie, F.; Fulconis, J.M.; Thiebaut, V.; Mahe, C.

    2006-07-01

    Decommissioning a nuclear facility is subject to various constraints including regulatory safety requirements, but also the obligation to limit the waste volume and toxicity. To meet these requirements the activity level in each component must be known at each stage of decommissioning, from the preliminary studies to the final release of the premises. This document describes a set of methods used to determine the radiological state of a spent fuel reprocessing plant. This approach begins with a bibliographical survey covering the nature of the chemical processes, the operational phases, and the radiological assessments during the plant operating period. In this phase it is also very important to analyze incidents and waste management practices. All available media should be examined, including photos and videos which can provide valuable data and must not be disregarded. At the end of this phase, any items requiring verification or additional data are reviewed to define further investigations. Although it is not unusual at this point to carry out an additional bibliographical survey, the essential task is to carry out in situ measurements. The second phase thus consists in performing in situ measurement campaigns involving essentially components containing significant activity levels. The most routinely used methods combine the results of elementary measurements such as the dose rate or more sophisticated measurements such as gamma spectrometry using CdZnTe detectors and gamma imaging to estimate and localize the radioactivity. Each instrument provides part of the answer (location of a contamination hot spot, standard spectrum, activity). The results are combined and verified through the use of calculation codes: Mercure, Visiplan and Microshield. (authors)

  6. Accident Investigation Report- Radiological Release

    Office of Energy Efficiency and Renewable Energy (EERE)

    On February 14, 2014, an airborne radiological release occurred at the Department of Energy Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Because access to the underground was restricted following the event, the investigation was broken into two phases. The Phase 1 report focused on how the radiological material was released into the atmosphere and Phase 2, performed once limited access to the underground was re‐established, focused on the source of the released radiological material.

  7. Software Verification and Validation Procedure

    SciTech Connect (OSTI)

    Olund, Thomas S.

    2008-09-15

    This Software Verification and Validation procedure provides the action steps for the Tank Waste Information Network System (TWINS) testing process. The primary objective of the testing process is to provide assurance that the software functions as intended, and meets the requirements specified by the client. Verification and validation establish the primary basis for TWINS software product acceptance.

  8. Benefits of Evaluation, Measurement, and Verification | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Benefits of Evaluation, Measurement, and Verification Benefits of Evaluation, Measurement, and Verification This document provides information about the benefits of performing ...

  9. Smart Radiological Dosimeter

    DOE Patents [OSTI]

    Kosslow, William J.; Bandzuch, Gregory S.

    2004-07-20

    A radiation dosimeter providing an indication of the dose of radiation to which the radiation sensor has been exposed. The dosimeter contains features enabling the monitoring and evaluating of radiological risks so that a user can concentrate on the task at hand. The dosimeter provides an audible alarm indication that a predetermined time period has elapsed, an audible alarm indication reminding the user to check the dosimeter indication periodically, an audible alarm indicating that a predetermined accumulated dose has been prematurely reached, and an audible alarm indication prior or to reaching the 3/4 scale point.

  10. ORISE: Independent verification

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    cleanup at decontamination and decommissioning (D&D) projects across the United States. ... and validation of contractors' final status survey procedures increases the ...

  11. Radiological Security Partnership | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) Programs / Nonproliferation / Global Material Security / Radiological Security Radiological Security Partnership Radiological Security Partnership Secure Your Business, Your Community, and Your Country. Sign Up Today for Services Provided by the Radiological Security Partnership. RSP Logo Initiative of the Global Material Security Program Formerly the Global Threat Reduction Initiative RSP Registration RSP More Info Learn More Radiological Security Partnership

  12. HEALTH AND SAFETY RESEARCH DIVISION REPORT OF INCLUSION SURVEY...

    Office of Legacy Management (LM)

    An inclusion radiological survey of location CA00401 was conducted on Sep- tember 27, 1985 by Oak Ridge National Laboratory. This property, located at Mayer Street, is classified ...

  13. Radiological Worker Computer Based Training

    Energy Science and Technology Software Center (OSTI)

    2003-02-06

    Argonne National Laboratory has developed an interactive computer based training (CBT) version of the standardized DOE Radiological Worker training program. This CD-ROM based program utilizes graphics, animation, photographs, sound and video to train users in ten topical areas: radiological fundamentals, biological effects, dose limits, ALARA, personnel monitoring, controls and postings, emergency response, contamination controls, high radiation areas, and lessons learned.

  14. Recommendation 207: Automate the Stewardship Verification Process

    Energy.gov [DOE]

    ORSSAB recommends DOE automate the Stewardship Verification Process for the Remediation Effectiveness Report.

  15. ESPC ENABLE Measurement and Verification Plan Template

    Energy.gov [DOE]

    Document contains a comprehensive measurement and verification plan template for a proposed ESPC ENABLE project.

  16. Handling and Packaging a Potentially Radiologically Contaminated...

    Office of Environmental Management (EM)

    Handling and Packaging a Potentially Radiologically Contaminated Patient Handling and Packaging a Potentially Radiologically Contaminated Patient The purpose of this procedure is...

  17. Nuclear Radiological Threat Task Force Established | National...

    National Nuclear Security Administration (NNSA)

    Nuclear Radiological Threat Task Force Established Washington, DC NNSA's Administrator Linton Brooks announces the establishment of the Nuclear Radiological Threat Reduction Task ...

  18. ORISE Resources: Radiological and Nuclear Terrorism: Medical...

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    to mass casualties that may involve radiological injuries. The interactive, two-hour training, titled Radiological and Nuclear Terrorism: Medical Response to Mass Casualties...

  19. PIA - Radiological Work Permit | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    PIA - Radiological Work Permit PDF icon PIA - Radiological Work Permit More Documents & Publications PIA - Bonneville Power Adminstration Ethics Helpline Occupational Medical ...

  20. radiological consquence management | National Nuclear Security...

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Apply for Our Jobs Our Jobs Working at NNSA Blog Home radiological consquence management radiological consquence management Fukushima: Five Years Later After the March 11, 2011, ...

  1. radiological response | National Nuclear Security Administration

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Apply for Our Jobs Our Jobs Working at NNSA Blog Home radiological response radiological response Fukushima: Five Years Later After the March 11, 2011, Japan earthquake, tsunami, ...

  2. Radionuclide Inventory Distribution Project Data Evaluation and Verification White Paper

    SciTech Connect (OSTI)

    NSTec Environmental Restoration

    2010-05-17

    Testing of nuclear explosives caused widespread contamination of surface soils on the Nevada Test Site (NTS). Atmospheric tests produced the majority of this contamination. The Radionuclide Inventory and Distribution Program (RIDP) was developed to determine distribution and total inventory of radionuclides in surface soils at the NTS to evaluate areas that may present long-term health hazards. The RIDP achieved this objective with aerial radiological surveys, soil sample results, and in situ gamma spectroscopy. This white paper presents the justification to support the use of RIDP data as a guide for future evaluation and to support closure of Soils Sub-Project sites under the purview of the Federal Facility Agreement and Consent Order. Use of the RIDP data as part of the Data Quality Objective process is expected to provide considerable cost savings and accelerate site closures. The following steps were completed: - Summarize the RIDP data set and evaluate the quality of the data. - Determine the current uses of the RIDP data and cautions associated with its use. - Provide recommendations for enhancing data use through field verification or other methods. The data quality is sufficient to utilize RIDP data during the planning process for site investigation and closure. Project planning activities may include estimating 25-millirem per industrial access year dose rate boundaries, optimizing characterization efforts, projecting final end states, and planning remedial actions. In addition, RIDP data may be used to identify specific radionuclide distributions, and augment other non-radionuclide dose rate data. Finally, the RIDP data can be used to estimate internal and external dose rates. The data quality is sufficient to utilize RIDP data during the planning process for site investigation and closure. Project planning activities may include estimating 25-millirem per industrial access year dose rate boundaries, optimizing characterization efforts, projecting final

  3. Standardized radiological dose evaluations

    SciTech Connect (OSTI)

    Peterson, V.L.; Stahlnecker, E.

    1996-05-01

    Following the end of the Cold War, the mission of Rocky Flats Environmental Technology Site changed from production of nuclear weapons to cleanup. Authorization baseis documents for the facilities, primarily the Final Safety Analysis Reports, are being replaced with new ones in which accident scenarios are sorted into coarse bins of consequence and frequency, similar to the approach of DOE-STD-3011-94. Because this binning does not require high precision, a standardized approach for radiological dose evaluations is taken for all the facilities at the site. This is done through a standard calculation ``template`` for use by all safety analysts preparing the new documents. This report describes this template and its use.

  4. RADRELAY RADIOLOGICAL DATA LINK DEVICE

    SciTech Connect (OSTI)

    Harpring, L; Frank Heckendorn, F

    2007-11-06

    The RadRelay effort developed small, field appropriate, portable prototype devices that allow radiological spectra to be downloaded from field radiological detectors, like the identiFINDER-U, and transmitted to land based experts. This communications capability was designed for the U. S. Coast Guard (USCG) but is also applicable to the Customs and Border Protection (CBP) personnel working in remote locations. USCG Level II personnel currently use the identiFINDER-U Hand-Held Radioisotope ID Devices (HHRIID) to detect radiological materials during specific boarding operations. These devices will detect not only radiological emissions but will also evaluate those emissions against a table of known radiological spectra. The RadRelay has been developed to significantly improve the functionality of HHRIID, by providing the capability to download radiological spectra and then transmit them using satellite or cell phone technology. This remote wireless data transfer reduces the current lengthy delay often encountered between the shipboard detection of unknown radiological material and the evaluation of that data by technical and command personnel. That delay is reduced from hours to minutes and allows the field located personnel to remain on station during the inspection and evaluation process.

  5. Final report: survey and removal of radioactive surface contamination at environmental restoration sites, Sandia National Laboratories/New Mexico. Volume 1

    SciTech Connect (OSTI)

    Lambert, K.A.; Mitchell, M.M.; Jean, D.; Byrd, C.S.

    1997-09-01

    This report describes the survey and removal of radioactive surface contamination at Sandia`s Environmental Restoration (ER) sites. Radiological characterization was performed as a prerequisite to beginning the Resource Conservation and Recovery Act (RCRA) corrective action process. The removal of radioactive surface contamination was performed in order to reduce potential impacts to human health and the environment. The predominant radiological contaminant of concern was depleted uranium (DU). Between October 1993 and November 1996 scanning surface radiation surveys, using gamma scintillometers, were conducted at 65 sites covering approximately 908 acres. A total of 9,518 radiation anomalies were detected at 38 sites. Cleanup activities were conducted between October 1994 and November 1996. A total of 9,122 anomalies were removed and 2,072 waste drums were generated. The majority of anomalies not removed were associated with a site that has subsurface contamination beyond the scope of this project. Verification soil samples (1,008 total samples) were collected from anomalies during cleanup activities and confirm that the soil concentration achieved in the field were far below the target cleanup level of 230 pCi/g of U-238 (the primary constituent of DU) in the soil. Cleanup was completed at 21 sites and no further radiological action is required. Seventeen sites were not completed since cleanup activities wee precluded by ongoing site activity or were beyond the original project scope.

  6. Verification of RESRAD-build computer code, version 3.1.

    SciTech Connect (OSTI)

    2003-06-02

    RESRAD-BUILD is a computer model for analyzing the radiological doses resulting from the remediation and occupancy of buildings contaminated with radioactive material. It is part of a family of codes that includes RESRAD, RESRAD-CHEM, RESRAD-RECYCLE, RESRAD-BASELINE, and RESRAD-ECORISK. The RESRAD-BUILD models were developed and codified by Argonne National Laboratory (ANL); version 1.5 of the code and the user's manual were publicly released in 1994. The original version of the code was written for the Microsoft DOS operating system. However, subsequent versions of the code were written for the Microsoft Windows operating system. The purpose of the present verification task (which includes validation as defined in the standard) is to provide an independent review of the latest version of RESRAD-BUILD under the guidance provided by ANSI/ANS-10.4 for verification and validation of existing computer programs. This approach consists of a posteriori V&V review which takes advantage of available program development products as well as user experience. The purpose, as specified in ANSI/ANS-10.4, is to determine whether the program produces valid responses when used to analyze problems within a specific domain of applications, and to document the level of verification. The culmination of these efforts is the production of this formal Verification Report. The first step in performing the verification of an existing program was the preparation of a Verification Review Plan. The review plan consisted of identifying: Reason(s) why a posteriori verification is to be performed; Scope and objectives for the level of verification selected; Development products to be used for the review; Availability and use of user experience; and Actions to be taken to supplement missing or unavailable development products. The purpose, scope and objectives for the level of verification selected are described in this section of the Verification Report. The development products that were used for

  7. Estimate Radiological Dose for Animals

    Energy Science and Technology Software Center (OSTI)

    1997-12-18

    Estimate Radiological dose for animals in ecological environment using open literature values for parameters such as body weight, plant and soil ingestion rate, rad. halflife, absorbed energy, biological halflife, gamma energy per decay, soil-to-plant transfer factor, ...etc

  8. Radiological Training for Tritium Facilities

    Energy Savers

    ... by Title 10 Code of Federal Regulations Occupational Radiation Protection, (10 CFR 835) Subpart J and as outlined in the DOE standard DOE-STD-1098-99, Radiological Control (RCS). ...

  9. Radiological cleanup of Enewetak Atoll

    SciTech Connect (OSTI)

    Not Available

    1981-01-01

    For 8 years, from 1972 until 1980, the United States planned and carried out the radiological cleanup, rehabilitation, and resettlement of Enewetak Atoll in the Marshall Islands. This documentary records, from the perspective of DOD, the background, decisions, actions, and results of this major national and international effort. The documentary is designed: First, to provide a historical document which records with accuracy this major event in the history of Enewetak Atoll, the Marshall Islands, the Trust Territory of the Pacific Islands, Micronesia, the Pacific Basin, and the United States. Second, to provide a definitive record of the radiological contamination of the Atoll. Third, to provide a detailed record of the radiological exposure of the cleanup forces themselves. Fourth, to provide a useful guide for subsequent radiological cleanup efforts elsewhere.

  10. Radiological Control Manual. Revision 0, January 1993

    SciTech Connect (OSTI)

    Not Available

    1993-04-01

    This manual has been prepared by Lawrence Berkeley Laboratory to provide guidance for site-specific additions, supplements, and clarifications to the DOE Radiological Control Manual. The guidance provided in this manual is based on the requirements given in Title 10 Code of Federal Regulations Part 835, Radiation Protection for Occupational Workers, DOE Order 5480.11, Radiation Protection for Occupational Workers, and the DOE Radiological Control Manual. The topics covered are (1) excellence in radiological control, (2) radiological standards, (3) conduct of radiological work, (4) radioactive materials, (5) radiological health support operations, (6) training and qualification, and (7) radiological records.

  11. Radiological Monitoring Continues at WIPP

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Radiological Monitoring Continues at WIPP CARLSBAD, N.M., February 19, 2014 - Radiological control personnel continue to collect surface and underground monitoring samples at the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) after an underground air monitor detected airborne radiation around 11:30 p.m. (MT) on February 14. Recent laboratory analyses by Carlsbad Environmental Monitoring and Research Center (CEMRC) found some trace amounts of americium and plutonium from a

  12. Radiological training for tritium facilities

    SciTech Connect (OSTI)

    1996-12-01

    This program management guide describes a recommended implementation standard for core training as outlined in the DOE Radiological Control Manual (RCM). The standard is to assist those individuals, both within DOE and Managing and Operating contractors, identified as having responsibility for implementing the core training recommended by the RCM. This training may also be given to radiological workers using tritium to assist in meeting their job specific training requirements of 10 CFR 835.

  13. ORISE: Radiological program assessment services

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Radiological program assessment services Minimizing the risk of human exposure to hazardous levels of radioactive materials requires designing a comprehensive safety program that ensures appropriate measures are taken to protect workers and the public. As a U.S. Department of Energy (DOE) institute, the Oak Ridge Institute for Science and Education (ORISE) understands the importance of having an effective safety program in place to assure stakeholders and regulators that your radiological

  14. Radiological Protection for DOE Activities

    Directives, Delegations, and Requirements [Office of Management (MA)]

    1995-09-29

    Establishes radiological protection program requirements that, combined with 10 CFR 835 and its associated implementation guidance, form the basis for a comprehensive program for protection of individuals from the hazards of ionizing radiation in controlled areas. Extended by DOE N 441.3. Cancels DOE 5480.11, DOE 5480.15, DOE N 5400.13, DOE N 5480.11; please note: the DOE radiological control manual (DOE/EH-0256T)

  15. Principles on Radiological Characterization of the Unit 1 at Ignalina NPP for Decommissioning Purposes

    SciTech Connect (OSTI)

    Poskas, P.; Zujus, R.; Drumstas, G.; Poskas, R.; Simonis, V.

    2008-07-01

    There is only one nuclear power plant in Lithuania - Ignalina NPP (INPP). The INPP operated two similar units with installed capacity of 1500 MW(each). They were commissioned in 12/1983 and 08/1987, and the original design lifetime was projected out to 2010 and 2015 respectively. But the first Unit of Ignalina NPP was shutdown December 31, 2004, and second Unit will be closed down before 2010 taking into consideration substantial long-term financial assistance from the EU, G7 and other states as well as international institutions. Implementation of dismantling activities requires detailed knowledge of the radiological situation at the Unit 1. General Programme of Radiological Survey for Ignalina NPP Unit 1 based on NUREG-1575 was prepared in 2005- 2006 by Consortium led by Lithuanian Energy Institute and approved by Regulatory Bodies. It includes such main steps as historical site assessment, scoping, characterization, remedial actions/decontamination support surveys and final status surveys. General Programme of Radiological Survey defines content and principles of the surveys, and preliminary survey considerations, including identification of the contaminants, establishment of the free release levels, principles on areas classification depending on contamination potential, identification of the final survey units, criteria for selection survey instrumentation, techniques and methods etc. So, in the paper information on these principles and the content of the different stages in General Programme of Radiological Survey is presented. (authors)

  16. Formerly utilized MED/AEC sites remedial action program. Geohydrological and radiological survey of the Albany Research Center, United States Bureau of Mines, Albany, Oregon, July 1983. Supplement 1

    SciTech Connect (OSTI)

    Wynveen, R.A.; Smith, W.H.; Sholeen, C.M.; Justus, A.L.; Flynn, K.F.; Tsai, S.Y.

    1984-06-01

    The purpose of this report is to present details of follow-up investigations of certain conditions revealed by the results of the initial survey - specifically the potential for contamination of groundwater and for lateral subsurface migration of radioactive waste from contaminated areas on the Albany Research Center site. 9 references, 12 figures, 7 tables.

  17. DOE standard: Radiological control

    SciTech Connect (OSTI)

    Not Available

    1999-07-01

    The Department of Energy (DOE) has developed this Standard to assist line managers in meeting their responsibilities for implementing occupational radiological control programs. DOE has established regulatory requirements for occupational radiation protection in Title 10 of the Code of Federal Regulations, Part 835 (10 CFR 835), ``Occupational Radiation Protection``. Failure to comply with these requirements may lead to appropriate enforcement actions as authorized under the Price Anderson Act Amendments (PAAA). While this Standard does not establish requirements, it does restate, paraphrase, or cite many (but not all) of the requirements of 10 CFR 835 and related documents (e.g., occupational safety and health, hazardous materials transportation, and environmental protection standards). Because of the wide range of activities undertaken by DOE and the varying requirements affecting these activities, DOE does not believe that it would be practical or useful to identify and reproduce the entire range of health and safety requirements in this Standard and therefore has not done so. In all cases, DOE cautions the user to review any underlying regulatory and contractual requirements and the primary guidance documents in their original context to ensure that the site program is adequate to ensure continuing compliance with the applicable requirements. To assist its operating entities in achieving and maintaining compliance with the requirements of 10 CFR 835, DOE has established its primary regulatory guidance in the DOE G 441.1 series of Guides. This Standard supplements the DOE G 441.1 series of Guides and serves as a secondary source of guidance for achieving compliance with 10 CFR 835.

  18. K Basins Field Verification Program

    SciTech Connect (OSTI)

    Booth, H.W.

    1994-12-02

    The Field Verification Program establishes a uniform and systematic process to ensure that technical information depicted on selected engineering drawings accurately reflects the actual existing physical configuration. This document defines the Field Verification Program necessary to perform the field walkdown and inspection process that identifies the physical configuration of the systems required to support the mission objectives of K Basins. This program is intended to provide an accurate accounting of the actual field configuration by documenting the as-found information on a controlled drawing.

  19. MONTHLY RADIATION SURVEY TECHNICAL BASIS

    SciTech Connect (OSTI)

    BROWN, R.L.

    2003-06-13

    This document details the technical basis, analysis, and justification for rescheduling radiation surveys in occupied radiation areas within Tank Farm Facilities from a weekly to a monthly frequency. The purpose of this document is to provide the technical basis, analysis, and justification for seeking a technical equivalency determination (TED) to TFRCM Article 552.1.b. The scope of this document limited to radiation surveys in occupied areas, no equivalency is being sought for high radiation area boundary surveys, radiological buffer area surveys, active ventilations surveys, or work coverage surveys.

  20. Carbon Storage Monitoring, Verification and Accounting Research |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Monitoring, Verification and Accounting Research Carbon Storage Monitoring, Verification and Accounting Research Reliable and cost-effective monitoring, verification and accounting (MVA) techniques are an important part of making geologic sequestration a safe, effective, and acceptable method for greenhouse gas control. MVA of geologic storage sites is expected to serve several purposes, including addressing safety and environmental concerns; inventory verification;

  1. ETA-AC06 - Vehicle Verification

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    6 Revision 0 Effective: March 23, 2001 Vehicle Verification Prepared by Electric Transportation Applications Prepared by: ... Date:... Jude M. ...

  2. Uncertainty in verification and validation: recent perspective...

    Office of Scientific and Technical Information (OSTI)

    Country of Publication: United States Language: English Subject: 99 GENERAL AND MISCELLANEOUSMATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; VALIDATION; VERIFICATION; COMPUTER ...

  3. Radiological control manual. Revision 1

    SciTech Connect (OSTI)

    Kloepping, R.

    1996-05-01

    This Lawrence Berkeley National Laboratory Radiological Control Manual (LBNL RCM) has been prepared to provide guidance for site-specific additions, supplements and interpretation of the DOE Radiological Control Manual. The guidance provided in this manual is one methodology to implement the requirements given in Title 10 Code of Federal Regulations Part 835 (10 CFR 835) and the DOE Radiological Control Manual. Information given in this manual is also intended to provide demonstration of compliance to specific requirements in 10 CFR 835. The LBNL RCM (Publication 3113) and LBNL Health and Safety Manual Publication-3000 form the technical basis for the LBNL RPP and will be revised as necessary to ensure that current requirements from Rules and Orders are represented. The LBNL RCM will form the standard for excellence in the implementation of the LBNL RPP.

  4. Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites | Department of Energy Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites Pre-MARSSIM Surveys in a MARSSIM World: Demonstrating How Pre-MARSSIM Radiological Data Demonstrate Protectiveness at Formerly Utilized Sites Remedial Action Program Sites Pre-MARSSIM Surveys in a

  5. WIPP Radiological Relase Report Phase 2

    Office of Environmental Management (EM)

    Department of Energy Office of Environmental Management Accident Investigation Report Phase 2 Radiological Release Event at the Waste Isolation Pilot Plant, February 14, 2014 April 2015 Radiological Release Event at the Waste Isolation Pilot Plant Radiological Release Event at the Waste Isolation Pilot Plant Disclaimer On February 14, 2014, an airborne radiological release occurred at the Department of Energy Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. On March 4, 2014, an

  6. Operational Guidelines/Radiological Emergency Response

    Energy.gov [DOE]

    Operational Guidelines/Radiological Emergency Response. Provides information and resources concerning the development of Operational Guidelines as part of planning guidance for protection and recovery following Radiological Dispersal Device (RDD) and/or Improvised Nuclear Device (IND) incidents. Operational Guidelines Technical (OGT) Manual, 2009 RESRAD-RDD Complementing Software to OGT Manual EPA Protective Action Guidelines (2013), Interim Final Federal Radiological Monitoring and Assessment Center (FRMAC) Federal Radiological Preparedness Coordinating Committee (FRPCC)

  7. Radiological Assistance Program | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    | (NNSA) Radiological Assistance Program RAP Logo NNSA's Radiological Assistance Program (RAP) is the nation's premier first-response resource in assessing an emergency situation and advising decision-makers on further steps to take to evaluate and minimize the hazards of a radiological incident. RAP provides resources (trained personnel and equipment) to evaluate, assess, advise, isotopically identify, search for, and assist in the mitigation of actual or perceived nuclear or radiological

  8. Nuclear & Radiological Material Removal | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    & Radiological Material Removal | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing Proliferation...

  9. International Data on Radiological Sources

    SciTech Connect (OSTI)

    Martha Finck; Margaret Goldberg

    2010-07-01

    ABSTRACT The mission of radiological dispersal device (RDD) nuclear forensics is to identify the provenance of nuclear and radiological materials used in RDDs and to aid law enforcement in tracking nuclear materials and routes. The application of databases to radiological forensics is to match RDD source material to a source model in the database, provide guidance regarding a possible second device, and aid the FBI by providing a short list of manufacturers and distributors, and ultimately to the last legal owner of the source. The Argonne/Idaho National Laboratory RDD attribution database is a powerful technical tool in radiological forensics. The database (1267 unique vendors) includes all sealed sources and a device registered in the U.S., is complemented by data from the IAEA Catalogue, and is supported by rigorous in-lab characterization of selected sealed sources regarding physical form, radiochemical composition, and age-dating profiles. Close working relationships with global partners in the commercial sealed sources industry provide invaluable technical information and expertise in the development of signature profiles. These profiles are critical to the down-selection of potential candidates in either pre- or post- event RDD attribution. The down-selection process includes a match between an interdicted (or detonated) source and a model in the database linked to one or more manufacturers and distributors.

  10. Departmental Radiological Emergency Response Assets

    Directives, Delegations, and Requirements [Office of Management (MA)]

    2007-06-27

    The order establishes requirements and responsibilities for the DOE/NNSA national radiological emergency response assets and capabilities and Nuclear Emergency Support Team assets. Supersedes DOE O 5530.1A, DOE O 5530.2, DOE O 5530.3, DOE O 5530.4, and DOE O 5530.5.

  11. radiological | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    radiological NNSA program strengthens national security from afar The Nuclear Smuggling Detection and Deterrence (NSDD) program is a key component of NNSA's core mission to reduce nuclear threats. The program, part of NNSA's Office of Defense Nuclear Nonproliferation, provides partners tools and training to deter, detect, and investigate smuggling of

  12. Radiological Security Partnership Information | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) About / Our Programs / Nonproliferation / Global Material Security / Radiological Security / Radiological Security Partnership Radiological Security Partnership Information Radioactive sources play an important role in a number of commercial, medical, and research facilities. The benefits of these sources must be balanced with proper security. The Department of Energy's (DOE) National Nuclear Security Administration (NNSA) is working with the Nuclear Regulatory

  13. TEPP Training - Modular Emergency Response Radiological Transportation

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Training (MERRTT) | Department of Energy Training - Modular Emergency Response Radiological Transportation Training (MERRTT) TEPP Training - Modular Emergency Response Radiological Transportation Training (MERRTT) Once the jurisdiction has completed an evaluation of their plans and procedures, they will need to address any gaps in training. To assist, TEPP has developed the Modular Emergency Response Radiological Transportation Training (MERRTT) program. MERRTT provides fundamental knowledge

  14. Model Recovery Procedure for Response to a Radiological Transportation...

    Office of Environmental Management (EM)

    for Response to a Radiological Transportation Incident Model Recovery Procedure for Response to a Radiological Transportation Incident This Transportation Emergency...

  15. Mobile autonomous robotic apparatus for radiologic characterization

    DOE Patents [OSTI]

    Dudar, Aed M.; Ward, Clyde R.; Jones, Joel D.; Mallet, William R.; Harpring, Larry J.; Collins, Montenius X.; Anderson, Erin K.

    1999-01-01

    A mobile robotic system that conducts radiological surveys to map alpha, beta, and gamma radiation on surfaces in relatively level open areas or areas containing obstacles such as stored containers or hallways, equipment, walls and support columns. The invention incorporates improved radiation monitoring methods using multiple scintillation detectors, the use of laser scanners for maneuvering in open areas, ultrasound pulse generators and receptors for collision avoidance in limited space areas or hallways, methods to trigger visible alarms when radiation is detected, and methods to transmit location data for real-time reporting and mapping of radiation locations on computer monitors at a host station. A multitude of high performance scintillation detectors detect radiation while the on-board system controls the direction and speed of the robot due to pre-programmed paths. The operators may revise the preselected movements of the robotic system by ethernet communications to remonitor areas of radiation or to avoid walls, columns, equipment, or containers. The robotic system is capable of floor survey speeds of from 1/2-inch per second up to about 30 inches per second, while the on-board processor collects, stores, and transmits information for real-time mapping of radiation intensity and the locations of the radiation for real-time display on computer monitors at a central command console.

  16. Mobile autonomous robotic apparatus for radiologic characterization

    DOE Patents [OSTI]

    Dudar, A.M.; Ward, C.R.; Jones, J.D.; Mallet, W.R.; Harpring, L.J.; Collins, M.X.; Anderson, E.K.

    1999-08-10

    A mobile robotic system is described that conducts radiological surveys to map alpha, beta, and gamma radiation on surfaces in relatively level open areas or areas containing obstacles such as stored containers or hallways, equipment, walls and support columns. The invention incorporates improved radiation monitoring methods using multiple scintillation detectors, the use of laser scanners for maneuvering in open areas, ultrasound pulse generators and receptors for collision avoidance in limited space areas or hallways, methods to trigger visible alarms when radiation is detected, and methods to transmit location data for real-time reporting and mapping of radiation locations on computer monitors at a host station. A multitude of high performance scintillation detectors detect radiation while the on-board system controls the direction and speed of the robot due to pre-programmed paths. The operators may revise the preselected movements of the robotic system by ethernet communications to remonitor areas of radiation or to avoid walls, columns, equipment, or containers. The robotic system is capable of floor survey speeds of from 1/2-inch per second up to about 30 inches per second, while the on-board processor collects, stores, and transmits information for real-time mapping of radiation intensity and the locations of the radiation for real-time display on computer monitors at a central command console. 4 figs.

  17. Nuclear Data Verification and Standardization

    SciTech Connect (OSTI)

    Karam, Lisa R.; Arif, Muhammad; Thompson, Alan K.

    2011-10-01

    The objective of this interagency program is to provide accurate neutron interaction verification and standardization data for the U.S. Department of Energy Division of Nuclear Physics programs which include astrophysics, radioactive beam studies, and heavy-ion reactions. The measurements made in this program are also useful to other programs that indirectly use the unique properties of the neutron for diagnostic and analytical purposes. These include homeland security, personnel health and safety, nuclear waste disposal, treaty verification, national defense, and nuclear based energy production. The work includes the verification of reference standard cross sections and related neutron data employing the unique facilities and capabilities at NIST and other laboratories as required; leadership and participation in international intercomparisons and collaborations; and the preservation of standard reference deposits. An essential element of the program is critical evaluation of neutron interaction data standards including international coordinations. Data testing of critical data for important applications is included. The program is jointly supported by the Department of Energy and the National Institute of Standards and Technology.

  18. Radiological characterization of a vitrification facility for decommissioning

    SciTech Connect (OSTI)

    Asou, M. [CEA/DEN/VALRHO/UMODD, 30207 Bagnols-sur-Ceze Cedex (France); Le Goaller, C. [CEA/DEN/VALRHO/DDCO, 30207 Bagnols-sur-Ceze Cedex (France); Martin, F. [AREVA NC DAP/MOP (France)

    2007-07-01

    Cleanup operations in the Marcoule Vitrification Facility (AVM) will start in 2007. This plant includes 20 highly irradiating storage tanks for high-level liquid waste before vitrification. The objective of the cleanup phase is to significantly decrease the amount of highly radioactive waste resulting from dismantling. A comprehensive radiological survey of the plant was initiated in 2000. Most of the tanks were characterized using advanced technologies: gamma imaging, CdZnTe gamma spectroscopy, dose rate measurements and 3D calculations codes. At the same time, inspections were conducted to develop 3D geometrical models of the tanks. The techniques used and the main results obtained are described as well as lessons learned from these operations. The rinsing program was defined in 2006. Decontamination operations are expected to begin in 2007, and radiological surveys will be followed up to monitor the efficiency of the decontamination process. Specific rinsing of all tanks and equipment will be carried out from 2007 to 2009. Concentrated liquid solutions will be vitrified between 2008 and 2010; the decommissioning of AVM will be delayed until the end of 2010. This strategy aims at producing less than 5% 'B' type (long-lived intermediate-level) waste from the decommissioning operations, as well as reducing the dose rate and risks by simplified remote dismantling. The paper reviews the main options selected for decontamination, as well as the radiological characterization strategy. Some cost-related aspects will also be analyzed. (authors)

  19. Understanding Mechanisms of Radiological Contamination

    SciTech Connect (OSTI)

    Rick Demmer; John Drake; Ryan James, PhD

    2014-03-01

    Over the last 50 years, the study of radiological contamination and decontamination has expanded significantly. This paper addresses the mechanisms of radiological contamination that have been reported and then discusses which methods have recently been used during performance testing of several different decontamination technologies. About twenty years ago the Idaho Nuclear Technology Engineering Center (INTEC) at the INL began a search for decontamination processes which could minimize secondary waste. In order to test the effectiveness of these decontamination technologies, a new simulated contamination, termed SIMCON, was developed. SIMCON was designed to replicate the types of contamination found on stainless steel, spent fuel processing equipment. Ten years later, the INL began research into methods for simulating urban contamination resulting from a radiological dispersal device (RDD). This work was sponsored by the Defense Advanced Research Projects Agency (DARPA) and included the initial development an aqueous application of contaminant to substrate. Since 2007, research sponsored by the US Environmental Protection Agency (EPA) has advanced that effort and led to the development of a contamination method that simulates particulate fallout from an Improvised Nuclear Device (IND). The IND method diverges from previous efforts to create tenacious contamination by simulating a reproducible “loose” contamination. Examining these different types of contamination (and subsequent decontamination processes), which have included several different radionuclides and substrates, sheds light on contamination processes that occur throughout the nuclear industry and in the urban environment.

  20. TYPE A VERIFICATION REPORT FOR THE HIGH FLUX BEAM REACTOR STACK AND GROUNDS, BROOKHAVEN NATIONAL LABORATORY, UPTON, NEW YORK DCN 5098-SR-08-0

    SciTech Connect (OSTI)

    Evan Harpenau

    2011-11-30

    The U.S. Department of Energy (DOE) Order 458.1 requires independent verification (IV) of DOE cleanup projects (DOE 2011). The Oak Ridge Institute for Science and Education (ORISE) has been designated as the responsible organization for IV of the High Flux Beam Reactor (HFBR) Stack and Grounds area at Brookhaven National Laboratory (BNL) in Upton, New York. The IV evaluation may consist of an in-process inspection with document and data reviews (Type A Verification) or a confirmatory survey of the site (Type B Verification). DOE and ORISE determined that a Type A verification of the documents and data for the HFBR Stack and Grounds: Survey Units (SU) 6, 7, and 8 was appropriate based on the initial survey unit classification, the walkover surveys, and the final analytical results provided by the Brookhaven Science Associates (BSA).

  1. DOE Zero Energy Ready Home Verification...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... Home Verification Summary DRAFT REMRate - Residential Energy Analysis and Rating Software ... Followed the DOE Zero Energy Ready Home Quality Management Guidelines X The buyer of this ...

  2. Headquarters Employment Verification | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Employment Verification Headquarters Employment Verification M&P Employees should contact Marilyn Samuels at 202-586-8571 for basic employment verification. S&E Employees should contact the Benefits Branch for basic employment verification. Requests should be faxed to 865-576-5050. If a fax is not available, please email requests to SESSCBenefits@hc.doe.gov This is for "is this person employed here?", or "how long has this person been employed?". There will be no

  3. Verification and validation benchmarks. (Technical Report) |...

    Office of Scientific and Technical Information (OSTI)

    high-consequence fields, such as nuclear reactor safety, underground nuclear waste ... For example, the field of nuclear reactor safety has not focused on code verification ...

  4. Verification and validation benchmarks. (Technical Report) |...

    Office of Scientific and Technical Information (OSTI)

    Validation addresses the physics modeling accuracy of a computational simulation by comparing the computational results with experimental data. Code verification benchmarks and ...

  5. ESPC ENABLE Measurement and Verification Protocol

    Energy.gov [DOE]

    Document provides an overview of the Measurement and Verification (M&V) Protocol utilized within ENABLE energy savings performance contract projects.

  6. Input apparatus for dynamic signature verification systems

    DOE Patents [OSTI]

    EerNisse, Errol P.; Land, Cecil E.; Snelling, Jay B.

    1978-01-01

    The disclosure relates to signature verification input apparatus comprising a writing instrument and platen containing piezoelectric transducers which generate signals in response to writing pressures.

  7. ETA-HAC06 - Vehicle Verification

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    This procedure identifies the verification parameters that shall be recorded prior to Performance Testing of any Electric Vehicle provided to Electric Transportation Applications. ...

  8. Lessons Learned from Independent Verification Activities

    Office of Environmental Management (EM)

    Demonstration Oak Ridge Institute for Science and Education - Independent Verification Lessons Learned IV - performed at nine DOE sites from 2004 to 2008 Page 1 of 2 Oak Ridge ...

  9. Superior Energy Performance Measurement and Verification Protocol...

    Energy.gov (indexed) [DOE]

    Superior Energy Performance Measurement and Verification Protocol for Industry November ... with the U.S. Department of Energy, for the management and operation of the ...

  10. Superior Energy Performance Measurement and Verification Protocol...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Superior Energy Performance logo This Measurement and Verification Protocol for Industry defines the procedures that will be used to confirm conformance with the energy performance ...

  11. Why do verification and validation?

    DOE PAGES-Beta [OSTI]

    Hu, Kenneth T.; Paez, Thomas L.

    2016-02-19

    In this discussion paper, we explore different ways to assess the value of verification and validation (V&V) of engineering models. We first present a literature review on the value of V&V and then use value chains and decision trees to show how value can be assessed from a decision maker's perspective. In this context, the value is what the decision maker is willing to pay for V&V analysis with the understanding that the V&V results are uncertain. As a result, the 2014 Sandia V&V Challenge Workshop is used to illustrate these ideas.

  12. AHAM DOE Verification Test Agreement | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    DOE Verification Test Agreement AHAM DOE Verification Test Agreement This letter is to inform AHAM that DOE is adopting a new policy regarding DOE ENERGY STAR verification testing of models that are part of the AHAM verification program for clothes washers; dishwashers; or residential refrigerators, refrigerator-freezers, and freezers. aham_verification_letter.pdf (3.6 MB) More Documents & Publications AHAM Letter Acknowledging DOE Letter on Verification Program This letter is to inform AHAM

  13. WIPP Radiological Release Report Phase 1

    Office of Environmental Management (EM)

    U.S. Department of Energy Office of Environmental Management Accident Investigation Report Phase 1 Radiological Release Event at the Waste Isolation Pilot Plant on February 14, 2014 April 2014 Radiological Release Event at the Waste Isolation Pilot Plant Radiological Release Event at the Waste Isolation Pilot Plant Disclaimer Phase 1 of this accident investigation report is an independent product of the Accident Investigation Board appointed by Matthew Moury, Deputy Assistant Secretary, Safety,

  14. Nuclear / Radiological Advisory Team | National Nuclear Security

    National Nuclear Security Administration (NNSA)

    Administration | (NNSA) / Radiological Advisory Team NRAT Logo NNSA's Nuclear / Radiological Advisory Team (NRAT) provides an emergency response capability for on-scene scientific and technical advice for both domestic and international nuclear or radiological incidents. It is led by a Senior Energy Official who runs the NNSA field operation and who coordinates NNSA follow-on assets as needed. The NRAT is composed of scientists and technicians who can provide advice or conduct limited

  15. Radiological Triage | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Radiological Triage Triage Logo NNSA's Triage is a non-deployable, secure, on-line capability that provides remote support to emergency responders in the event of a nuclear or radiological emergency. Triage has on-call scientists available 24 hours a day to analyze site-specific data and confirm radioisotope identification in the event of a radiological incident. The data is transmitted through the Triage website or provided over the telephone. Triage is an integrated system that is comprised of

  16. Radiological Security | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Global Material Security Radiological Security The program collaborates with domestic and international partners to address the threat of illicit use of high-priority radiological materials in the United States and abroad. The Radiological Security program accomplishes its mission by removing and disposing of excess or orphaned radioactive sources; promoting the replacement of radioactive sources with non-isotopic technologies, where feasible; and increasing security where high-priority

  17. Lessons Learned from Independent Verification Activities | Department...

    Office of Environmental Management (EM)

    The Department of Energy clears property from radiological control after the property has been demonstrated to meet the Department's stringent radiation protection requirements. ...

  18. verification

    National Nuclear Security Administration (NNSA)

    %2A en NGSI Safeguards by Design http:nnsa.energy.govaboutusourprogramsdnnnissafeguardssbd

  19. verification

    National Nuclear Security Administration (NNSA)

    information with the need to obtain enough data to inform the process.

    Michele Smith, Deputy Director for the Warhead Dismantlement Transparency Program within NNSA's...

  20. The monitoring and verification of nuclear weapons

    SciTech Connect (OSTI)

    Garwin, Richard L.

    2014-05-09

    This paper partially reviews and updates the potential for monitoring and verification of nuclear weapons, including verification of their destruction. Cooperative monitoring with templates of the gamma-ray spectrum are an important tool, dependent on the use of information barriers.

  1. Additional Verification Bodies Now Available for SEP

    Energy.gov [DOE]

    Superior Energy Performance (SEP) recognizes industrial facilities that demonstrate energy management excellence and sustained energy savings. Third-party verification using an ANSI-ANAB Accredited Verification Body offers robust, independent confirmation of a facility's conformance to ISO 50001 and improved energy performance—providing accurate energy numbers that energy managers can present with confidence to management and other stakeholders.

  2. DOE handbook: Integrated safety management systems (ISMS) verification team leader`s handbook

    SciTech Connect (OSTI)

    1999-06-01

    The primary purpose of this handbook is to provide guidance to the ISMS verification Team Leader and the verification team in conducting ISMS verifications. The handbook describes methods and approaches for the review of the ISMS documentation (Phase I) and ISMS implementation (Phase II) and provides information useful to the Team Leader in preparing the review plan, selecting and training the team, coordinating the conduct of the verification, and documenting the results. The process and techniques described are based on the results of several pilot ISMS verifications that have been conducted across the DOE complex. A secondary purpose of this handbook is to provide information useful in developing DOE personnel to conduct these reviews. Specifically, this handbook describes methods and approaches to: (1) Develop the scope of the Phase 1 and Phase 2 review processes to be consistent with the history, hazards, and complexity of the site, facility, or activity; (2) Develop procedures for the conduct of the Phase 1 review, validating that the ISMS documentation satisfies the DEAR clause as amplified in DOE Policies 450.4, 450.5, 450.6 and associated guidance and that DOE can effectively execute responsibilities as described in the Functions, Responsibilities, and Authorities Manual (FRAM); (3) Develop procedures for the conduct of the Phase 2 review, validating that the description approved by the Approval Authority, following or concurrent with the Phase 1 review, has been implemented; and (4) Describe a methodology by which the DOE ISMS verification teams will be advised, trained, and/or mentored to conduct subsequent ISMS verifications. The handbook provides proven methods and approaches for verifying that commitments related to the DEAR, the FRAM, and associated amplifying guidance are in place and implemented in nuclear and high risk facilities. This handbook also contains useful guidance to line managers when preparing for a review of ISMS for radiological

  3. Declaration of Construction Completion and Verification of Readiness...

    Energy Savers

    Declaration of Construction Completion and Verification of Readiness to Test Declaration of Construction Completion and Verification of Readiness to Test Salt Waste Processing ...

  4. Numerical Verification of Bounce Harmonic Resonances in Neoclassical

    Office of Scientific and Technical Information (OSTI)

    for Tokamaks Kimin Kim, Jong-Kyu Park and Allen H. Boozer 70 PLASMA PHYSICS AND FUSION TECHNOLOGY Tokamaks, Numerical Verification Tokamaks, Numerical Verification This...

  5. Verification of J-integral capability in Sierra Mechanics. (Technical...

    Office of Scientific and Technical Information (OSTI)

    Verification of J-integral capability in Sierra Mechanics. Citation Details In-Document Search Title: Verification of J-integral capability in Sierra Mechanics. You are...

  6. California ARB Verification Testing of the CBSTM Soot Filter...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    California ARB Verification Testing of the CBSTM Soot Filter for Stationary Diesel Applications California ARB Verification Testing of the CBSTM Soot Filter for Stationary Diesel ...

  7. ENERGY STAR Appliance Verification Testing - Pilot Program Summary...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ENERGY STAR Appliance Verification Testing - Pilot Program Summary Report dated February 3, 2012 ENERGY STAR Appliance Verification Testing - Pilot Program Summary Report dated ...

  8. FAQ's for: ENERGY STAR Verification Testing Pilot Program dated...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    FAQ's for: ENERGY STAR Verification Testing Pilot Program dated December 2010 FAQ's for: ENERGY STAR Verification Testing Pilot Program dated December 2010 This document is the ...

  9. Nation's Radiological Assistance Program teams practice emergency...

    National Nuclear Security Administration (NNSA)

    Home Blog Nation's Radiological Assistance Program teams practice emergency response ... of Department of Energy (DOE)National Nuclear Security Administration (NNSA) nuclear ...

  10. Cardiovascular and Interventional Radiological Society of Europe...

    Office of Scientific and Technical Information (OSTI)

    Cardiovascular and Interventional Radiological Society of Europe Guidelines on Endovascular Treatment in Aortoiliac Arterial Disease Citation Details In-Document Search Title: ...

  11. Radiological Control Programs for Special Tritium Compounds

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    APPROVAL OF CHANGE NOTICE 1 TO DEPARTMENT OF ENERGY (DOE) SUBJECT. HANDBOOK 1184-2004, RADIOLOGICAL CONTROL PROGRAMS FOR SPECIAL TRITIUM COMPOUNDS TO: Dennis Kubicki, EH-24 ...

  12. DOE Issues WIPP Radiological Release Investigation Report

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Management (EM) released the initial accident investigation report related to the ... After the entry teams determine the source of the radiological event, the accident ...

  13. Radiological Assistance Program Flight Planning Tool

    SciTech Connect (OSTI)

    2011-12-19

    The Radiological Assitance Program (RAP) is the National Nuclear Security Administration's (NNSA) first responder to radiological emergencies. RAP's mission is to identify and minimize radiological hazards, as well as provide radiological emergency response and technical advice to decision makers. One tool commonly used is aerial radiation detection equipment. During a response getting this equipment in the right place quickly is critical. The RAP Flight Planning Tool (a ArcGIS 10 Desktop addin) helps minimize this response time and provides specific customizable flight path information to the flight staff including maps, coordinates, and azimuths.

  14. Operating Experience Level 3: Radiologically Contaminated Respirators...

    Energy Savers

    Experience Level 3 provides information on a safety concern related to radiological contamination of launderedreconditioned respirators and parts that have been certified as...

  15. Radiological Contamination Control Training for Laboratory Research

    Energy Savers

    researchers. Course Description: This course illustrates and reinforces the skills and knowledge needed to assist personnel with radiological controls for laboratory research...

  16. Radiological Control - DOE Directives, Delegations, and Requirements

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    98-2008, Change Notice 1, Radiological Control by Diane Johnson The Department of Energy (DOE) has developed this Standard to assist line managers in meeting their responsibilities...

  17. Nuclear / Radiological Advisory Team | National Nuclear Security...

    National Nuclear Security Administration (NNSA)

    Nuclear Radiological Advisory Team (NRAT) provides an emergency response capability for on-scene scientific and technical advice for both domestic and international nuclear or ...

  18. Radiological Assistance Program Flight Planning Tool

    Energy Science and Technology Software Center (OSTI)

    2011-12-19

    The Radiological Assitance Program (RAP) is the National Nuclear Security Administration's (NNSA) first responder to radiological emergencies. RAP's mission is to identify and minimize radiological hazards, as well as provide radiological emergency response and technical advice to decision makers. One tool commonly used is aerial radiation detection equipment. During a response getting this equipment in the right place quickly is critical. The RAP Flight Planning Tool (a ArcGIS 10 Desktop addin) helps minimize this responsemore » time and provides specific customizable flight path information to the flight staff including maps, coordinates, and azimuths.« less

  19. Memorandum, Reporting of Radiological Sealed Sources Transactions...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    The requirements for reporting transactions involving radiological sealed sources are identified in Department of Energy (DOE) Notice (N) 234.1, Reporting of Radioactive Sealed ...

  20. Final Report - Independent Confirmatory Survey Summary and Results for the Hematite Decommissioning Project

    SciTech Connect (OSTI)

    E.N. Bailey

    2009-03-18

    The objectives of the confirmatory surveys were to provide independent contractor field data reviews and to generate independent radiological data for use by the NRC in evaluating the adequacy and accuracy of the licensee’s procedures and survey results.

  1. Survey of Existing Tools for Formal Verification. (Technical...

    Office of Scientific and Technical Information (OSTI)

    Content: Close Send 0 pages in this document matching the terms "" Search For Terms: Enter terms in the toolbar above to search the full text of this document for pages...

  2. Oak Ridge Associated VERIFICATION SURVEY Universities OF THE

    Office of Legacy Management (LM)

    ... for computing the dose to members of the general public. ... area of the adjacent Beaver Valley Nuclear Power Stations. ... accomplished by use of a gas proportional floor monitor, ...

  3. I RADIOLOGICAL SCOPING SURVEY OF FO,RMER MONSANTO' FACILITIES

    Office of Legacy Management (LM)

    responsibility for the production of polonium in support of the development of an ... and were lim ited to trace quantities of polonium fop the analysis of environmental m o n ...

  4. Radiological Survey Data for 38 Grove Avenue, Rochelle Park,...

    Office of Legacy Management (LM)

    E a s t m a n , 0 R A. llhltrnan, NE-24 Aeros pace ATG. SYMBOL NEzE4 . - . 4 . W . rNrfif,LcstG F.e.lg DATE RTG. SYMBOT tNtTTALSSlG, N E - 7 3 ( 4 ) N E - 2 4 R F DOE F ...

  5. RADIOLOGICAL SURVEY AT 5823/5849 NORTH RAVENSWOOD AVEXJE CHICAGO...

    Office of Legacy Management (LM)

    The subcontract number 7401-37-93, was to furnish the necessary personnel, facilities and equipment required to produce special tools, dies, fixtures, etc., from materials ...

  6. RADIOLOGICAL SURVEY OF THE GUN FORGING MACHINE BUILDING ITHACA...

    Office of Legacy Management (LM)

    ... these manuals were developed to meet the requirements of DOE Order I 5700.6C and ASMB NQA-1 for Quality Assurance and contain measures to assess processes during their performance. ...

  7. NNSA to Conduct Aerial Radiological Surveys Over Washington,...

    National Nuclear Security Administration (NNSA)

    Washington, D.C. and Baltimore, MD Areas | National Nuclear Security Administration Facebook Twitter Youtube Flickr RSS People Mission Managing the Stockpile Preventing...

  8. ENERGY MEASUREMENTS GROUP EG&G SURVEY REPORT

    Office of Legacy Management (LM)

    ENERGY MEASUREMENTS GROUP EG&G SURVEY REPORT NRC-81 13 , NOVEMBER 1981 llti * Knb THE REMOTE SENSING lA6ORAORV OF THE UNITED STATES DEPARTMENT OF ENERGY AN AERIAL RADIOLOGICAL ...

  9. Federal Radiological Monitoring and Assessment Center

    Directives, Delegations, and Requirements [Office of Management (MA)]

    1992-12-02

    To establish Department of Energy (DOE) policy, procedures, authorities, and requirements for the establishment of a Federal Radiological Monitoring and Assessment Center (FRMAC), as set forth in the Federal Radiological Emergency Response Plan (FRERP). This directive does not cancel another directive. Canceled by DOE O 153.1.

  10. Memorandum, Reporting of Radiological Sealed Sources Transactions

    Energy.gov [DOE]

    The requirements for reporting transactions involving radiological sealed sources are identified in Department of Energy (DOE) Notice (N) 234.1, Reporting of Radioactive Sealed Sources. The data reported in accordance with DOE N 234.1 are maintained in the DOE Radiological Source Registry and Tracking (RSRT) database by the Office of Information Management, within the Office of Environment, Health, Safety and Security.

  11. Radiological Triage | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Radiological Triage NNSA stays prepared with world-class response units September is National Preparedness Month, but for the Department of Energy (DOE) and NNSA, preparedness is a priority every month of the year. NNSA can respond to an emergency at any DOE facility, and it is also the nation's premier technical resource for response to nuclear or radiological

  12. INL@Work Radiological Search & Response Training

    SciTech Connect (OSTI)

    Turnage, Jennifer

    2010-01-01

    Dealing with radiological hazards is just part of the job for many INL scientists and engineers. Dodging bullets isn't. But some Department of Defense personnel may have to do both. INL employee Jennifer Turnage helps train soldiers in the art of detecting radiological and nuclear material. For more information about INL's research projects, visit http://www.facebook.com/idahonationallaboratory.

  13. INL@Work Radiological Search & Response Training

    ScienceCinema (OSTI)

    Turnage, Jennifer

    2016-07-12

    Dealing with radiological hazards is just part of the job for many INL scientists and engineers. Dodging bullets isn't. But some Department of Defense personnel may have to do both. INL employee Jennifer Turnage helps train soldiers in the art of detecting radiological and nuclear material. For more information about INL's research projects, visit http://www.facebook.com/idahonationallaboratory.

  14. Nevada Test Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers' Council - Nevada Test Site

    2009-10-01

    This document supersedes DOE/NV/11718--079, “NV/YMP Radiological Control Manual,” Revision 5 issued in November 2004. Brief Description of Revision: A complete revision to reflect the recent changes in compliance requirements with 10 CFR 835, and for use as a reference document for Tenant Organization Radiological Protection Programs.

  15. MODARIA: Modelling and Data for Radiological Impact Assessment...

    Office of Environmental Management (EM)

    MODARIA: Modelling and Data for Radiological Impact Assessment Context and Overview MODARIA: Modelling and Data for Radiological Impact Assessment Context and Overview Presentation...

  16. Model Annex for Preparedness and Response to Radiological Transportati...

    Office of Environmental Management (EM)

    Annex for Preparedness and Response to Radiological Transportation Incidents Model Annex for Preparedness and Response to Radiological Transportation Incidents This part should...

  17. Office of Radiological Security | Y-12 National Security Complex

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Office of Radiological ... Office of Radiological Security Read more about Y-12's contributions of the Global Threat Reduction Initiative to secure the world's most vulnerable...

  18. DOE - Office of Legacy Management -- U S Naval Radiological Defense...

    Office of Legacy Management (LM)

    Naval Radiological Defense Laboratory - CA 0-06 FUSRAP Considered Sites Site: U. S. NAVAL RADIOLOGICAL DEFENSE LABORATORY (CA.0-06) Eliminated from consideration under FUSRAP - ...

  19. Hawaii Department of Health Indoor and Radiological Health Branch...

    Open Energy Information (Open El) [EERE & EIA]

    Indoor and Radiological Health Branch Jump to: navigation, search Name: Hawaii Department of Health Indoor and Radiological Health Branch From Open Energy Information Address: 591...

  20. Nuclear and Radiological Field Training Center | Y-12 National...

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    ... Nuclear and Radiological Field Training Center A site used for nuclear research in Oak ... and Radiological Field Training Center - the only facility of its kind in the world. ...

  1. DOE-HDBK-1122-99; Radiological Technician Training

    Energy Savers

    ... Causes of radiological incidents and emergencies could be ... material, weather conditions, non-radiological ... area to characterize the extent of contamination. * ...

  2. Los Alamos National Security Corrective Action Plan - Radiological...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Partnership (NWP) Corrective Action Plan - Truck Fire and Radiological Release Phase I Carlsbad Field Office (CBFO) Corrective Action Plan - Truck Fire and Radiological Release

  3. DOE Zero Energy Ready Home Verification | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Verification DOE Zero Energy Ready Home Verification DOE Zero Energy Ready Homes Verification, a publication of the U.S. Department of Energy Zero Energy Ready Homes program. DOE Zero Energy Ready Home - Verification Report.pdf (47.44 KB) More Documents & Publications The Appraisal Process: Be Your Own Advocate Prescriptive Path compliance form ZERO ENERGY READY HOME UPDATE NEWSLETTER AUGUST 2014

  4. Robotic Surveying

    SciTech Connect (OSTI)

    Suzy Cantor-McKinney; Michael Kruzic

    2007-03-01

    ZAPATA ENGINEERING challenged our engineers and scientists, which included robotics expertise from Carnegie Mellon University, to design a solution to meet our client's requirements for rapid digital geophysical and radiological data collection of a munitions test range with no down-range personnel. A prime concern of the project was to minimize exposure of personnel to unexploded ordnance and radiation. The field season was limited by extreme heat, cold and snow. Geographical Information System (GIS) tools were used throughout this project to accurately define the limits of mapped areas, build a common mapping platform from various client products, track production progress, allocate resources and relate subsurface geophysical information to geographical features for use in rapidly reacquiring targets for investigation. We were hopeful that our platform could meet the proposed 35 acres per day, towing both a geophysical package and a radiological monitoring trailer. We held our breath and crossed our fingers as the autonomous Speedrower began to crawl across the playa lakebed. We met our proposed production rate, and we averaged just less than 50 acres per 12-hour day using the autonomous platform with a path tracking error of less than +/- 4 inches. Our project team mapped over 1,800 acres in an 8-week (4 days per week) timeframe. The expertise of our partner, Carnegie Mellon University, was recently demonstrated when their two autonomous vehicle entries finished second and third at the 2005 Defense Advanced Research Projects Agency (DARPA) Grand Challenge. 'The Grand Challenge program was established to help foster the development of autonomous vehicle technology that will some day help save the lives of Americans who are protecting our country on the battlefield', said DARPA Grand Challenge Program Manager, Ron Kurjanowicz. Our autonomous remote-controlled vehicle (ARCV) was a modified New Holland 2550 Speedrower retrofitted to allow the machine

  5. Evaluation, Measurement, and Verification Overview | Department...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    This document provides an overview and definition of EM&V. PDF icon What is EMV? More ... and Verification Plan for Your Energy Efficiency ProjectProgram Developing an ...

  6. Assessment of Advanced Measurement and Verification Methods ...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    (M&V 2.0) Assessment of Advanced Measurement and Verification Methods (M&V 2.0) Automated M&V from Noesis Automated M&V from Noesis Lead Performer: Lawrence Berkeley ...

  7. Example Measurement and Verification Plan for an ESPC Project | Department

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    of Energy Measurement and Verification Plan for an ESPC Project Example Measurement and Verification Plan for an ESPC Project Report features a comprehensive measurement and verification (M&V) plan for a fictitious energy savings performance contract (ESPC) project. Download the Example M&V Plan. (282.05 KB) More Documents & Publications M&V Guidelines: Measurement and Verification for Performance-Based Contracts (Version 4.0) Reviewing Measurement and Verification Plans for

  8. FAQ's for: ENERGY STAR Verification Testing Pilot Program dated December

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    2010 | Department of Energy FAQ's for: ENERGY STAR Verification Testing Pilot Program dated December 2010 FAQ's for: ENERGY STAR Verification Testing Pilot Program dated December 2010 This document is the FAQ's for the ENERGY STAR Verification Testing Pilot Program dated December 2010 faq_final_december-2010.pdf (307.2 KB) More Documents & Publications Comment submitted by the Alliance for Water Efficiency (AWE) regarding the Energy Star Verification Testing Program DOE Verification

  9. Verification & Validation | National Nuclear Security Administration |

    National Nuclear Security Administration (NNSA)

    (NNSA) Verification & Validation Verification and Validation (V&V) provides assurance that the models in the codes produce mathematically correct answers and that the answers reflect physical reality. The V&V subprogram funds the critical skills needed to apply systematic measurement, documentation, and demonstration of the ability of the models and codes to predict physical behavior. The V&V subprogram is developing and implementing Uncertainty Quantification (UQ)

  10. Verification and Validation Supporting VERA Neutronics Code

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Verification and Validation Supporting VERA Neutronics Code As CASL produces its VERA software each physics capability must be tested, verified, and validated (V&V). The overarching objective of code verification is to establish that a computation- al model implemented in a code accurately represents the de- veloper's conceptual representation of the physics, while vali- dation refers to the process of determining the degree to which a computational model provides an accurate representation

  11. AMS/NRCan Joint Survey Report: Aerial Campaign

    SciTech Connect (OSTI)

    Wasiolek, Piotr; Stampahar, Jez; Malchow, Rusty; Stampahar, Tom; Lukens, Mike; Seywerd, Henry; Fortin, Richard; Harvey, Brad; Sinclair, Laurel

    2014-12-31

    In January 2014 the U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA) Aerial Measuring System (AMS) and the Natural Resources Canada (NRCan) Nuclear Emergency Response project conducted a series of joint surveys at a number of locations in Nevada including the Nevada National Security Site (NNSS). The goal of this project was to compare the responses of the two agencies’ aerial radiation detection systems and data analysis techniques. This test included varied radioactive surface contamination levels and isotopic composition experienced at the NNSS and the differing data processing techniques utilized by the respective teams. Because both teams used the commercial aerial radiation detection systems from Radiation Solutions, Inc., the main focus of the campaign was to investigate the data acquisition techniques, data analysis, and ground-truth verification. The NRCan system consisted of four 4" × 4" × 16" NaI(Tl) scintillator crystals of which two were externally mounted in a modified commercial cargo basket certified for the Eurocopter AS350; the NNSA AMS system consisted of twelve 2" × 4" × 16" NaI(Tl) crystals in externally mounted dedicated pods. For NRCan, the joint survey provided an opportunity to characterize their system’s response to extended sources of various fission products at the NNSS. Since both systems play an important role in their respective countries’ national framework of radiological emergency response and are subject to multiple mutual cooperation agreements, it was important for each country to obtain more thorough knowledge of how they would employ these important assets and define the roles that they would each play in an actual response.

  12. Nuclear Radiological Threat Task Force Established | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Radiological Threat Task Force Established Nuclear Radiological Threat Task Force Established Washington, DC NNSA's Administrator Linton Brooks announces the establishment of the Nuclear Radiological Threat Reduction Task Force (NRTRTF) to combat the threats posed by radiological dispersion devices or "dirty bombs."

  13. Radiological characterization of the Kellex site. Publication No. 45020. [Metal fabrication; pilot plant to demonstrate units for gaseous diffusion

    SciTech Connect (OSTI)

    Hutchinson, S.W.

    1981-03-01

    A radiological characterization has been conducted at the former Kellex Corporation site in Jersey City, New Jersey. Although several prior surveys and a remedial action were conducted, there was still a need for more information about the radiological condition of the site. A grid was established on the site and the surface was surveyed by a mobile in situ detection system. Trenches were systematically dug in an attempt to find subsurface areas of contamination. Material from the trenches was surveyed by the in situ measurement system and trench sidewalls were soil sampled and surveyed using portable dose rate and count rate instrumentation. Results of the survey indicated that radioactivity levels on the site were at or near background. Small amounts of contaminated material were found but not enough to exceed the guideline specified.

  14. Apparatus for safeguarding a radiological source

    SciTech Connect (OSTI)

    Bzorgi, Fariborz M

    2014-10-07

    A tamper detector is provided for safeguarding a radiological source that is moved into and out of a storage location through an access porthole for storage and use. The radiological source is presumed to have an associated shipping container approved by the U.S. Nuclear Regulatory Commission for transporting the radiological source. The tamper detector typically includes a network of sealed tubing that spans at least a portion of the access porthole. There is an opening in the network of sealed tubing that is large enough for passage therethrough of the radiological source and small enough to prevent passage therethrough of the associated shipping cask. Generally a gas source connector is provided for establishing a gas pressure in the network of sealed tubing, and a pressure drop sensor is provided for detecting a drop in the gas pressure below a preset value.

  15. DOE Issues WIPP Radiological Release Investigation Report

    Energy.gov [DOE]

    Today, the Department of Energy’s Office of Environmental Management (EM) released the initial accident investigation report related to the Feb. 14 radiological release at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico.

  16. Radiological safety training for uranium facilities

    SciTech Connect (OSTI)

    1998-02-01

    This handbook contains recommended training materials consistent with DOE standardized core radiological training material. These materials consist of a program management guide, instructor`s guide, student guide, and overhead transparencies.

  17. Contained radiological analytical chemistry module

    DOE Patents [OSTI]

    Barney, David M.

    1989-01-01

    A system which provides analytical determination of a plurality of water chemistry parameters with respect to water samples subject to radiological contamination. The system includes a water sample analyzer disposed within a containment and comprising a sampling section for providing predetermined volumes of samples for analysis; a flow control section for controlling the flow through the system; and a gas analysis section for analyzing samples provided by the sampling system. The sampling section includes a controllable multiple port valve for, in one position, metering out sample of a predetermined volume and for, in a second position, delivering the material sample for analysis. The flow control section includes a regulator valve for reducing the pressure in a portion of the system to provide a low pressure region, and measurement devices located in the low pressure region for measuring sample parameters such as pH and conductivity, at low pressure. The gas analysis section which is of independent utility provides for isolating a small water sample and extracting the dissolved gases therefrom into a small expansion volume wherein the gas pressure and thermoconductivity of the extracted gas are measured.

  18. Contained radiological analytical chemistry module

    DOE Patents [OSTI]

    Barney, David M.

    1990-01-01

    A system which provides analytical determination of a plurality of water chemistry parameters with respect to water samples subject to radiological contamination. The system includes a water sample analyzer disposed within a containment and comprising a sampling section for providing predetermined volumes of samples for analysis; a flow control section for controlling the flow through the system; and a gas analysis section for analyzing samples provided by the sampling system. The sampling section includes a controllable multiple port valve for, in one position, metering out sample of a predetermined volume and for, in a second position, delivering the material sample for analysis. The flow control section includes a regulator valve for reducing the pressure in a portion of the system to provide a low pressure region, and measurement devices located in the low pressure region for measuring sample parameters such as pH and conductivity, at low pressure. The gas analysis section which is of independent utility provides for isolating a small water sample and extracting the dissolved gases therefrom into a small expansion volume wherein the gas pressure and thermoconductivity of the extracted gas are measured.

  19. An evaluation of the management system verification pilot at Hanford

    SciTech Connect (OSTI)

    BRIGGS, C.R.

    1998-11-12

    The Chemical Management System (CMS), currently under development at Hanford, was used as the ''test program'' for pilot testing the value added aspects of the Chemical Manufacturers Association's (CMA) Management Systems Verification (MSV) process. The MSV process, which was developed by CMA's member chemical companies specifically as a tool to assist in the continuous improvement of environment, safety and health (ESH) performance, represents a commercial sector ''best practice'' for evaluating ESH management systems. The primary purpose of Hanford's MSV Pilot was to evaluate the applicability and utility of the MSV process in the Department of Energy (DOE) environment. However, because the Integrated Safety Management System (ISMS) is the framework for ESH management at Hanford and at all DOE sites, the pilot specifically considered the MSV process in the context of a possible future adjunct to Integrated Safety Management System Verification (ISMSV) efforts at Hanford and elsewhere within the DOE complex. The pilot involved the conduct of two-hour interviews with four separate panels of individuals with functional responsibilities related to the CMS including the Department of Energy Richland Operations (DOE-RL), Fluor Daniel Hanford (FDH) and FDH's major subcontractors (MSCS). A semi-structured interview process was employed by the team of three ''verifiers'' who directed open-ended questions to the panels regarding the development, integration and effectiveness of management systems necessary to ensure the sustainability of the CMS effort. An ''MSV Pilot Effectiveness Survey'' also was completed by each panel participant immediately following the interview.

  20. Flashback: Rapid scanning for radiological threats

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Flashback: Rapid scanning for radiological threats Flashback: Rapid scanning for radiological threats The ability to identify distinct material density enables the Multi-Mode Passive Detection System (MMPDS)to quickly detect unshielded to heavily shielded nuclear threats, as well as gamma rays, with near-zero false alarms. November 1, 2015 Decision Science Decision Science Decision Sciences' Multi-Mode Passive Detection System: Rapid scanning forradiological threats Click on headline to go to

  1. Environmental Management Headquarters Corrective Action Plan - Radiological

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Release Phase I | Department of Energy I Environmental Management Headquarters Corrective Action Plan - Radiological Release Phase I The purpose of this Corrective Action Plan (CAP) is to specify U.S. Department of Energy (DOE) actions for addressing Office of Environmental Management (EM) Headquarters (HQ) issues identified in the Accident Investigation Report for the Phase 1: Radiological Release Event at the Waste Isolation Pilot Plant (WIPP) on February 14, 2014. The report identified 31

  2. Environmental Management Headquarters Corrective Action Plan - Radiological

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Release Phase II | Department of Energy II Environmental Management Headquarters Corrective Action Plan - Radiological Release Phase II The purpose of this Corrective Action Plan (CAP) is to specify U.S. Department of Energy (DOE) actions for addressing Office of Environmental Management (EM) Headquarters (HQ) issues identified in the Accident Investigation Report for the Phase 2: Radiological Release Event at the Waste Isolation Pilot Plant (WIPP) on February 14, 2014. The report identified

  3. radiological protection | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    protection NNSA Receives Excellence Award for Radiological Security Enhancements in Hawaii HONOLULU - At an official event this week, the City and County of Honolulu presented the Department of Energy's (DOE) National Nuclear Security Administration (NNSA) with the Homeland Security Excellence Award for DOE/NNSA's Office of Radiological Security's (ORS) efforts... Dedication of Radioactive Source Storage Facilities in Tajikistan (Dushanbe, Tajikistan) - On May 11, the United States' Embassy of

  4. Los Alamos responds to radiological incident

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Los Alamos responds to radiological incident Los Alamos responds to radiological incident Multiple tests indicate no health risks to public or employees. August 27, 2012 Aerial view of the Los Alamos Neutron Science Center (LANSCE). Aerial view of the Los Alamos Neutron Science Center (LANSCE). The contamination poses no danger to the public. The Laboratory is investigating the inadvertent spread of Technetium 99 by employees and contractors at the Lujan Neutron Scattering Center August 27,

  5. radiological detection | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    radiological detection Meet a Machine: RPMs keep watch 24/7 to strengthen global nuclear security Ensuring that nuclear materials are not being illicitly moved is part of NNSA's core mission to reduce nuclear and radiological threats. However, since traditional security tools - such as metal detectors, X-ray scanners, and sniffer dogs - cannot measure radiation, frontline... NNSA program strengthens national security from afar The Nuclear Smuggling Detection and Deterrence (NSDD) program is a

  6. Monitoring and verification R&D

    SciTech Connect (OSTI)

    Pilat, Joseph F; Budlong - Sylvester, Kory W; Fearey, Bryan L

    2011-01-01

    The 2010 Nuclear Posture Review (NPR) report outlined the Administration's approach to promoting the agenda put forward by President Obama in Prague on April 5, 2009. The NPR calls for a national monitoring and verification R&D program to meet future challenges arising from the Administration's nonproliferation, arms control and disarmament agenda. Verification of a follow-on to New START could have to address warheads and possibly components along with delivery capabilities. Deeper cuts and disarmament would need to address all of these elements along with nuclear weapon testing, nuclear material and weapon production facilities, virtual capabilities from old weapon and existing energy programs and undeclared capabilities. We only know how to address some elements of these challenges today, and the requirements may be more rigorous in the context of deeper cuts as well as disarmament. Moreover, there is a critical need for multiple options to sensitive problems and to address other challenges. There will be other verification challenges in a world of deeper cuts and disarmament, some of which we are already facing. At some point, if the reductions process is progressing, uncertainties about past nuclear materials and weapons production will have to be addressed. IAEA safeguards will need to continue to evolve to meet current and future challenges, and to take advantage of new technologies and approaches. Transparency/verification of nuclear and dual-use exports will also have to be addressed, and there will be a need to make nonproliferation measures more watertight and transparent. In this context, and recognizing we will face all of these challenges even if disarmament is not achieved, this paper will explore possible agreements and arrangements; verification challenges; gaps in monitoring and verification technologies and approaches; and the R&D required to address these gaps and other monitoring and verification challenges.

  7. Los Alamos National Security Corrective Action Plan - Radiological Release

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Phase II | Department of Energy Security Corrective Action Plan - Radiological Release Phase II Los Alamos National Security Corrective Action Plan - Radiological Release Phase II Los Alamos National Security Corrective Action Plan - Radiological Release Phase II Los Alamos National Security Corrective Action Plan - Radiological Release Phase II (7.59 MB) More Documents & Publications Environmental Management Los Alamos Field Office Corrective Action Plan - Radiological Release Phase II

  8. The DES Science Verification Weak Lensing Shear Catalogs

    DOE PAGES-Beta [OSTI]

    Jarvis, M.

    2016-05-01

    We present weak lensing shear catalogs for 139 square degrees of data taken during the Science Verification (SV) time for the new Dark Energy Camera (DECam) being used for the Dark Energy Survey (DES). We describe our object selection, point spread function estimation and shear measurement procedures using two independent shear pipelines, IM3SHAPE and NGMIX, which produce catalogs of 2.12 million and 3.44 million galaxies respectively. We also detail a set of null tests for the shear measurements and find that they pass the requirements for systematic errors at the level necessary for weak lensing science applications using the SVmore » data. Furthermore, we discuss some of the planned algorithmic improvements that will be necessary to produce sufficiently accurate shear catalogs for the full 5-year DES, which is expected to cover 5000 square degrees.« less

  9. The DES Science Verification Weak Lensing Shear Catalogs

    SciTech Connect (OSTI)

    Jarvis, M.

    2015-07-20

    We present weak lensing shear catalogs for 139 square degrees of data taken during the Science Verification (SV) time for the new Dark Energy Camera (DECam) being used for the Dark Energy Survey (DES). We describe our object selection, point spread function estimation and shear measurement procedures using two independent shear pipelines, IM3SHAPE and NGMIX, which produce catalogs of 2.12 million and 3.44 million galaxies respectively. We also detail a set of null tests for the shear measurements and find that they pass the requirements for systematic errors at the level necessary for weak lensing science applications using the SV data. Furthermore, we discuss some of the planned algorithmic improvements that will be necessary to produce sufficiently accurate shear catalogs for the full 5-year DES, which is expected to cover 5000 square degrees.

  10. Cosmology from Cosmic Shear with DES Science Verification Data

    SciTech Connect (OSTI)

    Abbott, T.

    2015-07-20

    We present the first constraints on cosmology from the Dark Energy Survey (DES), using weak lensing measurements from the preliminary Science Verification (SV) data. We use 139 square degrees of SV data, which is less than 3% of the full DES survey area. Using cosmic shear 2-point measurements over three redshift bins we find ?8(m=0.3)0.5 = 0:81 0:06 (68% confidence), after marginalising over 7 systematics parameters and 3 other cosmological parameters. Furthermore, we examine the robustness of our results to the choice of data vector and systematics assumed, and find them to be stable. About 20% of our error bar comes from marginalising over shear and photometric redshift calibration uncertainties. The current state-of-the-art cosmic shear measurements from CFHTLenS are mildly discrepant with the cosmological constraints from Planck CMB data. Our results are consistent with both datasets. Our uncertainties are ~30% larger than those from CFHTLenS when we carry out a comparable analysis of the two datasets, which we attribute largely to the lower number density of our shear catalogue. We investigate constraints on dark energy and find that, with this small fraction of the full survey, the DES SV constraints make negligible impact on the Planck constraints. The moderate disagreement between the CFHTLenS and Planck values of ?8(?m=0.3)0.5 is present regardless of the value of w.

  11. Land Ice Verification and Validation Kit

    SciTech Connect (OSTI)

    2015-07-15

    To address a pressing need to better understand the behavior and complex interaction of ice sheets within the global Earth system, significant development of continental-scale, dynamical ice-sheet models is underway. The associated verification and validation process of these models is being coordinated through a new, robust, python-based extensible software package, the Land Ice Verification and Validation toolkit (LIVV). This release provides robust and automated verification and a performance evaluation on LCF platforms. The performance V&V involves a comprehensive comparison of model performance relative to expected behavior on a given computing platform. LIVV operates on a set of benchmark and test data, and provides comparisons for a suite of community prioritized tests, including configuration and parameter variations, bit-4-bit evaluation, and plots of tests where differences occur.

  12. Land Ice Verification and Validation Kit

    Energy Science and Technology Software Center (OSTI)

    2015-07-15

    To address a pressing need to better understand the behavior and complex interaction of ice sheets within the global Earth system, significant development of continental-scale, dynamical ice-sheet models is underway. The associated verification and validation process of these models is being coordinated through a new, robust, python-based extensible software package, the Land Ice Verification and Validation toolkit (LIVV). This release provides robust and automated verification and a performance evaluation on LCF platforms. The performance V&Vmore » involves a comprehensive comparison of model performance relative to expected behavior on a given computing platform. LIVV operates on a set of benchmark and test data, and provides comparisons for a suite of community prioritized tests, including configuration and parameter variations, bit-4-bit evaluation, and plots of tests where differences occur.« less

  13. Fuel Retrieval System (FRS) Design Verification

    SciTech Connect (OSTI)

    YANOCHKO, R.M.

    2000-01-27

    This document was prepared as part of an independent review to explain design verification activities already completed, and to define the remaining design verification actions for the Fuel Retrieval System. The Fuel Retrieval Subproject was established as part of the Spent Nuclear Fuel Project (SNF Project) to retrieve and repackage the SNF located in the K Basins. The Fuel Retrieval System (FRS) construction work is complete in the KW Basin, and start-up testing is underway Design modifications and construction planning are also underway for the KE Basin. An independent review of the design verification process as applied to the K Basin projects was initiated in support of preparation for the SNF Project operational readiness review (ORR).

  14. Active alignment/contact verification system

    DOE Patents [OSTI]

    Greenbaum, William M.

    2000-01-01

    A system involving an active (i.e. electrical) technique for the verification of: 1) close tolerance mechanical alignment between two component, and 2) electrical contact between mating through an elastomeric interface. For example, the two components may be an alumina carrier and a printed circuit board, two mating parts that are extremely small, high density parts and require alignment within a fraction of a mil, as well as a specified interface point of engagement between the parts. The system comprises pairs of conductive structures defined in the surfaces layers of the alumina carrier and the printed circuit board, for example. The first pair of conductive structures relate to item (1) above and permit alignment verification between mating parts. The second pair of conductive structures relate to item (2) above and permit verification of electrical contact between mating parts.

  15. Fuel Retrieval System Design Verification Report

    SciTech Connect (OSTI)

    GROTH, B.D.

    2000-04-11

    The Fuel Retrieval Subproject was established as part of the Spent Nuclear Fuel Project (SNF Project) to retrieve and repackage the SNF located in the K Basins. The Fuel Retrieval System (FRS) construction work is complete in the KW Basin, and start-up testing is underway. Design modifications and construction planning are also underway for the KE Basin. An independent review of the design verification process as applied to the K Basin projects was initiated in support of preparation for the SNF Project operational readiness review (ORR). A Design Verification Status Questionnaire, Table 1, is included which addresses Corrective Action SNF-EG-MA-EG-20000060, Item No.9 (Miller 2000).

  16. M&V Guidelines: Measurement and Verification for Federal Energy...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    M&V Guidelines: Measurement and Verification for Federal Energy Projects (Version 4.0) M&V Guidelines: Measurement and Verification for Federal Energy Projects (Version 4.0) ...

  17. M&V Guidelines: Measurement and Verification for Performance...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    You are here Home M&V Guidelines: Measurement and Verification for Performance-Based Contracts (Version 4.0) M&V Guidelines: Measurement and Verification for Performance-Based ...

  18. AHAM Letter Acknowledging DOE Letter on Verification Program | Department

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    of Energy Letter Acknowledging DOE Letter on Verification Program AHAM Letter Acknowledging DOE Letter on Verification Program This document is a response to the letter dated April 26, 2013, in which DOE adopted a new policy regarding DOE ENERGY STAR verification testing of models that are part of the AHAM verification program for clothes washers, dishwashers, and residential refrigerator/freezers. aham_response_doe_letter.pdf (80.05 KB) More Documents & Publications This letter is to

  19. Become an SEP Verification Body | Department of Energy

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Verification Body Become an SEP Verification Body Superior Energy Performance logo Conformity assessment bodies can expand their services and be prepared for customers pursuing Superior Energy Performance® (SEP(tm)) certification. Only ANSI-ANAB-accredited SEP Verification Bodies can certify facilities to SEP. SEP Verification Bodies are required to: conform to the ANSI/MSE 50028 standard obtain ANSI-ANAB accreditation sign an SEP participation agreement with the SEP Administrator (U.S.

  20. Recommendation 165: Recommendation on Conducting Future Verifications of Cleanup

    Energy.gov [DOE]

    The ORSSAB commends the DOE policy of obtaining independent verification of DOE Environmental Management-related activities.

  1. ETA-HTP11 - Vehicle Verification - Revision 1

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    1 Revision 1 Effective October 1, 2005 Vehicle Verification Prepared by Electric Transportation Applications Prepared by: ... Date:... Garrett ...

  2. Supplement No. 2 to the FUSRAP Summary Protocol - Verification and

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Certification Protocol | Department of Energy 2 to the FUSRAP Summary Protocol - Verification and Certification Protocol Supplement No. 2 to the FUSRAP Summary Protocol - Verification and Certification Protocol Supplement No. 2 to the FUSRAP Summary Protocol - Verification and Certification Protocol (November 1985, Rev. 1) Supplement No. 2 to the FUSRAP Summary Protocol - Verification and Certification Protocol (November 1985, Rev. 1) (1.14 MB) More Documents & Publications Supplement

  3. Invited book review for AIAA Journal of verification of computer...

    Office of Scientific and Technical Information (OSTI)

    Country of Publication: United States Language: English Subject: 99 GENERAL AND MISCELLANEOUSMATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; COMPUTER CODES; VERIFICATION; SANDIA ...

  4. Federal Radiological Monitoring and Assessment Center Overview of FRMAC Operations

    SciTech Connect (OSTI)

    1998-03-01

    In the event of a major radiological emergency, 17 federal agencies with various statutory responsibilities have agreed to coordinate their efforts at the emergency scene under the umbrella of the Federal Radiological Emergency Response Plan. This cooperative effort will ensure that all federal radiological assistance fully supports their efforts to protect the public. the mandated federal cooperation ensures that each agency can obtain the data critical to its specific responsibilities. This Overview of Federal Radiological Monitoring and Assessment Center (FRMAC) describes the FRMAC response activities to a major radiological emergency. It also describes the federal assets and subsequent operational activities which provide federal radiological monitoring and assessment of the off-site areas.

  5. Interventional Radiology of Male Varicocele: Current Status

    SciTech Connect (OSTI)

    Iaccarino, Vittorio Venetucci, Pietro

    2012-12-15

    Varicocele is a fairly common condition in male individuals. Although a minor disease, it may cause infertility and testicular pain. Consequently, it has high health and social impact. Here we review the current status of interventional radiology of male varicocele. We describe the radiological anatomy of gonadal veins and the clinical aspects of male varicocele, particularly the physical examination, which includes a new clinical and ultrasound Doppler maneuver. The surgical and radiological treatment options are also described with the focus on retrograde and antegrade sclerotherapy, together with our long experience with these procedures. Last, we compare the outcomes, recurrence and persistence rates, complications, procedure time and cost-effectiveness of each method. It clearly emerges from this analysis that there is a need for randomized multicentre trials designed to compare the various surgical and percutaneous techniques, all of which are aimed at occlusion of the anterior pampiniform plexus.

  6. Routine Radiological Environmental Monitoring Plan. Volume 1

    SciTech Connect (OSTI)

    Bechtel Nevada

    1999-12-31

    The U.S. Department of Energy manages the Nevada Test Site in a manner that meets evolving DOE Missions and responds to the concerns of affected and interested individuals and agencies. This Routine Radiological Monitoring Plan addressess complicance with DOE Orders 5400.1 and 5400.5 and other drivers requiring routine effluent monitoring and environmental surveillance on the Nevada Test Site. This monitoring plan, prepared in 1998, addresses the activities conducted onsite NTS under the Final Environmental Impact Statement and Record of Decision. This radiological monitoring plan, prepared on behalf of the Nevada Test Site Landlord, brings together sitewide environmental surveillance; site-specific effluent monitoring; and operational monitoring conducted by various missions, programs, and projects on the NTS. The plan provides an approach to identifying and conducting routine radiological monitoring at the NTS, based on integrated technical, scientific, and regulatory complicance data needs.

  7. Emergency Response Planning for Radiological Releases

    SciTech Connect (OSTI)

    Biwer, B.M.; LePoire, D.J.; Lazaro, M.A.; Allison, T.; Kamboj, S.; Chen, S.Y.

    2006-07-01

    The emergency management planning tool RISK-RDD was developed to aid emergency response planners and decision makers at all levels of government to better understand and prepare for potential problems related to a radiological release, especially those in urban areas. Radioactive release scenarios were studied by using the RISK-RDD radiological emergency management program. The scenarios were selected to investigate the key aspects of radiological risk management not always considered in emergency planning as a whole. These aspects include the evaluation of both aerosolized and non-aerosolized components of an atmospheric release, methods of release, acute and chronic human health risks, and the concomitant economic impacts as a function of the risk-based cleanup level. (authors)

  8. SU-E-T-435: Development and Commissioning of a Complete System for In-Vivo Dosimetry and Range Verification in Proton Therapy

    SciTech Connect (OSTI)

    Samuel, D; Testa, M; Park, Y; Schneider, R; Moteabbed, M; Janssens, G; Prieels, D; Orban de Xivry, J; Lu, H; Bentefour, E

    2014-06-01

    Purpose: In-vivo dose and beam range verification in proton therapy could play significant roles in proton treatment validation and improvements. Invivo beam range verification, in particular, could enable new treatment techniques one of which, for example, could be the use of anterior fields for prostate treatment instead of opposed lateral fields as in current practice. We have developed and commissioned an integrated system with hardware, software and workflow protocols, to provide a complete solution, simultaneously for both in-vivo dosimetry and range verification for proton therapy. Methods: The system uses a matrix of diodes, up to 12 in total, but separable into three groups for flexibility in application. A special amplifier was developed to capture extremely small signals from very low proton beam current. The software was developed within iMagX, a general platform for image processing in radiation therapy applications. The range determination exploits the inherent relationship between the internal range modulation clock of the proton therapy system and the radiological depth at the point of measurement. The commissioning of the system, for in-vivo dosimetry and for range verification was separately conducted using anthropomorphic phantom. EBT films and TLDs were used for dose comparisons and range scan of the beam distal fall-off was used as ground truth for range verification. Results: For in-vivo dose measurement, the results were in agreement with TLD and EBT films and were within 3% from treatment planning calculations. For range verification, a precision of 0.5mm is achieved in homogeneous phantoms, and a precision of 2mm for anthropomorphic pelvic phantom, except at points with significant range mixing. Conclusion: We completed the commissioning of our system for in-vivo dosimetry and range verification in proton therapy. The results suggest that the system is ready for clinical trials on patient.

  9. Radiological Assessment for the Vance Road Facility Source Vault, Oak Ridge Institute for Science and Education, Oak Ridge, Tennessee

    SciTech Connect (OSTI)

    J. R. Morton

    2000-09-01

    From the 1950s, the Vance Road laboratories had been used for a broad range of nuclear medicine research involving numerous radionuclides. These radionuclides were stored in the a source vault located on the first floor of the facility. The Environmental Survey and Site Assessment Program (ESSAP) of ORISE performed a radiological assessment survey of the source vault after it had been remediated and in preparation for converting the area to office space.

  10. RELAP-7 SOFTWARE VERIFICATION AND VALIDATION PLAN

    SciTech Connect (OSTI)

    Smith, Curtis L; Choi, Yong-Joon; Zou, Ling

    2014-09-01

    This INL plan comprehensively describes the software for RELAP-7 and documents the software, interface, and software design requirements for the application. The plan also describes the testing-based software verification and validation (SV&V) process—a set of specially designed software models used to test RELAP-7.

  11. Nuclear Verification | National Nuclear Security Administration | (NNSA)

    National Nuclear Security Administration (NNSA)

    Control Nuclear Verification Challenge: Maintain the U.S. ability to monitor and verify nuclear reduction agreements and detect violations of treaties and other nuclear nonproliferation commitments. Solution: Develop and deploy measures to ensure verifiable compliance with treaties and other international agreements, implement regimes to reduce nuclear weapons, and detect and dismantle undeclared nuclear programs. Specific subprogram activities include: Implementing current and developing future

  12. The year book of diagnostic radiology 1981

    SciTech Connect (OSTI)

    Whitehouse, W.M.; Adams, D.F.; Bookstein, J.J.; Gabrielsen, T.O.; Holt, J.F.; Martel, W.; Silver, T.M.; Thornbury, J.R.

    1981-01-01

    The 1981 edition of the Year Book of Diagnostic Radiology fulfills the standards of excellence established by previous volumes in this series. The abstracts were carefully chosen, are concise, and are well illustrated. The book is recommended for all practicing radiologists: for the resident it is a good source from which to select articles to be carefully studied, and as review source before board examinations; for the subspecialist it provides a means to maintain contact with all areas of diagnostic radiology; and for the general radiologist, it is a convenient and reliable guide to new developments in the specialty.

  13. Fiber-coupled Luminescence Dosimetry in Therapeutic and Diagnostic Radiology

    SciTech Connect (OSTI)

    Andersen, Claus E.

    2011-05-05

    Fiber-coupled luminescence dosimetry is an emerging technology with several potentially attractive features of relevance for uses in therapeutic and diagnostic radiology: direct water equivalence (i.e. no significant perturbation of the radiation field in a water phantom or a patient), sub-mm detector size, high dynamic range (below a mGy to several Gy), microsecond time resolution, and absence of electrical wires or other electronics in the dosimeter probe head. Fiber-coupled luminescence dosimetry systems typically consist of one or more small samples of phosphor, e.g. a mg of plastic scintillator, attached to 10-20 m long optical fiber cables of plastic. During irradiation, each dosimeter probe spontaneously emits radioluminescence (RL) in proportion to the dose rate. The luminescence intensity can be detected with photomultiplier tubes, CCD cameras or other highly sensitive photodetectors. Some crystalline phosphors, such as carbon-doped aluminium oxide (Al{sub 2}O{sub 3}:C) have the ability to store charge produced in the crystal during irradiation. The stored charge may later be released by fiber-guided laser light under emission of so-called optically stimulated luminescence (OSL). The OSL signal therefore reflects the passively integrated dose. In contrast to thermoluminescence dosimetry, fiber-coupled OSL dosimetry may be performed in vivo while the dosimeter is still in the patient. Within the last few years, several improvements and new applications of these techniques have been published, and the objective of this review is to provide an introduction to this field and to outline some of these new results. Emphasis will be given to applications in medical dosimetry such as in vivo real-time dose verification in brachytherapy and methods aimed for improved quality assurance of linear accelerators.

  14. The AdaptiV Approach to Verification of Adaptive Systems

    SciTech Connect (OSTI)

    Rouff, Christopher; Buskens, Richard; Pullum, Laura L; Cui, Xiaohui; Hinchey, Mike

    2012-01-01

    Adaptive systems are critical for future space and other unmanned and intelligent systems. Verification of these systems is also critical for their use in systems with potential harm to human life or with large financial investments. Due to their nondeterministic nature and extremely large state space, current methods for verification of software systems are not adequate to provide a high level of assurance. The combination of stabilization science, high performance computing simulations, compositional verification and traditional verification techniques, plus operational monitors, provides a complete approach to verification and deployment of adaptive systems that has not been used before. This paper gives an overview of this approach.

  15. DOE-HDBK-1122-99; Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ALARA Instructor's Guide 1.10-1 Course Title: Radiological Control Technician Module ... Energy, DOE-STD-1098-99, "Radiological Control Standard" 3. 10 CFR Part 835 (1998), ...

  16. DOE-HDBK-1122-99; Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    R. L.; PNL; Richland, Wa. 3. DOE-STD-1098-99, "Radiological Control Standard." 4. 10 CFR Part 835 (1998) "Occupational Radiation Protection" 5. "The Health Physics and Radiological ...

  17. Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant

    Energy.gov [DOE]

    NNSA presentation on Radiological Assessment of effects from Fukushima Daiichi Nuclear Power Plant from May 13, 2011

  18. Office of Radiological Security | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Radiological Security NNSA Receives Excellence Award for Radiological Security Enhancements in Hawaii HONOLULU - At an official event this week, the City and County of Honolulu presented the Department of Energy's (DOE) National Nuclear Security Administration (NNSA) with the Homeland Security Excellence Award for DOE/NNSA's Office of Radiological Security's (ORS) efforts... NNSA Provides Tajikistan Specialized Vehicles to Transport Radiological Materials NNSA Program Manager Nick Cavellero,

  19. Radiological Security Program | National Nuclear Security Administration

    National Nuclear Security Administration (NNSA)

    Radiological Security Program Armenia Secures Dangerous Radioactive Sources in Cooperation with NNSA The Department of Energy's National Nuclear Security Administration (NNSA) joined the Republic of Armenia today to announce the safe and secure removal of three unused radioactive sources from two locations in Yerevan, Armenia. The successful completion of the radioactive source recovery campaign

  20. Radiological/biological/aerosol removal system

    DOE Patents [OSTI]

    Haslam, Jeffery J

    2015-03-17

    An air filter replacement system for existing buildings, vehicles, arenas, and other enclosed airspaces includes a replacement air filter for replacing a standard air filter. The replacement air filter has dimensions and air flow specifications that allow it to replace the standard air filter. The replacement air filter includes a filter material that removes radiological or biological or aerosol particles.

  1. Development of radiological concentrations and unit liter doses for TWRS FSAR radiological consequence calculations

    SciTech Connect (OSTI)

    Cowley, W.L.

    1996-04-25

    The analysis described in this report develops the Unit Liter Doses for use in the TWRS FSAR. The Unit Liter Doses provide a practical way to calculate conservative radiological consequences for a variety of potential accidents for the tank farms.

  2. Confirmatory Survey for the Partial Site Release at the ABB Inc. CE Winsor Site, Windsor, CT

    SciTech Connect (OSTI)

    W.C. Adams

    2008-06-27

    The objectives of the confirmatory surveys were to confirm that remedial actions had been effective in meeting established release criteria and that documentation accurately and adequately describes the final radiological conditions of the PSR Impacted Areas.

  3. EOSO ENERGY MEASUREMENTS GROUP THE REMOT SENSIN EG&G SURVEY REPORT...

    Office of Legacy Management (LM)

    Oe. 1-G lZLq n EOSO ENERGY MEASUREMENTS GROUP THE REMOT SENSIN EG&G SURVEY REPORT LABORATO EP-F-002 Of THE UNITED STATES DECEMBER 1981 DEPARTMENT OF ENERGY AN AERIAL RADIOLOGICAL ...

  4. ENERGY MEASUREMENTS GROUP EG&G SURVEY REPORT NE-F-003

    Office of Legacy Management (LM)

    * * nEGc.G ENERGY MEASUREMENTS GROUP EG&G SURVEY REPORT NE-F-003 FEBRUARY 1983 THE REMOTE SENSING LABORATORY OF THE UNITED STATES DEPARTMENT OF ENERGY AN AERIAL RADIOLOGICAL ...

  5. Packaged low-level waste verification system

    SciTech Connect (OSTI)

    Tuite, K.; Winberg, M.R.; McIsaac, C.V.

    1995-12-31

    The Department of Energy through the National Low-Level Waste Management Program and WMG Inc. have entered into a joint development effort to design, build, and demonstrate the Packaged Low-Level Waste Verification System. Currently, states and low-level radioactive waste disposal site operators have no method to independently verify the radionuclide content of packaged low-level waste that arrives at disposal sites for disposition. At this time, the disposal site relies on the low-level waste generator shipping manifests and accompanying records to ensure that low-level waste received meets the site`s waste acceptance criteria. The subject invention provides the equipment, software, and methods to enable the independent verification of low-level waste shipping records to ensure that the site`s waste acceptance criteria are being met. The objective of the prototype system is to demonstrate a mobile system capable of independently verifying the content of packaged low-level waste.

  6. GRIMHX verification and validation action matrix summary

    SciTech Connect (OSTI)

    Trumble, E.F.

    1991-12-01

    WSRC-RP-90-026, Certification Plan for Reactor Analysis Computer Codes, describes a series of action items to be completed for certification of reactor analysis computer codes used in Technical Specifications development and for other safety and production support calculations. Validation and verification of the code is an integral part of this process. This document identifies the work performed and documentation generated to satisfy these action items for the Reactor Physics computer code GRIMHX. Each action item is discussed with the justification for its completion. Specific details of the work performed are not included in this document but are found in the references. The publication of this document signals the validation and verification effort for the GRIMHX code is completed.

  7. Systems Approach to Arms Control Verification

    SciTech Connect (OSTI)

    Allen, K; Neimeyer, I; Listner, C; Stein, G; Chen, C; Dreicer, M

    2015-05-15

    Using the decades of experience of developing concepts and technologies for verifying bilateral and multilateral arms control agreements, a broad conceptual systems approach is being developed that takes into account varying levels of information and risk. The IAEA has already demonstrated the applicability of a systems approach by implementing safeguards at the State level, with acquisition path analysis as the key element. In order to test whether such an approach could also be implemented for arms control verification, an exercise was conducted in November 2014 at the JRC ITU Ispra. Based on the scenario of a hypothetical treaty between two model nuclear weapons states aimed at capping their nuclear arsenals at existing levels, the goal of this exercise was to explore how to use acquisition path analysis in an arms control context. Our contribution will present the scenario, objectives and results of this exercise, and attempt to define future workshops aimed at further developing verification measures that will deter or detect treaty violations.

  8. NGSI: IAEA Verification of UF6 Cylinders

    SciTech Connect (OSTI)

    Curtis, Michael M.

    2012-06-05

    The International Atomic Energy Agency (IAEA) is often ignorant of the location of declared, uranium hexafluoride (UF6) cylinders following verification, because cylinders are not typically tracked onsite or off. This paper will assess various methods the IAEA uses to verify cylinder gross defects, and how the task could be ameliorated through the use of improved identification and monitoring. The assessment will be restricted to current verification methods together with one that has been applied on a trial basis—short-notice random inspections coupled with mailbox declarations. This paper is part of the NNSA Office of Nonproliferation and International Security’s Next Generation Safeguards Initiative (NGSI) program to investigate the concept of a global monitoring scheme that uniquely identifies and tracks UF6 cylinders.

  9. TWRS system drawings and field verification

    SciTech Connect (OSTI)

    Shepard, D.G.

    1995-04-11

    The Configuration Management Program combines the TWRS Labeling and O and M drawing and drawing verification programs. The combined program will produce system drawings for systems that are normally operated or have maintenance performed on the system, label individual pieces of equipment for proper identification, even if system drawings are not warranted, and perform verification of drawings that are identified as essential in Tank Farm Essential Drawing Plans. During fiscal year 1994, work was begun to label Tank Farm components and provide user friendly system based drawings for Tank Waste Remediation System (TWRS) operations and maintenance. During the first half of fiscal 1995, the field verification program continued to convert TWRS drawings into CAD format and verify the accuracy based on visual inspections. During the remainder of fiscal year 1995 these efforts will be combined into a single program providing system based drawings and field verification of TWRS equipment and facilities. This combined program for TWRS will include all active systems for tank farms. Operations will determine the extent of drawing and labeling requirements for single shell tanks, i.e. the electrical distribution, HVAC, leak detection, and the radiation monitoring system. The tasks required to meet these objectives, include the following: identify system boundaries or scope for drawing being verified; label equipment/components in the process systems with a unique Equipment Identification Number (EIN) per the TWRS Data Standard; develop system drawings that are coordinated by ``smart`` drawing numbers and/or drawing references as identified on H-14-020000; develop a Master Equipment List (MEL) multi-user data base application which will contain key information about equipment identified in the field; and field verify and release TWRS Operation and Maintenance (O and M) drawings.

  10. DOE Zero Energy Ready Home Verification Summary

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Zero Energy Ready Home Verification Summary DRAFT REM/Rate - Residential Energy Analysis and Rating Software v14.5.1 This information does not constitute any warranty of energy cost or savings. © 1985-2014 Architectural Energy Corporation, Boulder, Colorado. Projected Rating: Based on Plans - Field Confirmation Required. Energy Performance House Type DOE Zero Energy Ready Home Builder Partner ID# Single-family detached 12345 Year built Square footage of Conditioned Space including Basement 2013

  11. Paint for detection of radiological or chemical agents

    DOE Patents [OSTI]

    Farmer, Joseph C.; Brunk, James L.; Day, Sumner Daniel

    2010-08-24

    A paint that warns of radiological or chemical substances comprising a paint operatively connected to the surface, an indicator material carried by the paint that provides an indication of the radiological or chemical substances, and a thermo-activation material carried by the paint. In one embodiment, a method of warning of radiological or chemical substances comprising the steps of painting a surface with an indicator material, and monitoring the surface for indications of the radiological or chemical substances. In another embodiment, a paint is operatively connected to a vehicle and an indicator material is carried by the paint that provides an indication of the radiological or chemical substances.

  12. Technical safety requirements control level verification

    SciTech Connect (OSTI)

    STEWART, J.L.

    1999-05-21

    A Technical Safety Requirement (TSR) control level verification process was developed for the Tank Waste Remediation System (TWRS) TSRs at the Hanford Site in Richland, WA, at the direction of the US. Department of Energy, Richland Operations Office (RL). The objective of the effort was to develop a process to ensure that the TWRS TSR controls are designated and managed at the appropriate levels as Safety Limits (SLs), Limiting Control Settings (LCSs), Limiting Conditions for Operation (LCOs), Administrative Controls (ACs), or Design Features. The TSR control level verification process was developed and implemented by a team of contractor personnel with the participation of Fluor Daniel Hanford, Inc. (FDH), the Project Hanford Management Contract (PHMC) integrating contractor, and RL representatives. The team was composed of individuals with the following experience base: nuclear safety analysis; licensing; nuclear industry and DOE-complex TSR preparation/review experience; tank farm operations; FDH policy and compliance; and RL-TWRS oversight. Each TSR control level designation was completed utilizing TSR control logic diagrams and TSR criteria checklists based on DOE Orders, Standards, Contractor TSR policy, and other guidance. The control logic diagrams and criteria checklists were reviewed and modified by team members during team meetings. The TSR control level verification process was used to systematically evaluate 12 LCOs, 22 AC programs, and approximately 100 program key elements identified in the TWRS TSR document. The verification of each TSR control required a team consensus. Based on the results of the process, refinements were identified and the TWRS TSRs were modified as appropriate. A final report documenting key assumptions and the control level designation for each TSR control was prepared and is maintained on file for future reference. The results of the process were used as a reference in the RL review of the final TWRS TSRs and control suite. RL

  13. Thoughts on Verification of Nuclear Disarmament

    SciTech Connect (OSTI)

    Dunlop, W H

    2007-09-26

    It is my pleasure to be here to day to participate in this Conference. My thanks to the organizers for preparing such an interesting agenda on a very difficult topic. My effort in preparing my presentation was performed under the auspices of the U.S. Department of Energy by University of California, Lawrence Livermore National Laboratory under Contract W-7405-Eng-48. And as many of you know Lawrence Livermore National Laboratory is now, as of Oct 1st, under contract to the Lawrence Livermore National Security LLC. There has been a long history of how to view verification of arms control agreements. The basis for verification during the days of SALT was that verification would be based on each country's national technical means. For treaties dealing with strategic missiles this worked well as the individual items subject to verification were of such a size that they were visible by the National Technical Means available at the time. And it was felt that the counting of missiles and launchers could be verified by our National Technical Means. For nuclear testing treaties the use of seismic measurements developed into a capability that was reasonably robust for all but the smallest of nuclear tests. However, once we had the Threshold Test Ban Treaty, there was a significant problem in that the fidelity of the measurements were not sufficient to determine if a test was slightly above the 150 kt limit or slightly below the 150 kt limit. This led some in the US to believe that the Soviet Union was not living up to the TTBT agreement. An on-site verification protocol was negotiated in 1988 and 1989 that allowed the US to make hydrodynamic yield measurements on Soviet tests above 50 kt yield and regional seismic measurements on all tests above 35 kt of yield; and the Soviets to make the same type of measurements on US tests to ensure that they were not over 150 kt. These on-site measurements were considered reasonably intrusive. Again the measurement capability was not

  14. NV/YMP RADIOLOGICAL CONTROL MANUAL

    SciTech Connect (OSTI)

    U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE; BECHTEL NEVADA

    2004-11-01

    This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and the Yucca Mountain Office of Repository Development (YMORD). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations Part 835 (10 CFR 835), Occupational Radiation Protection. Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Pleasanton, California; and at Andrews Air Force Base, Maryland. In addition, field work by NNSA/NSO at other locations is also covered by this manual.

  15. Nevada National Security Site Radiological Control Manual

    SciTech Connect (OSTI)

    Radiological Control Managers’ Council

    2012-03-26

    This document supersedes DOE/NV/25946--801, 'Nevada Test Site Radiological Control Manual,' Revision 1 issued in February 2010. Brief Description of Revision: A complete revision to reflect a recent change in name for the NTS; changes in name for some tenant organizations; and to update references to current DOE policies, orders, and guidance documents. Article 237.2 was deleted. Appendix 3B was updated. Article 411.2 was modified. Article 422 was re-written to reflect the wording of DOE O 458.1. Article 431.6.d was modified. The glossary was updated. This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE) and the U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office (NNSA/NSO). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations (CFR) Part 835, 'Occupational Radiation Protection.' Programs covered by this manual are located at the Nevada National Security Site (NNSS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Livermore, California; and Andrews Air Force Base, Maryland. In addition, fieldwork by NNSA/NSO at other locations is covered by this manual. Current activities at NNSS include operating low-level radioactive and mixed waste disposal facilities for United States defense-generated waste, assembly and execution of subcritical experiments, assembly/disassembly of special experiments, the storage and use of special nuclear materials, performing criticality experiments, emergency responder training, surface cleanup and site characterization of contaminated land areas, environmental activity by the University system, and nonnuclear test operations, such as controlled spills of hazardous materials at the Hazardous Materials Spill Center. Currently, the major potential for occupational radiation exposure is associated with the burial of

  16. Fixation of Radiological Contamination; International Collaborative Development

    SciTech Connect (OSTI)

    Rick Demmer

    2013-03-01

    A cooperative international project was conducted by the Idaho National Laboratory (INL) and the United Kingdoms National Nuclear Laboratory (NNL) to integrate a capture coating with a high performance atomizing process. The initial results were promising, and lead to further trials. The somewhat longer testing and optimization process has resulted in a product that could be demonstrated in the field to reduce airborne radiological dust and contamination.

  17. Enewetak radiological support project. Final report

    SciTech Connect (OSTI)

    Friesen, B.

    1982-09-01

    From 1972 through 1980, the Department of Energy acted in an advisory role to the Defense Nuclear Agency during planning for and execution of the cleanup of Enewetak Atoll. The Nevada Operations Office of the Department of Energy was responsible for the radiological characterization of the atoll and for certification of radiological condition of each island upon completion of the project. In-situ measurements of gamma rays emitted by americium-241 were utilized along with wet chemistry separation of plutonium from soil samples to identify and delineate surface areas requiring removal of soil. Military forces removed over 100,000 cubic yards of soil from the surface of five islands and deposited this material in a crater remaining from the nuclear testing period. Subsurface soil was excavated and removed from several locations where measurements indicated the presence of radionuclides above predetermined criteria. The methodologies of data acquisition, analysis and interpretation are described and detailed results are provided in text, figures and microfiche. The final radiological condition of each of 43 islets is reported.

  18. Verification and validation plan for the SFR system analysis module

    SciTech Connect (OSTI)

    Hu, R.

    2014-12-18

    This report documents the Verification and Validation (V&V) Plan for software verification and validation of the SFR System Analysis Module (SAM), developed at Argonne National Laboratory for sodium fast reactor whole-plant transient analysis. SAM is developed under the DOE NEAMS program and is part of the Reactor Product Line toolkit. The SAM code, the phenomena and computational models of interest, the software quality assurance, and the verification and validation requirements and plans are discussed in this report.

  19. Evaluation, Measurement, and Verification of Energy Data | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Evaluation, Measurement, and Verification of Energy Data Evaluation, Measurement, and Verification of Energy Data Evaluation, measurement, and verification (EM&V) is the collection of methods and processes used to assess the performance of energy efficiency activities so planned results can be achieved with greater certainty and future activities can be more effective. The main objectives of an EM&V process are to assess the performance of an energy efficiency program or

  20. Reviewing Measurement and Verification Plans for Federal ESPC Projects |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Reviewing Measurement and Verification Plans for Federal ESPC Projects Reviewing Measurement and Verification Plans for Federal ESPC Projects Document provides a framework for implementing uniform and consistent reviews of measurement and verification plans for federal energy savings performance contract (ESPC) projects. Download the review framework. (184.56 KB) More Documents & Publications Reviewing Post-Installation and Annual Reports for Federal ESPC Projects

  1. Measurement and Verification of Low Income Energy Efficiency...

    Open Energy Information (Open El) [EERE & EIA]

    URI: cleanenergysolutions.orgcontentmeasurement-and-verification-low-inco Language: English Policies: "Regulations,Financial Incentives" is not in the list of possible...

  2. CHARPY IMPACT TEST RESULTS ON FIVE MAERIALS AND NIST VERIFICATION...

    Office of Scientific and Technical Information (OSTI)

    CHARPY IMPACT TEST RESULTS ON FIVE MAERIALS AND NIST VERIFICATION SPECIMENS USING ... Randy K, Nanstad' and Mikbail A. Sokolov' cHARPY IMPACT' TEST RESULTS ON FIVE MATERIALS ...

  3. Measurement and Verification of Energy Savings and Performance...

    Office of Environmental Management (EM)

    Savings and Performance from Advanced Lighting Controls Measurement and Verification of Energy Savings and Performance from Advanced Lighting Controls This document provides a ...

  4. Verification of the Time Evolution of Cosmological Simulations...

    Office of Scientific and Technical Information (OSTI)

    Country of Publication: United States Language: English Subject: 71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS; ACCURACY; ALGORITHMS; COSMOLOGY; SIMULATION; VERIFICATION Word ...

  5. ON THE EXPERIMENTAL VERIFICATION AND DETERMINATION OF PARAMETERS...

    Office of Scientific and Technical Information (OSTI)

    Title: ON THE EXPERIMENTAL VERIFICATION AND DETERMINATION OF PARAMETERS OF STOPPING-POWER THEORY Authors: Turner, J. E. Publication Date: 1964-01-01 OSTI Identifier: 4887408 Report ...

  6. Design, Installation, and Field Verification of Integrated Active...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Cogeneration Package, 2008 Design, Installation, and Field Verification of Integrated Active Desiccant Hybrid Rooftop Systems Combined with a Natural Gas Driven Cogeneration ...

  7. Measurement and Verification for Federal Energy Savings Performance...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Measurement and verification (M&V) activities help agencies confirm that legally and ... When done correctly, M&V: Appropriately allocates risks Reduces uncertainty of savings ...

  8. Measurement and Verification Plan and Savings Calculations Methods...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Methods Outline (IDIQ Attachment J-8) Measurement and Verification Plan and Savings Calculations Methods Outline (IDIQ Attachment J-8) Document outlines measurement and ...

  9. NNSA Begins New Campaign of Verification Experiments at Nevada...

    National Nuclear Security Administration (NNSA)

    NNSA Begins New Campaign of Verification Experiments at Nevada National Security Site May ... are being conducted at NNSA's Nevada National Security Site (NNSS) and will ...

  10. Microsoft Word - Advanced Solution Verification of CFD Solutions...

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    verification (i.e., numerical error estimation) techniques on computational fluid dynamics simulations of interest to CASL. The specific case chosen is the G TRF---related f ...

  11. Verification Method for SSI Problems with Extended Parameter Ranges

    Office of Energy Efficiency and Renewable Energy (EERE)

    Verification Method for SSI Problems with Extended Parameter Ranges 2014 U.S. DOE Natural Phenomena Hazards Meeting Carl J. Costantino and Associates www.cjcassoc.com

  12. Verification of the Time Evolution of Cosmological Simulations...

    Office of Scientific and Technical Information (OSTI)

    Journal Article: Verification of the Time Evolution of Cosmological Simulations via Hypothesis-Driven Comparative and Quantitative Visualization Citation Details In-Document Search...

  13. DOE Verification Testing in Support of ENERGY STAR, April 22...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Comment submitted by Hoshizaki America, Inc. regarding the Energy Star Verification Testing Program Comment submitted by the North American Association of Food Equipment ...

  14. Energy Star Lighting Verification Program (Program for the Evaluation...

    Office of Scientific and Technical Information (OSTI)

    Technical Report: Energy Star Lighting Verification Program (Program for the Evaluation and Analysis of Residential Lighting) Citation Details In-Document Search Title: Energy Star ...

  15. NEMVP: North American energy measurement and verification protocol

    SciTech Connect (OSTI)

    1996-03-01

    This measurement and verification protocol discusses procedures that,when implemented, allow buyers, sellers, and financiers of energy projects to quantify energy conservation measure performance and savings.

  16. Advanced Waste Management Now Available as Accredited SEP Verification...

    Office of Environmental Management (EM)

    Technical Assistance Superior Energy Performance Advanced Waste Management Now Available as Accredited SEP Verification Body Advanced Waste Management Now Available as ...

  17. Measurement and Verification for Federal Energy Savings Performance Contracts

    Energy.gov [DOE]

    Measurement and verification (M&V) activities help agencies confirm that legally and contractually required savings guarantees are met in federal energy savings performance contracts (ESPCs).

  18. A golden anniversary for space-based treaty verification

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    ... bursts, X-ray novae and solar wind composition. Modern space-based verification systems rely on ... Cibola's supercomputer is testing new power sources and new strategies ...

  19. Accelerating functional verification of an integrated circuit

    SciTech Connect (OSTI)

    Deindl, Michael; Ruedinger, Jeffrey Joseph; Zoellin, Christian G.

    2015-10-27

    Illustrative embodiments include a method, system, and computer program product for accelerating functional verification in simulation testing of an integrated circuit (IC). Using a processor and a memory, a serial operation is replaced with a direct register access operation, wherein the serial operation is configured to perform bit shifting operation using a register in a simulation of the IC. The serial operation is blocked from manipulating the register in the simulation of the IC. Using the register in the simulation of the IC, the direct register access operation is performed in place of the serial operation.

  20. Accelerating functional verification of an integrated circuit

    DOE Patents [OSTI]

    Deindl, Michael; Ruedinger, Jeffrey Joseph; Zoellin, Christian G

    2015-11-05

    Illustrative embodiments include a method, system, and computer program product for accelerating functional verification in simulation testing of an integrated circuit (IC). Using a processor and a memory, a serial operation is replaced with a direct register access operation, wherein the serial operation is configured to perform bit shifting operation using a register in a simulation of the IC. The serial operation is blocked from manipulating the register in the simulation of the IC. Using the register in the simulation of the IC, the direct register access operation is performed in place of the serial operation.

  1. CMB lensing tomography with the DES Science Verification galaxies

    DOE PAGES-Beta [OSTI]

    Giannantonio, T.

    2016-01-07

    We measure the cross-correlation between the galaxy density in the Dark Energy Survey (DES) Science Verification data and the lensing of the cosmic microwave background (CMB) as reconstructed with the Planck satellite and the South Pole Telescope (SPT). When using the DES main galaxy sample over the full redshift range 0.2 < zphot < 1.2, a cross-correlation signal is detected at 6σ and 4σ with SPT and Planck respectively. We then divide the DES galaxies into five photometric redshift bins, finding significant (>2σ) detections in all bins. Comparing to the fiducial Planck cosmology, we find the redshift evolution of themore » signal matches expectations, although the amplitude is consistently lower than predicted across redshift bins. We test for possible systematics that could affect our result and find no evidence for significant contamination. Finally, we demonstrate how these measurements can be used to constrain the growth of structure across cosmic time. We find the data are fit by a model in which the amplitude of structure in the z < 1.2 universe is 0.73 ± 0.16 times as large as predicted in the LCDM Planck cosmology, a 1.7σ deviation.« less

  2. Weak lensing by galaxy troughs in DES Science Verification data

    DOE PAGES-Beta [OSTI]

    Gruen, D.; Friedrich, O.; Amara, A.; Bacon, D.; Bonnett, C.; Hartley, W.; Jain, B.; M. Jarvis; Kavprzak, T.; Krause, E.; et al

    2015-11-29

    In this study, we measure the weak lensing shear around galaxy troughs, i.e. the radial alignment of background galaxies relative to underdensities in projections of the foreground galaxy field over a wide range of redshift in Science Verification data from the Dark Energy Survey. Our detection of the shear signal is highly significant (10σ–15σ for the smallest angular scales) for troughs with the redshift range z ϵ [0.2, 0.5] of the projected galaxy field and angular diameters of 10 arcmin…1°. These measurements probe the connection between the galaxy, matter density, and convergence fields. By assuming galaxies are biased tracers ofmore » the matter density with Poissonian noise, we find agreement of our measurements with predictions in a fiducial Λ cold dark matter model. The prediction for the lensing signal on large trough scales is virtually independent of the details of the underlying model for the connection of galaxies and matter. Our comparison of the shear around troughs with that around cylinders with large galaxy counts is consistent with a symmetry between galaxy and matter over- and underdensities. In addition, we measure the two-point angular correlation of troughs with galaxies which, in contrast to the lensing signal, is sensitive to galaxy bias on all scales. The lensing signal of troughs and their clustering with galaxies is therefore a promising probe of the statistical properties of matter underdensities and their connection to the galaxy field.« less

  3. Weak lensing by galaxy troughs in DES Science Verification data

    SciTech Connect (OSTI)

    Gruen, D.; Friedrich, O.; Amara, A.; Bacon, D.; Bonnett, C.; Hartley, W.; Jain, B.; M. Jarvis; Kavprzak, T.; Krause, E.; Mana, A.; Rozo, E.; Rykoff, E. S.; Seitz, S.; Sheldon, E.; Troxel, M. A.; Vikram, V.; Abbott, T. M. C.; Abdalla, F. B.; Allam, S.; Armstrong, R.; Banerji, M.; Bauer, A. H.; Becker, M. R.; Benoit-Levy, A.; Bernstein, G. M.; Bernstein, R. A.; Bertin, E.; Bridle, S. L.; Brooks, D.; Buckley-Geer, E.; Burke, D. L.; Capozzi, D.; Rosell, A. Carnero; Carretero, J.; Crocce, M.; Cunha, C. E.; D'Andrea, C. B.; da Costa, L. N.; DePoy, D. L.; Desai, S.; Diehl, H. T.; Dietrich, J. P.; Doel, P.; Eifler, T. F.; Neto, A. Fausti; Fernandez, E.; Flaugher, B.; Fosalba, P.; Frieman, J.; Gerdes, D. W.; Gruendl, R. A.; Gutierrez, G.; Honscheid, K.; James, D. J.; Kuehn, K.; Kuropatkin, N.; Lahav, O.; Li, T. S.; Lima, M.; Maia, M. A. G.; March, M.; Martini, P.; Melchior, P.; Miller, C. J.; Miguel, R.; Mohr, J. J.; Nord, B.; Orgando, R.; Plazas, A. A.; Reil, K.; Romer, A. K.; Roodman, A.; Sako, M.; Sanchez, E.; Scarpine, V.; Schubnell, M.; Sevilla-Noarbe, I.; Smith, R. C.; Soares-Santos, M.; Sobreira, F.; Suchyta, E.; Swanson, M. E. C.; Tarle, G.; Thaler, J.; Thomas, D.; Walker, A. R.; Wechsler, R. H.; Weller, J.; Zhang, Y.; Zuntz, J.

    2015-11-29

    In this study, we measure the weak lensing shear around galaxy troughs, i.e. the radial alignment of background galaxies relative to underdensities in projections of the foreground galaxy field over a wide range of redshift in Science Verification data from the Dark Energy Survey. Our detection of the shear signal is highly significant (10σ–15σ for the smallest angular scales) for troughs with the redshift range z ϵ [0.2, 0.5] of the projected galaxy field and angular diameters of 10 arcmin…1°. These measurements probe the connection between the galaxy, matter density, and convergence fields. By assuming galaxies are biased tracers of the matter density with Poissonian noise, we find agreement of our measurements with predictions in a fiducial Λ cold dark matter model. The prediction for the lensing signal on large trough scales is virtually independent of the details of the underlying model for the connection of galaxies and matter. Our comparison of the shear around troughs with that around cylinders with large galaxy counts is consistent with a symmetry between galaxy and matter over- and underdensities. In addition, we measure the two-point angular correlation of troughs with galaxies which, in contrast to the lensing signal, is sensitive to galaxy bias on all scales. The lensing signal of troughs and their clustering with galaxies is therefore a promising probe of the statistical properties of matter underdensities and their connection to the galaxy field.

  4. Weak Lensing by Galaxy Troughs in DES Science Verification Data

    SciTech Connect (OSTI)

    Gruen, D.

    2015-09-29

    We measure the weak lensing shear around galaxy troughs, i.e. the radial alignment of background galaxies relative to underdensities in projections of the foreground galaxy field over a wide range of redshift in Science Verification data from the Dark Energy Survey. Our detection of the shear signal is highly significant (10σ–15σ for the smallest angular scales) for troughs with the redshift range z ϵ [0.2, 0.5] of the projected galaxy field and angular diameters of 10 arcmin…1°. These measurements probe the connection between the galaxy, matter density, and convergence fields. By assuming galaxies are biased tracers of the matter density with Poissonian noise, we find agreement of our measurements with predictions in a fiducial Λ cold dark matter model. Furthermore, the prediction for the lensing signal on large trough scales is virtually independent of the details of the underlying model for the connection of galaxies and matter. Our comparison of the shear around troughs with that around cylinders with large galaxy counts is consistent with a symmetry between galaxy and matter over- and underdensities. In addition, we measure the two-point angular correlation of troughs with galaxies which, in contrast to the lensing signal, is sensitive to galaxy bias on all scales. Finally, the lensing signal of troughs and their clustering with galaxies is therefore a promising probe of the statistical properties of matter underdensities and their connection to the galaxy field.

  5. Cosmic Shear Measurements with DES Science Verification Data

    SciTech Connect (OSTI)

    Becker, M. R.

    2015-07-20

    We present measurements of weak gravitational lensing cosmic shear two-point statistics using Dark Energy Survey Science Verification data. We demonstrate that our results are robust to the choice of shear measurement pipeline, either ngmix or im3shape, and robust to the choice of two-point statistic, including both real and Fourier-space statistics. Our results pass a suite of null tests including tests for B-mode contamination and direct tests for any dependence of the two-point functions on a set of 16 observing conditions and galaxy properties, such as seeing, airmass, galaxy color, galaxy magnitude, etc. We use a large suite of simulations to compute the covariance matrix of the cosmic shear measurements and assign statistical significance to our null tests. We find that our covariance matrix is consistent with the halo model prediction, indicating that it has the appropriate level of halo sample variance. We also compare the same jackknife procedure applied to the data and the simulations in order to search for additional sources of noise not captured by the simulations. We find no statistically significant extra sources of noise in the data. The overall detection significance with tomography for our highest source density catalog is 9.7σ. Cosmological constraints from the measurements in this work are presented in a companion paper (DES et al. 2015).

  6. Results of radiological measurements taken in the Niagara Falls, New York, area (NF002)

    SciTech Connect (OSTI)

    Williams, J.K.; Berven, B.A.

    1986-11-01

    The results of a radiological survey of 100 elevated gamma radiation anomalies in the Niagara Falls, New York, area are presented. These radiation anomalies were identified by a mobile gamma scanning survey during the period October 3-16, 1984, and were recommended for an onsite survey to determine if the elevated levels of radiation may be related to the transportation of radioactive waste material to the Lake Ontario Ordnance Works for storage. In this survey, radiological measurements included outdoor gamma exposure rates at 1 m above the surface; outdoor gamma exposure rates at the surface, range of gamma exposure rates during scan; and uranium, radium, and thorium concentrations in biased surface soil samples. The results show 38 anomalies (35 located along Pletcher Road and 3 associated with other unreleated locations) were found to exceed Formerly Utilized Sites Remedial Action Program (FUSRAP) remedial action guidelines and were recommended for formal characterization surveys. (Since the time of this survey, remedial actions have been conducted on the 38 anomalies identified as exceeding FUSRAP guidelines, and the radioactive material above guidelines has been removed.) The remaining 62 anomalies are associated with asphalt driveways and parking lots, which used a phosphate slag material (previously identified as cyclowollastonite, synthetic CaSiO/sub 3/). This rocky-slag waste material was used for bedding under asphalt surfaces and in general gravel applications. Most of the contaminated soil and rock samples collected at the latter anomalies had approximately equal concentrations of /sup 226/Ra and /sup 238/U and, therefore, are not related to materials connected with the Niagara Falls Storage Site (NFSS), including material that was transported to the NFSS. 13 refs., 7 figs., 14 tabs.

  7. CONFIRMATORY SURVEY REPORT FOR THE SECTION 4 AREA AT THE RIO ALGOM AMBROSIA LAKE FACILITY NEW MEXICO

    SciTech Connect (OSTI)

    W.C. Adams

    2010-02-12

    The objectives of the confirmatory survey were to verify that remedial actions were effective in meeting established release criteria and that documentation accurately and adequately described the final radiological conditions of the RAM Ambrosia Lake, Section 4 Areas.

  8. Environmental/Radiological Assistance Directory (ERAD) | Department of

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Energy Environmental/Radiological Assistance Directory (ERAD) Environmental/Radiological Assistance Directory (ERAD) The Environmental Radiological Assistance Directory or ERAD, developed by AU-22, serves as an assistance tool to the DOE complex for protection of the public and environment from radiation. The ERAD is a combination webinar/conference call, designed to provide DOE and its contractors a forum to share information, lessons-learned, best practices, emerging trends, compliance

  9. 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Environmental/Radiological Assistance Directory (ERAD) Presentations 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations 2012 Environmental/Radiological Assistance Directory (ERAD) Presentations November 2012; Environmental Measurements in an Emergency: This is not a Drill!; Stephen V. Musolino; Brookhaven National Laboratory (2.44 MB) November 2012; Brookhaven Graphite Research Reactor (BGRR) D&D Presentation for the DOE ERAD Working Group;

  10. Federal Radiological Monitoring and Assessment Center | National Nuclear

    National Nuclear Security Administration (NNSA)

    Security Administration | (NNSA) Federal Radiological Monitoring and Assessment Center The Federal Radiological Monitoring and Assessment Center (FRMAC) is a federal asset available on request by the Department of Homeland Security (DHS) and state and local agencies to respond to a nuclear or radiological incident. The FRMAC is an interagency organization with representation from the NNSA, the Department of Defense (DOD), the Environmental Protection Agency (EPA), the Department of Health

  11. GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material |

    National Nuclear Security Administration (NNSA)

    National Nuclear Security Administration | (NNSA) GTRI: Removing Vulnerable Civilian Nuclear and Radiological Material May 29, 2014 GTRI's Remove Program works around the world to remove excess nuclear and radiological materials that could be used for a nuclear weapon or radiological dispersal device (RDD), or "dirty bomb". Mission In 2004 NNSA established the Global Threat Reduction Initiative (GTRI) in the Office of Defense Nuclear Nonproliferation to, as quickly as possible,

  12. Nuclear and Radiological Field Training Center | Y-12 National Security

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Complex ... Nuclear and Radiological Field Training Center A site used for nuclear research in Oak Ridge, Tennessee during the Manhattan Project is now the Y-12 National Security Complex's Nuclear and Radiological Field Training Center - the only facility of its kind in the world. The Center provides world-class nuclear and radiological training in a safe, secure, realistic environment using expert instruction and personnel to serve as observers/evaluators for customer training. For military

  13. Surface Contamination Guidelines/Radiological Clearance of Property |

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Department of Energy Surface Contamination Guidelines/Radiological Clearance of Property Surface Contamination Guidelines/Radiological Clearance of Property Authorized limits govern the control and clearance of personal and real property. They are radionuclide concentrations or activity levels approved by DOE to permit the clearance of property from DOE radiological control for either restricted or unrestricted use, consistent with DOE's radiation protection framework and standards for the

  14. DESIGN INFORMATION VERIFICATION FOR NUCLEAR SAFEGUARDS

    SciTech Connect (OSTI)

    Robert S. Bean; Richard R. M. Metcalf; Phillip C. Durst

    2009-07-01

    A critical aspect of international safeguards activities performed by the International Atomic Energy Agency (IAEA) is the verification that facility design and construction (including upgrades and modifications) do not create opportunities for nuclear proliferation. These Design Information Verification activities require that IAEA inspectors compare current and past information about the facility to verify the operator’s declaration of proper use. The actual practice of DIV presents challenges to the inspectors due to the large amount of data generated, concerns about sensitive or proprietary data, the overall complexity of the facility, and the effort required to extract just the safeguards relevant information. Planned and anticipated facilities will (especially in the case of reprocessing plants) be ever larger and increasingly complex, thus exacerbating the challenges. This paper reports the results of a workshop held at the Idaho National Laboratory in March 2009, which considered technologies and methods to address these challenges. The use of 3D Laser Range Finding, Outdoor Visualization System, Gamma-LIDAR, and virtual facility modeling, as well as methods to handle the facility data issues (quantity, sensitivity, and accessibility and portability for the inspector) were presented. The workshop attendees drew conclusions about the use of these techniques with respect to successfully employing them in an operating environment, using a Fuel Conditioning Facility walk-through as a baseline for discussion.

  15. Nonintrusive verification attributes for excess fissile materials

    SciTech Connect (OSTI)

    Nicholas, N.J.; Eccleston, G.W.; Fearey, B.L.

    1997-10-01

    Under US initiatives, over two hundred metric tons of fissile materials have been declared to be excess to national defense needs. These excess materials are in both classified and unclassified forms. The US has expressed the intent to place these materials under international inspections as soon as practicable. To support these commitments, members of the US technical community are examining a variety of nonintrusive approaches (i.e., those that would not reveal classified or sensitive information) for verification of a range of potential declarations for these classified and unclassified materials. The most troublesome and potentially difficult issues involve approaches for international inspection of classified materials. The primary focus of the work to date has been on the measurement of signatures of relevant materials attributes (e.g., element, identification number, isotopic ratios, etc.), especially those related to classified materials and items. The authors are examining potential attributes and related measurement technologies in the context of possible verification approaches. The paper will discuss the current status of these activities, including their development, assessment, and benchmarking status.

  16. Verification and validation for induction heating

    SciTech Connect (OSTI)

    Lam, Kin [Los Alamos National Laboratory; Tippetts, Trevor B [Los Alamos National Laboratory; Allen, David W [NON LANL

    2008-01-01

    Truchas is a software package being developed at LANL within the Telluride project for predicting the complex physical processes in metal alloy casting. The software was designed to be massively parallel, multi-material, multi-physics, and to run on 3D, fully unstructured meshes. This work describes a Verification and Validation assessment of Truchas for simulating the induction heating phase of a casting process. We used existing data from a simple experiment involving the induction heating of a graphite cylinder, as graphite is a common material used for mold assemblies. Because we do not have complete knowledge of all the conditions and properties in this experiment (as is the case in many other experiments), we performed a parameter sensitivity study, modeled the uncertainties of the most sensitive parameters, and quantified how these uncertainties propagate to the Truchas output response. A verification analysis produced estimates of the numerical error of the Truchas solution to our computational model. The outputs from Truchas runs with randomly sampled parameter values were used for the validation study.

  17. SPR Hydrostatic Column Model Verification and Validation.

    SciTech Connect (OSTI)

    Bettin, Giorgia; Lord, David; Rudeen, David Keith

    2015-10-01

    A Hydrostatic Column Model (HCM) was developed to help differentiate between normal "tight" well behavior and small-leak behavior under nitrogen for testing the pressure integrity of crude oil storage wells at the U.S. Strategic Petroleum Reserve. This effort was motivated by steady, yet distinct, pressure behavior of a series of Big Hill caverns that have been placed under nitrogen for extended period of time. This report describes the HCM model, its functional requirements, the model structure and the verification and validation process. Different modes of operation are also described, which illustrate how the software can be used to model extended nitrogen monitoring and Mechanical Integrity Tests by predicting wellhead pressures along with nitrogen interface movements. Model verification has shown that the program runs correctly and it is implemented as intended. The cavern BH101 long term nitrogen test was used to validate the model which showed very good agreement with measured data. This supports the claim that the model is, in fact, capturing the relevant physical phenomena and can be used to make accurate predictions of both wellhead pressure and interface movements.

  18. Radiological Weapons: How Great Is The Danger?

    SciTech Connect (OSTI)

    Moore, G M

    2003-06-01

    One of the underlying purposes of this paper is to provoke thinking about the interplay between the regulation of radioactive materials and the risk of their use in an radiological weapon (RW). Also considered in this paper are the types of RWs that a terrorist might use, the nature of the threat and danger posed by the various types of RWs, the essential elements that must be considered in responding to the terrorist use of an RW, and what steps may need to be taken a priori to minimize the consequences of the inevitable use of an RW. Because radiological dispersal devices (RDDs) have been the focus of so much recent concern and because RDDs are arguably the most likely of RWs to be used by a terrorist group, a major focus of this paper will be on RDDs. Radiological weapons are going to be used by some individual or group, if not this year then next year, or at some time in the foreseeable future. A policy of focusing resources solely on prevention of their use would leave any government open to significant economic disruption when the inevitable use occurs. Preplanning can limit the injuries, property damage, and economic losses that might result from the use of an RW. Moreover, a combination of efforts to prevent and to minimize the impact of RWs may significantly discourage potential users. The dangers from RWs can be dealt with while society continues to enjoy the benefits of nuclear technology that were promised under Atoms for Peace. However, some restructuring of our use of radioactive materials is necessary to ensure that the current and future uses of radioactive materials outweigh the potential disruption caused by misuse of the materials in RWs.

  19. Advanced Waste Management Now Available as Accredited SEP Verification Body

    Energy.gov [DOE]

    The U.S. Department of Energy is pleased to announce that Advanced Waste Management Systems Inc. (AWM) is now a fully accredited Verification Body for Superior Energy Performance™ (SEP). This ANSI-ANAB accreditation enables AWM to provide third-party verification for industrial facilities that wish to demonstrate energy management excellence and sustained energy savings to earn SEP certification.

  20. Radiological Source Term Estimates for the February 14, 2014...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    This document corresponds to Appendix D: Modeling Integrated Summary Report of the Technical Assessment Team Report. Radiological Source Term Estimates for the February 14, 2014 ...

  1. DOE-HDBK-1122-99; Radiological Control Technician Training

    Energy.gov (indexed) [DOE]

    7 Interaction of Radiation with Matter Instructor's Guide 1.07-1 Course Title: Radiological Control Technician Module Title: Interaction of Radiation with Matter Module Number: ...

  2. NNSA Nuclear/Radiological Incident Response | National Nuclear...

    National Nuclear Security Administration (NNSA)

    NNSA NuclearRadiological Incident Response December 01, 2008 The National Nuclear Security Administration (NNSA) has over 60 years of nuclear weapons experience in responding to ...

  3. Fifth Anniversary of Radiological Alarm Response Training for...

    National Nuclear Security Administration (NNSA)

    Fifth Anniversary of Radiological Alarm Response Training for Local Law Enforcement and ... program for local law enforcement and other critical first responders around the country. ...

  4. ORISE: Radiological Terrorism Toolkit | How ORISE is Making a...

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Education (ORISE) distributed more than 400 radiological terrorism toolkits filled with key resources, such as training guidelines, clinical directives, details about radioactive...

  5. An Assessment Of The External Radiological Impact In Areas Of...

    Open Energy Information (Open El) [EERE & EIA]

    Assessment Of The External Radiological Impact In Areas Of Greece With Elevated Natural Radioactivity Jump to: navigation, search OpenEI Reference LibraryAdd to library Journal...

  6. 2013 Environmental/Radiological Assistance Directory (ERAD) Presentati...

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Radiological Assistance Directory (ERAD) meetings PDF icon Nov 2013 Derived Intervention and Response Levels for Tritium Oxide at the Savannah River Site; Tim Janik,...

  7. The Readiness of the Department's Federal Radiological Monitoring...

    Energy.gov (indexed) [DOE]

    However, we did identify issues with aging equipment and potential reliability issues that could adversely impact the timeliness of FRMAC's response to radiological emergencies. ...

  8. DOE-HDBK-1131-98; General Employee Radiological Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... DOE-HDBK-1131-98 iii Course Developers Christine Liner Savannah River Site (Development ... Radiological Controls, Monitoring (Dosimetry), Emergency Procedures, ALARA Program, ...

  9. NNSA, Philippine Nuclear Research Institute to Prevent Radiological...

    National Nuclear Security Administration (NNSA)

    to our shared efforts to prevent nuclear and radiological terrorism and the proliferation of nuclear weapons," said NNSA Deputy Administrator for Defense Nuclear ...

  10. Trending and root cause analysis of TWRS radiological problem reports

    SciTech Connect (OSTI)

    Brown, R.L.

    1997-07-31

    This document provides a uniform method for trending and performing root cause analysis for radiological problem reports at Tank Waste Remediation System (TWRS).

  11. Hospital Triage in First Hours After Nuclear or Radiological...

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    Hospital Triage in the First 24 Hours after a Nuclear or Radiological Disaster Medical professionals with the Radiation Emergency Assistance CenterTraining Site (REACTS) at the...

  12. Radiological Release Event at the Waste Isolation Pilot Plant...

    Energy.gov (indexed) [DOE]

    radiological release occurred at the Department of Energy Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. Because access to the underground was restricted following...

  13. NNSA Receives Excellence Award for Radiological Security Enhancements...

    National Nuclear Security Administration (NNSA)

    ... nuclear propulsion; and responds to nuclear and radiological emergencies in the U.S. and abroad. Visit http:nnsa.energy.gov for more information. ...

  14. DOE-HDBK-1122-99; Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    ... to enable the rescuer to avoid becoming contaminated. has facial contamination?" b. ... the nature of the injuries, the radiological conditions, the location of the injured, etc. ...

  15. DOE-HDBK-1122-99; Radiological Control Technician Training

    Energy.gov (indexed) [DOE]

    PNL; Richland, Wa. 3. DOE-STD-1098-99, "DOE Radiological Control Standard". 4. 10 CFR Part 835 (1998) "Occupational Radiation Protection". 5. "The Health Physics and ...

  16. DOE-HDBK-1122-99; Radiological Control Technician Training

    Energy Savers

    "DOE Radiological Control Standard" (reference TSP project number SAFT- 0039). 4. 10 CFR Part 835 (1998) "Occupational Radiation Protection" Instructional Aids: 1. Overheads 2. ...

  17. DOE-HDBK-1122-99; Radiological Control Technician Training

    Energy Savers

    ... Accordingly, DOE shall ensure radiological measurements, analyses, worker monitoring results and estimates of public exposures are accurate and appropriately made. 10 CFR 835 ...

  18. DOE-HDBK-1122-99; Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    L 2.10.13 State the requirements for removing or releasing materials from any radiological area. References: 1. 10 CFR 835, "Occupational Radiation Protection" (1998) 2. ...

  19. Fifth Anniversary of Radiological Alarm Response Training for...

    National Nuclear Security Administration (NNSA)

    Fifth Anniversary of Radiological Alarm Response Training for Local Law Enforcement and ... Administration's (NNSA) Alarm Response Training (ART) program for local law enforcement ...

  20. NNSA Nuclear/Radiological Incident Response | National Nuclear...

    National Nuclear Security Administration (NNSA)

    December 01, 2008 The National Nuclear Security Administration (NNSA) has over 60 years of nuclear weapons experience in responding to nuclear and radiological accidents and ...

  1. NNSA Nuclear/Radiological Incident Response | National Nuclear...

    National Nuclear Security Administration (NNSA)

    January 01, 2009 The National Nuclear Security Administration (NNSA) has more than 60 years of nuclear weapons experience in responding to nuclear and radiological accidents and ...

  2. DOE-HDBK-1122-99; Radiological Control Technician Training

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    Communication Systems Instructor's Guide 2.02-1 Course Title: Radiological Control Technician Module Title: Communication Systems Module Number: 2.02 Objectives: 2.02.01 Explain ...

  3. Handling and Packaging a Potentially Radiologically Contaminated Patient

    Energy.gov [DOE]

    The purpose of this procedure is to provide guidance to EMS care providers for properly handling and packaging potentially radiologically contaminated patients.

  4. The New Radiological and Environmental Sciences Laboratory (RESL...

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    None File Format: Microsoft Windows WMV File Size: 19 Kb Video of Radiological and Environmental Sciences Laboratory (RESL) Editorial Date December 7, 2011 By Danielle Miller...

  5. Spent Nuclear Fuel (SNF) Multi Canister Overpack (MCO) Design Verification Summary

    SciTech Connect (OSTI)

    GOLDMANN, L.H.

    1999-11-30

    This document summarizes the design verification activities performed on the Multi-canister Overpack design and documents verification plans for design changes during fabrication.

  6. Radiological Control Programs for Special Tritium Compounds

    Office of Energy Efficiency and Renewable Energy (EERE) (indexed site)

    84-2004 SEPTEMBER 2004 CHANGE NOTICE NO. 1 Date June 2006 DOE HANDBOOK RADIOLOGICAL CONTROL PROGRAMS FOR SPECIAL TRITIUM COMPOUNDS U.S. Department of Energy AREA OCSH Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE ii Table of Changes Page Change 67 (near bottom) In row 1, column 2 of the table titled "dosimetric properties" 6 mrem was changed to 6 x 10 -2 mrem Available on the Department of Energy

  7. Radiological Dose Calculations for Fusion Facilities

    SciTech Connect (OSTI)

    Michael L. Abbott; Lee C. Cadwallader; David A. Petti

    2003-04-01

    This report summarizes the results and rationale for radiological dose calculations for the maximally exposed individual during fusion accident conditions. Early doses per unit activity (Sieverts per TeraBecquerel) are given for 535 magnetic fusion isotopes of interest for several release scenarios. These data can be used for accident assessment calculations to determine if the accident consequences exceed Nuclear Regulatory Commission and Department of Energy evaluation guides. A generalized yearly dose estimate for routine releases, based on 1 Terabecquerel unit releases per radionuclide, has also been performed using averaged site parameters and assumed populations. These routine release data are useful for assessing designs against US Environmental Protection Agency yearly release limits.

  8. Progress Continues on Mitigation of Radiological Contamination

    U.S. Department of Energy (DOE) all webpages (Extended Search)

    August 13, 2015 Progress Continues on Mitigation of Radiological Contamination This week, WIPP personnel will complete the installation of the brattice cloth and salt barrier on a 570-foot section of floor in the WIPP underground. The installation process includes rolling the brattice cloth out to cover the entire surface area of the floor and securing it to the ribs (walls) and in the center of the drift (access tunnel). Once the cloth is in place, it is covered with six to eight inches of

  9. Approaches to verification of two-dimensional water quality models

    SciTech Connect (OSTI)

    Butkus, S.R. . Water Quality Dept.)

    1990-11-01

    The verification of a water quality model is the one procedure most needed by decision making evaluating a model predictions, but is often not adequate or done at all. The results of a properly conducted verification provide the decision makers with an estimate of the uncertainty associated with model predictions. Several statistical tests are available for quantifying of the performance of a model. Six methods of verification were evaluated using an application of the BETTER two-dimensional water quality model for Chickamauga reservoir. Model predictions for ten state variables were compared to observed conditions from 1989. Spatial distributions of the verification measures showed the model predictions were generally adequate, except at a few specific locations in the reservoir. The most useful statistics were the mean standard error of the residuals. Quantifiable measures of model performance should be calculated during calibration and verification of future applications of the BETTER model. 25 refs., 5 figs., 7 tabs.

  10. Radiological Contamination Control Training for Laboratory Research

    Energy.gov (indexed) [DOE]

    ... "Radiation Safety Surveys at Medical Institutions." NRC (1991), U.S. Nuclear Regulatory ... ANSI 13.12 (1999), "Surface Radioactivity Guides for Materials, Equipment, and Facilities ...

  11. Federal Radiological Monitoring and Assessment Center Monitoring Manual Volume 1, Operations

    SciTech Connect (OSTI)

    NSTec Aerial Measurement Systems

    2012-07-31

    The Monitoring division is primarily responsible for the coordination and direction of: Aerial measurements to delineate the footprint of radioactive contaminants that have been released into the environment. Monitoring of radiation levels in the environment; Sampling to determine the extent of contaminant deposition in soil, water, air and on vegetation; Preliminary field analyses to quantify soil concentrations or depositions; and Environmental and personal dosimetry for FRMAC field personnel, during a Consequence Management Response Team (CMRT) and Federal Radiological Monitoring and Assessment Center (FRMAC) response. Monitoring and sampling techniques used during CM/FRMAC operations are specifically selected for use during radiological emergencies where large numbers of measurements and samples must be acquired, analyzed, and interpreted in the shortest amount of time possible. In addition, techniques and procedures are flexible so that they can be used during a variety of different scenarios; e.g., accidents involving releases from nuclear reactors, contamination by nuclear waste, nuclear weapon accidents, space vehicle reentries, or contamination from a radiological dispersal device. The Monitoring division also provides technicians to support specific Health and Safety Division activities including: The operation of the Hotline; FRMAC facility surveys; Assistance with Health and Safety at Check Points; and Assistance at population assembly areas which require support from the FRMAC. This volume covers deployment activities, initial FRMAC activities, development and implementation of the monitoring and assessment plan, the briefing of field teams, and the transfer of FRMAC to the EPA.

  12. Nuclear and Radiological Forensics and Attribution Overview

    SciTech Connect (OSTI)

    Smith, D K; Niemeyer, S

    2005-11-04

    The goal of the U.S. Department of Homeland Security (DHS) Nuclear and Radiological Forensics and Attribution Program is to develop the technical capability for the nation to rapidly, accurately, and credibly attribute the origins and pathways of interdicted or collected materials, intact nuclear devices, and radiological dispersal devices. A robust attribution capability contributes to threat assessment, prevention, and deterrence of nuclear terrorism; it also supports the Federal Bureau of Investigation (FBI) in its investigative mission to prevent and respond to nuclear terrorism. Development of the capability involves two major elements: (1) the ability to collect evidence and make forensic measurements, and (2) the ability to interpret the forensic data. The Program leverages the existing capability throughout the U.S. Department of Energy (DOE) national laboratory complex in a way that meets the requirements of the FBI and other government users. At the same time the capability is being developed, the Program also conducts investigations for a variety of sponsors using the current capability. The combination of operations and R&D in one program helps to ensure a strong linkage between the needs of the user community and the scientific development.

  13. Digital Surveying Directional Surveying Specialists | Open Energy...

    Open Energy Information (Open El) [EERE & EIA]

    Surveying Specialists Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Digital Surveying Directional Surveying Specialists Author Directional Surveying...

  14. SU-E-E-06: Teaching Medical Physics in a Radiology Museum

    SciTech Connect (OSTI)

    Bednarek, D; Rudin, S

    2014-06-01

    Purpose: To enhance the learning process in the teaching of medical physics by providing a venue to experience the historical equipment and devices of radiology. Methods: We have created a museum by assembling a large collection of equipment and artifacts related to radiology and medical physics. As part of a learning-in-context educational approach, classes for a survey course in medical physics are held in the museum so that students are able to visually and tangibly experience the implements of radiology, while related topics are discussed. The students learn how x-ray equipment and techniques evolved throughout the years and they learn to appreciate the differences and similarities between current x-ray technology and that of the early days. The collection contains items dating from the era of the discovery of x-rays up to recent times and includes gas x-ray tubes, hand-held fluoroscopes, generators, spark-gap kV meters, stereoscopes, glass-plate radiographs, a photofluorographic unit, wood-interspaced grid, flat-panel detector, linear-accelerator klystron, and brachytherapy radium applicators, as well as an extensive library containing some of the seminal literature of the field so that students can delve deeper into the technology. In addition to the classes, guided tours are provided for radiologic-technology, bioengineering, physics and medical students, as well as group and individual tours for the general public. Results: Student course assessments have consistently included positive expressions of their experience in the museum. Numerous students have volunteered to assist with display preparation and have learned by researching the content. Many individuals have been attracted on a walk-in basis and have expressed a deep curiosity in the technology, with positive feedback. Conclusion: The museum and its artifacts have been invaluable in stimulating interest in the history and technology of medical physics. Students and visitors alike obtain a deeper

  15. MOV reliability evaluation and periodic verification scheduling

    SciTech Connect (OSTI)

    Bunte, B.D.

    1996-12-01

    The purpose of this paper is to establish a periodic verification testing schedule based on the expected long term reliability of gate or globe motor operated valves (MOVs). The methodology in this position paper determines the nominal (best estimate) design margin for any MOV based on the best available information pertaining to the MOVs design requirements, design parameters, existing hardware design, and present setup. The uncertainty in this margin is then determined using statistical means. By comparing the nominal margin to the uncertainty, the reliability of the MOV is estimated. The methodology is appropriate for evaluating the reliability of MOVs in the GL 89-10 program. It may be used following periodic testing to evaluate and trend MOV performance and reliability. It may also be used to evaluate the impact of proposed modifications and maintenance activities such as packing adjustments. In addition, it may be used to assess the impact of new information of a generic nature which impacts safety related MOVs.

  16. Nevada Test Site Radiological Control Manual. Revision 1

    SciTech Connect (OSTI)

    None, None

    2010-02-09

    This document supersedes DOE/NV/25946--801, “Nevada Test Site Radiological Control Manual,” Revision 0 issued in October 2009. Brief Description of Revision: A minor revision to correct oversights made during revision to incorporate the 10 CFR 835 Update; and for use as a reference document for Tenant Organization Radiological Protection Programs.

  17. FRMAC Interactions During a Radiological or Nuclear Event

    SciTech Connect (OSTI)

    Wong, C T

    2011-01-27

    During a radiological or nuclear event of national significance the Federal Radiological Emergency Monitoring and Assessment Center (FRMAC) assists federal, state, tribal, and local authorities by providing timely, high-quality predictions, measurements, analyses and assessments to promote efficient and effective emergency response for protection of the public and the environment from the consequences of such an event.

  18. Current Trends in Gamma Ray Detection for Radiological Emergency Response

    SciTech Connect (OSTI)

    Mukhopadhyay, S., Guss, P., Maurer, R.

    2011-08-18

    Passive and active detection of gamma rays from shielded radioactive materials, including special nuclear materials, is an important task for any radiological emergency response organization. This article reports on the current trends and status of gamma radiation detection objectives and measurement techniques as applied to nonproliferation and radiological emergencies.

  19. Independent Confirmatory Survey Summary and Results for the Plum Brook Reactor Facility Sandusky OH

    SciTech Connect (OSTI)

    E.N. Bailey

    2008-05-06

    The objectives of the confirmatory survey activities were to provide independent contractor field data reviews and to generate independent radiological data for use by the Nuclear Regulatory Commission (NRC) in evaluating the adequacy and accuracy of the licensee’s procedures and final status survey (FSS) results.

  20. Confirmatory Survey of the Fuel Oil Tank Area - Humboldt Bay Power Plant, Eureka, California

    SciTech Connect (OSTI)

    ADAMS, WADE C

    2012-04-09

    During the period of February 14 to 15, 2012, ORISE performed radiological confirmatory survey activities for the former Fuel Oil Tank Area (FOTA) and additional radiological surveys of portions of the Humboldt Bay Power Plant site in Eureka, California. The radiological survey results demonstrate that residual surface soil contamination was not present significantly above background levels within the FOTA. Therefore, it is ORISE’s opinion that the radiological conditions for the FOTA surveyed by ORISE are commensurate with the site release criteria for final status surveys as specified in PG&E’s Characterization Survey Planning Worksheet. In addition, the confirmatory results indicated that the ORISE FOTA survey unit Cs-137 mean concentrations results compared favorably with the PG&E FOTA Cs-137 mean concentration results, as determined by ORISE from the PG&E characterization data. The interlaboratory comparison analyses of the three soil samples analyzed by PG&E’s onsite laboratory and the ORISE laboratory indicated good agreement for the sample results and provided confidence in the PG&E analytical procedures and final status survey soil sample data reporting.